Sample records for material testing solutions

  1. Atlas Material Testing Solutions | Open Energy Information

    Open Energy Info (EERE)

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE: Alternative Fuels Data Center Home Page on Google Bookmark EERE: Alternative Fuels Data Center Home Page on Office of InspectorConcentrating SolarElectricEnergyCT BiomassArnprior, Ontario: EnergyAskjaAtlas Material Testing

  2. Standard test method for nondestructive analysis of special nuclear materials in homogeneous solutions by Gamma-Ray spectrometry

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01T23:59:59.000Z

    1.1 This test method covers the determination of the concentration of gamma-ray emitting special nuclear materials dissolved in homogeneous solutions. The test method corrects for gamma-ray attenuation by the solution and its container by measurement of the transmission of a beam of gamma rays from an external source (Refs. (1), (2), and (3)). 1.2 Two solution geometries, slab and cylinder, are considered. The solution container that determines the geometry may be either a removable or a fixed geometry container. This test method is limited to solution containers having walls or a top and bottom of equal transmission through which the gamma rays from the external transmission correction source must pass. 1.3 This test method is typically applied to radionuclide concentrations ranging from a few milligrams per litre to several hundred grams per litre. The assay range will be a function of the specific activity of the nuclide of interest, the physical characteristics of the solution container, counting equip...

  3. Materials Solutions for Hydrogen Delivery in Pipelines

    E-Print Network [OSTI]

    Materials Solutions for Hydrogen Delivery in Pipelines Dr. Subodh K. Das Secat, Inc. September of new pipeline infrastructure Develop barrier coatings for minimizing hydrogen permeation in pipelines;NACE Hydrogen Induced Cracking (HIC) Test Evaluates resistance of pipeline and pressure vessel

  4. Solutions to Test 1

    E-Print Network [OSTI]

    Owner

    2014-03-06T23:59:59.000Z

    Math 373. Spring 2013. Test 1. February 12, 2013. 1. Tracy is receiving an annuity immediate with quarterly payments of 250 for 10 years. Tracy invests each ...

  5. Solutions to Test 1

    E-Print Network [OSTI]

    jeffb_000

    2014-03-04T23:59:59.000Z

    STAT 479. Spring 2014. Test 1. February 18, 2014. 1. You are given the following empirical distribution of losses: 300 500 700 800 1000 1400. An insurance ...

  6. Solutions to Test 2

    E-Print Network [OSTI]

    Microsoft account

    2015-01-14T23:59:59.000Z

    Jan 14, 2015 ... Test 2. Fall 2014. October 28, 2014. 1. Joon is going to buy a 10 year callable bond. The bond matures for 15,000 and pays semi-annual.

  7. Solutions to Test 3

    E-Print Network [OSTI]

    jeffb_000

    2014-08-16T23:59:59.000Z

    Math 373. Test 3. Spring 2014. April 8, 2014. 1. Yujin can buy each of the following bonds for a price of P . The bonds are: a. A 10 year zero coupon bond ...

  8. Solutions to Test 1

    E-Print Network [OSTI]

    jeffb_000

    2014-08-16T23:59:59.000Z

    MATH 373. Spring 2014. Test 1. February 18, 2013. 1. Amar wants to accumulate 1 million (1,000,000) by the time that he is 50 years old. Amar is currently 20 ...

  9. Solutions to Test 2

    E-Print Network [OSTI]

    jeffb_000

    2014-04-14T23:59:59.000Z

    STAT 479. Test 2. Spring 2014. April 1, 2014. 1. (5 points) You are given the following grouped data: Amount of claims. Number of Claims. 0 to 1000. 8. 1000 to ...

  10. Solutions to Test 1

    E-Print Network [OSTI]

    Microsoft account

    2014-10-24T23:59:59.000Z

    Test 1. STAT 47201. Fall 2014. October 7, 2014. 1. You are given: i. Mortality follows the illustrative life table ii. 6% i = Calculate: a. The actuarial present value

  11. Solutions to Test 1

    E-Print Network [OSTI]

    jeffb_000

    2014-02-16T23:59:59.000Z

    Test 1. September 26, 2013. 1. Zach buys a billiards table for his apartment. The cost of the table is 4000 and he uses a loan to pay for the table. The loan will be ...

  12. Solutions to Test 2

    E-Print Network [OSTI]

    Test 2. Spring 2013. March 5, 2013. 1. Jana purchased a 20 year zero coupon bond for 20,000. The bond matures for 70,000. Christian borrowed 50,000 to be ...

  13. Solutions to Test 1

    E-Print Network [OSTI]

    Owner

    2014-03-09T23:59:59.000Z

    March 9, 2014. Math 373. Test 1. Fall 2012. September 27, 2012. 1. Meng takes out a loan to buy a new motorcycle. The amount of the loan is 12,500. Meng will.

  14. Solutions to Test 2

    E-Print Network [OSTI]

    jeffb_000

    2014-03-26T23:59:59.000Z

    March 27, 2014. Math 373. Test 2. Fall 2013. October 17, 2013. 1. You are given the following table of interest rates: Year 1. Year 2. Year 3. Portfolio. Year. 2007.

  15. Solutions to Test 3

    E-Print Network [OSTI]

    jeffb_000

    2014-04-05T23:59:59.000Z

    April 5, 2014. Math 373. Test 3. Fall 2013. November 7, 2013. 1. You are given the following spot interest rate curve: Time t. Spot Rate tr. 0.5. 3.2%. 1.0. 3.5%. 1.5.

  16. Radioactive material package seal tests

    SciTech Connect (OSTI)

    Madsen, M.M.; Humphreys, D.L.; Edwards, K.R.

    1990-01-01T23:59:59.000Z

    General design or test performance requirements for radioactive materials (RAM) packages are specified in Title 10 of the US Code of Federal Regulations Part 71 (US Nuclear Regulatory Commission, 1983). The requirements for Type B packages provide a broad range of environments under which the system must contain the RAM without posing a threat to health or property. Seals that provide the containment system interface between the packaging body and the closure must function in both high- and low-temperature environments under dynamic and static conditions. A seal technology program, jointly funded by the US Department of Energy Office of Environmental Restoration and Waste Management (EM) and the Office of Civilian Radioactive Waste Management (OCRWM), was initiated at Sandia National Laboratories. Experiments were performed in this program to characterize the behavior of several static seal materials at low temperatures. Helium leak tests on face seals were used to compare the materials. Materials tested include butyl, neoprene, ethylene propylene, fluorosilicone, silicone, Eypel, Kalrez, Teflon, fluorocarbon, and Teflon/silicone composites. Because most elastomer O-ring applications are for hydraulic systems, manufacturer low-temperature ratings are based on methods that simulate this use. The seal materials tested in this program with a fixture similar to a RAM cask closure, with the exception of silicone S613-60, are not leak tight (1.0 {times} 10{sup {minus}7} std cm{sup 3}/s) at manufacturer low-temperature ratings. 8 refs., 3 figs., 1 tab.

  17. Use of advanced composite materials for innovative building design solutions/

    E-Print Network [OSTI]

    Lau, Tak-bun, Denvid

    2009-01-01T23:59:59.000Z

    Advanced composite materials become popular in construction industry for the innovative building design solutions including strengthening and retrofitting of existing structures. The interface between different materials ...

  18. Nondestructive ultrasonic testing of materials

    DOE Patents [OSTI]

    Hildebrand, Bernard P. (Richland, WA)

    1994-01-01T23:59:59.000Z

    Reflection wave forms obtained from aged and unaged material samples can be compared in order to indicate trends toward age-related flaws. Statistical comparison of a large number of data points from such wave forms can indicate changes in the microstructure of the material due to aging. The process is useful for predicting when flaws may occur in structural elements of high risk structures such as nuclear power plants, airplanes, and bridges.

  19. Nondestructive ultrasonic testing of materials

    DOE Patents [OSTI]

    Hildebrand, B.P.

    1994-08-02T23:59:59.000Z

    Reflection wave forms obtained from aged and unaged material samples can be compared in order to indicate trends toward age-related flaws. Statistical comparison of a large number of data points from such wave forms can indicate changes in the microstructure of the material due to aging. The process is useful for predicting when flaws may occur in structural elements of high risk structures such as nuclear power plants, airplanes, and bridges. 4 figs.

  20. STRUCTURES AND MATERIALS TEST LABORATORY

    E-Print Network [OSTI]

    Russell, Jeffrey S.

    that are on important haul routes for logging trucks were examined. Two of the seven bridges were judged to be load that there is no direct solution for avoiding load posting of bridges on important timber hauling highway routes been allowed to deteriorate combined with trucks that are carrying heavier loads. Any fix

  1. CORROSION TESTING IN SIMULATED TANK SOLUTIONS

    SciTech Connect (OSTI)

    Hoffman, E.

    2010-12-09T23:59:59.000Z

    Three simulated waste solutions representing wastes from tanks SY-102 (high nitrate, modified to exceed guidance limits), AN-107, and AY-102 were supplied by PNNL. Out of the three solutions tested, both optical and electrochemical results show that carbon steel samples corroded much faster in SY-102 (high nitrate) than in the other two solutions with lower ratios of nitrate to nitrite. The effect of the surface preparation was not as strong as the effect of solution chemistry. In areas with pristine mill-scale surface, no corrosion occurred even in the SY-102 (high nitrate) solution, however, corrosion occurred in the areas where the mill-scale was damaged or flaked off due to machining. Localized corrosion in the form of pitting in the vapor space of tank walls is an ongoing challenge to overcome in maintaining the structural integrity of the liquid waste tanks at the Savannah River and Hanford Sites. It has been shown that the liquid waste condensate chemistry influences the amount of corrosion that occurs along the walls of the storage tanks. To minimize pitting corrosion, an effort is underway to gain an understanding of the pitting response in various simulated waste solutions. Electrochemical testing has been used as an accelerated tool in the investigation of pitting corrosion. While significant effort has been undertaken to evaluate the pitting susceptibility of carbon steel in various simulated waste solutions, additional effort is needed to evaluate the effect of liquid waste supernates from six Hanford Site tanks (AY-101, AY-102, AN-102, AN-107, SY-102 (high Cl{sup -}), and SY-102 (high nitrate)) on carbon steel. Solutions were formulated at PNNL to replicate tank conditions, and in the case of SY-102, exceed Cl{sup -} and NO{sub 3}{sup -} conditions, respectively, to provide a contrast between in and out of specification limits. The majority of previous testing has been performed on pristine polished samples. To evaluate the actual tank carbon steel surface, efforts are needed to compare the polished surfaces to corroded and mill-scale surfaces, which are more likely to occur in application. Additionally, due to the change in liquid waste levels within the tanks, salt deposits are highly likely to be present along the tank wall. When the level of the tank decreases, a salt deposit will form as the solution evaporates. The effects of this pre-existing salt, or supernate deposit, are unknown at this time on the corrosion effect and thus require investigation. Additionally, in the presence of radiation, moist air undergoes radiolysis, forming a corrosive nitric acid condensate. This condensate could accelerate the corrosion process in the vapor space. To investigate this process, an experimental apparatus simulating the effects of radiation was designed and constructed to provide gamma irradiation while coupons are exposed to a simulate tank solution. Additionally, ammonia vapors will also be introduced to further represent the tank environment.

  2. Sludge stabilization boat material test plan

    SciTech Connect (OSTI)

    De Vries, M.L.

    1995-04-05T23:59:59.000Z

    This document provides instructions for testing different types of potential boat materials in the HC-21C muffle furnace process. The boats must withstand corrosive environments at up to 1000 degrees C.

  3. Materials Solutions for Hydrogen Delivery in Pipelines

    SciTech Connect (OSTI)

    Ningileri, Shridas T.; Boggess, Todd A; Stalheim, Douglas

    2013-01-02T23:59:59.000Z

    The main objective of the study is as follows: Identify steel compositions/microstructures suitable for construction of new pipeline infrastructure and evaluate the potential use of the existing steel pipeline infrastructure in high pressure gaseous hydrogen applications. The microstructures of four pipeline steels were characterized and tensile testing was conducted in gaseous hydrogen and helium at pressures of 5.5 MPa (800 psi), 11 MPa (1600 psi) and 20.7 MPa (3000 psi). Based on reduction of area, two of the four steels that performed the best across the pressure range were selected for evaluation of fracture and fatigue performance in gaseous hydrogen at 5.5 MPa (800 psi) and 20.7 MPa (3000 psi). The basic format for this phase of the study is as follows: Microstructural characterization of volume fraction of phases in each alloy; Tensile testing of all four alloys in He and H{sub 2} at 5.5 MPa (800 psi), 11 MPa (1600 psi), and 20.7 MPa (3000 psi). RA performance was used to choose the two best performers for further mechanical property evaluation; Fracture testing (ASTM E1820) of two best tensile test performers in H{sub 2} at 5.5 MPa (800 psi) and 20.7 MPa (3000 psi); Fatigue testing (ASTM E647) of two best tensile test performers in H2 at 5.5 MPa (800 psi) and 20.7 MPa (3000 psi) with frequency =1.0 Hz and R-ratio=0.5 and 0.1.

  4. Active Waste Materials Corrosion and Decontamination Tests

    SciTech Connect (OSTI)

    MJ Danielson; MR Elmore; SG Pitman

    2000-08-15T23:59:59.000Z

    Stainless steel alloys, 304L and 316L, were corrosion tested in representative radioactive samples of three actual Hanford tank waste solutions (Tanks AW-101, C-104, AN-107). Both the 304L and 316L exhibited good corrosion performance when immersed in boiling waste solutions. The maximum general corrosion rate was 0.015 mm/y (0.60 mils per year). Generally, the 304L had a slightly higher rate than the 316L. No localized attack was observed after 122 days of testing in the liquid phase, liquid/vapor phase, or vapor phase. Radioactive plate-out decontamination tests indicated that a 24-hour exposure to 1 {und M} HNO{sub 3} could remove about 99% of the radioactive components in the metal film when exposed to the C-104 and AN-107 solutions. The decontamination results are less certain for the AW-101 solution, since the initial contamination readings exceeded the capacity of the meter used for this test.

  5. SCREENING TESTS FOR IMPROVED METHANE CRACKING MATERIALS

    SciTech Connect (OSTI)

    Klein, J; Jeffrey Holder, J

    2007-07-16T23:59:59.000Z

    Bench scale (1 to 6 gram) methane cracking tests have been performed on a variety of pure elements, some alloys, and SAES{reg_sign} commercial getters St 101, St 198, St 707, St 737, and St 909 to determine methane cracking performance (MCP) of 5% methane in a helium carrier at 700 C, 101.3 kPa (760 torr) with a 10 sccm feed. The MCP was almost absent from some materials tested while others showed varying degrees of MCP. Re, Cr, V, Gd, and Mo powders had good MCP, but limited capacities. Nickel supported on kieselguhr (Ni/k), a Zr-Ni alloy, and the SAES{reg_sign} getters had good MCP in a helium carrier. The MCP of these same materials was suppressed in a hydrogen carrier stream and the MCP of the Zr-based materials was reduced by nitride formation when tested with a nitrogen carrier gas.

  6. Coal Ash Corrosion Resistant Materials Testing Program

    SciTech Connect (OSTI)

    McDonald, D.K.

    2003-04-22T23:59:59.000Z

    The "Coal Ash Corrosion Resistant Materials Testing Program" is being conducted by The Babcock & Wilcox Company (B&W), the U.S. Department of Energy (DOE) and the Ohio Coal Development Office (OCDO) at Reliant Energy?s Niles plant in Niles, Ohio to provide full-scale, in-situ testing of recently developed boiler superheater materials. Fireside corrosion is a key issue for improving efficiency of new coal fired power plants and improving service life in existing plants. In November 1998, B&W began development of a system to permit testing of advanced tube materials at metal temperatures typical of advanced supercritical steam temperatures (1100°F and higher) in a boiler exhibiting coal ash corrosive conditions. Several materials producers including Oak Ridge National Laboratory (ORNL) contributed advanced materials to the project. In the spring of 1999 a system consisting of three identical sections, each containing multiple segments of twelve different materials, was installed. The sections are cooled by reheat steam, and are located just above the furnace entrance in Niles? Unit #1, a 110 MWe unit firing high sulfur Ohio coal. In November 2001 the first section was removed for thorough metallurgical evaluation after 33 months of operation. The second and third sections remain in service and the second is expected to be removed in the fall of 2003; the last is tentatively planned for the fall of 2004. This paper describes the program; its importance; the design, fabrication, installation and operation of the test system; materials utilized; experience to date; and results of the evaluation of the first section.

  7. Electrochemical Corrosion Testing of Neutron Absorber Materials

    SciTech Connect (OSTI)

    Tedd Lister; Ron Mizia; Arnold Erickson; Tammy Trowbridge

    2007-05-01T23:59:59.000Z

    This report summarizes the results of crevice-corrosion tests for six alloys in solutions representative of ionic compositions inside the Yucca Mountain waste package should a breech occur. The alloys in these tests are Neutronit A978a (ingot metallurgy, hot rolled), Neutrosorb Plus 304B4 Grade Ab (powder metallurgy, hot rolled), Neutrosorb Plus 304B5 Grade Ab (powder metallurgy, hot rolled), Neutrosorb Plus 304B6 Grade Ab (powder metallurgy, hot rolled), Ni-Cr-Mo-Gd alloy2 (ingot metallurgy, hot rolled), and Alloy 22 (ingot metallurgy, hot rolled).

  8. Integrated Performance Testing Workshop - Supplemental Materials (Scripts and Procedures)

    SciTech Connect (OSTI)

    Baum, Gregory A.

    2014-02-01T23:59:59.000Z

    A variety of performance tests are described relating to: Material Transfers; Emergency Evacuation; Alarm Response Assessment; and an Enhanced Limited Scope Performance Test (ELSPT). Procedures are given for: nuclear material physical inventory and discrepancy; material transfers; and emergency evacuation.

  9. Coal Ash Corrosion Resistant Materials Testing

    SciTech Connect (OSTI)

    D. K. McDonald; P. L. Daniel; D. J. DeVault

    2007-12-31T23:59:59.000Z

    In April 1999, three identical superheater test sections were installed into the Niles Unit No.1 for the purpose of testing and ranking the coal ash corrosion resistance of candidate superheater alloys. The Niles boiler burns high sulfur coal (3% to 3.5%) that has a moderate alkali content (0.2% sodium equivalents), thus the constituents necessary for coal ash corrosion are present in the ash. The test sections were controlled to operate with an average surface metal temperature from approximately 1060 F to 1210 F which was within the temperature range over which coal ash corrosion occurs. Thus, this combination of aggressive environment and high temperature was appropriate for testing the performance of candidate corrosion-resistant tube materials. Analyses of the deposit and scale confirmed that aggressive alkali sulfate constituents were present at the metal surface and active in tube metal wastage. The test sections were constructed so that the response of twelve different candidate tube and/or coating materials could be studied. The plan was to remove and evaluate one of the three test sections at time intervals of 1 year, 3 years, and 5 years. This would permit an assessment of performance of the candidate materials as a function of time. Test Section A was removed in November 2001 after about 24 months of service at the desired steam temperature set point, with about 15.5 months of exposure at full temperature. A progress report, issued in October 2002, was written to document the performance of the candidate alloys in that test section. The evaluation described the condition of each tube sample after exposure. It involved a determination of the rate of wall thickness loss for these samples. In cases where there was more than one sample of a candidate material in the test section, an assessment was made of the performance of the alloy as a function of temperature. Test Sections B and C were examined during the November 2001 outage, and it was decided that, due to excessive wastage, certain tube samples needed to be removed and replaced in order to ensure that Test Sections B and C would have a chance of remaining in the boiler for their intended exposure period. These suspect tube samples were replaced and the two remaining test sections were put back into service. The tube samples that were removed from Test Sections B and C were set aside for later analysis at the end of the planned exposure period. Test Sections B and C were again examined approximately six months later. At that time, measured wall thickness losses raised concerns about additional tube samples. These suspect samples were also removed, set aside for later analysis, and replaced. The test sections then went back into service until the end of the second exposure period, which was concluded in May 2003 when, due to evidence of excessive wastage, the valves were opened increasing cooling steam flow and thereby effectively stopping corrosion. In August 2003, Test Sections B and C were removed for closer examination. Section C had experienced about 42 months of service at the desired team temperature set point with 28.5 months at temperature at full temperature. Additional suspect samples were removed from Test Section B, then, it was re-installed into the boiler (at the location originally occupied by Section C), where it remained in service until the end of the program. Due to this removal history, the samples from Test Section B had a total service duration that varied from a minimum of 15.5 months (for samples that performed poorly) to 37 months for samples the survived for the full intended service exposure for Section B. The figure below shows a schematic of Test Section B and indicates the length of service exposure for different locations. This report provides the results of the evaluation of Test Section B, including the samples that remained in the Test Section for the full exposure period as well as those that were removed early. This report also is intended to compare and summarize the results for all three test sections. The analysis of T

  10. THE CORROSION OF SILICATE MATERIALS BY HYDROGEN GAS AND HYDROFLUORIC ACID SOLUTION

    E-Print Network [OSTI]

    Tso, Stephen T.

    2011-01-01T23:59:59.000Z

    THE CORROSION OF SILICATE MATERIALS BY HYDROGEN GAS ANDApparatus II. Hydrogen Gas Corrosion, HydrofluoricAcid Solution Corrosion. Material Preparation, , , ,

  11. Test device for measuring permeability of a barrier material

    DOE Patents [OSTI]

    Reese, Matthew; Dameron, Arrelaine; Kempe, Michael

    2014-03-04T23:59:59.000Z

    A test device for measuring permeability of a barrier material. An exemplary device comprises a test card having a thin-film conductor-pattern formed thereon and an edge seal which seals the test card to the barrier material. Another exemplary embodiment is an electrical calcium test device comprising: a test card an impermeable spacer, an edge seal which seals the test card to the spacer and an edge seal which seals the spacer to the barrier material.

  12. Sandia National Laboratories: New Material Tests Show Biaxial...

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

    Material Tests Show Biaxial Laminate Creep Is Important for Large Wind-Turbine Blades New Material Tests Show Biaxial Laminate Creep Is Important for Large Wind-Turbine Blades...

  13. ESP – Data from Restarted Life Tests of Various Silicon Materials

    SciTech Connect (OSTI)

    Schneider, Jim

    2010-10-06T23:59:59.000Z

    Current funding has allowed the restart of testing of various silicone materials placed in Life Tests or Aging Studies from past efforts. Some of these materials have been in test since 1982, with no testing for approximately 10 years, until funding allowed the restart in FY97. Charts for the various materials at different thickness, compression, and temperature combinations illustrate trends for the load-bearing properties of the materials.

  14. Survey of hazardous materials used in nuclear testing

    SciTech Connect (OSTI)

    Bryant, E.A.; Fabryka-Martin, J.

    1991-02-01T23:59:59.000Z

    The use of hazardous'' materials in routine underground nuclear tests at the Nevada Test Site has been reviewed. In addition the inventory of test yields, originally reported in 1976 has been updated. A trail down-hole inventory'' has been conducted for a selected test. The inorganic hazardous materials introduced during testing (with the exception of lead and the fissionable materials) produce an incremental change in the quantity of such materials already present in the geologic media surrounding the test points. 1 ref., 3 tabs.

  15. Adsorbent materials development and testing for the extraction of uranium from seawater

    SciTech Connect (OSTI)

    Felker, L.K.; Dai, S.; Hay, B.P.; Janke, C.J.; Mayes, R.T.; Sun, X.; Tsouris, C. [Oak Ridge National Laboratory, Oak Ridge, Tennessee, 37831-6384 (United States)

    2013-07-01T23:59:59.000Z

    The extraction of uranium from seawater has been the focus of a research project for the U.S. Department of Energy to develop amidoxime functional group adsorbents using radiation-induced graphing on polymer-based fiber materials and subsequent chemical conversion of the radical sites to form the desired adsorbent material. Materials with promising uranium adsorption capacities were prepared through a series of parametric studies on radiation dose, time, temperature, graphing solutions, and properties of the base polymer materials. A laboratory screening protocol was developed to determine the uranium adsorption capacity to identify the most promising candidate materials for seawater testing. (authors)

  16. Module Encapsulation Materials, Processing and Testing (Presentation...

    Office of Scientific and Technical Information (OSTI)

    Exposure EVA Yellowing Rate is: 1. dependant on product formulation 2. higher under solar simulator (7 UV suns) than in weatherometer (2.5 UV suns) 3. different in two test...

  17. Test plan for the irradiation of nonmetallic materials.

    SciTech Connect (OSTI)

    Brush, Laurence H.; Farnum, Cathy Ottinger; Dahl, M. [ARES Corporation, Richland, WA; Joslyn, C. C. [Washington River Protection Solutions, Richland, WA; Venetz, T. J. [Washington River Protection Solutions, Richland, WA

    2013-05-01T23:59:59.000Z

    A comprehensive test program to evaluate nonmetallic materials use in the Hanford tank farms is described in detail. This test program determines the effects of simultaneous multiple stressors at reasonable conditions on in-service configuration components by engineering performance testing.

  18. Test plan for the irradiation of nonmetallic materials.

    SciTech Connect (OSTI)

    Brush, Laurence H.; Farnum, Cathy Ottinger; Gelbard, Fred; Dahl, M. [ARES Corporation, Richland, WA; Joslyn, C. C. [Washington River Protection Solutions, Richland, WA; Venetz, T. J. [Washington River Protection Solutions, Richland, WA

    2013-03-01T23:59:59.000Z

    A comprehensive test program to evaluate nonmetallic materials use in the Hanford Tank Farms is described in detail. This test program determines the effects of simultaneous multiple stressors at reasonable conditions on in-service configuration components by engineering performance testing.

  19. Long term materials test program. Preliminary operations plan

    SciTech Connect (OSTI)

    None

    1980-03-01T23:59:59.000Z

    The Long Term Materials Testing (LTMT) PFB facility has been designed to duplicate the design point condition of the Coal-Fired Combined Cycle (CFCC) reference commercial plant design developed by GE under contract to DOE, including bed temperature (1750/sup 0/F), pressure (10 atm), excess air (20%), and gas residence time (1.8 sec). The test rig has a one foot diameter bed and consumes about 1.6 tons/day of coal and 0.5 tons/day of dolomite sulphur sorbent. Material specimens are contained in two test sections. The low velocity test section houses 132 pin specimens 1/4 dia., sixty of which can be cooled below the gas stream temperature. The nominal exposure environment of 1650/sup 0/F, 10 atm, 27 fps should ensure representative corrosive conditions, without erosion. The control system for the LTMT facility is designed to operate the rig in such a manner that the test specimens are subjected to constant, controlled conditions representative of the actual service environment. The Preliminary Test Plan presented in Section V outlines three phases of PFB testing, plus screening tests for candidate materials. Operating costs have been updated to reflect the preliminary rig design data and current raw material quotes. The projected operating costs have been effected by raw material costs since the time of the original estimate, but the overall cost per hour of test is still very low: $122/test hour.

  20. Construction materials as a waste management solution for cellulose sludge

    SciTech Connect (OSTI)

    Modolo, R., E-mail: regina.modolo@ua.pt [University of Aveiro, Civil Engineering Department/CICECO, 3810-193 Aveiro (Portugal); Ferreira, V.M. [University of Aveiro, Civil Engineering Department/CICECO, 3810-193 Aveiro (Portugal); Machado, L.M. [RAIZ - Forest and Paper Research Institute, Portucel-Soporcel, Eixo (Portugal); Rodrigues, M.; Coelho, I. [CIMIANTO - Sociedade Tecnica Hidraulica, S.A., Alhandra (Portugal)

    2011-02-15T23:59:59.000Z

    Sustainable waste management system for effluents treatment sludge has been a pressing issue for pulp and paper sector. Recycling is always recommended in terms of environmental sustainability. Following an approach of waste valorisation, this work aims to demonstrate the technical viability of producing fiber-cement roof sheets incorporating cellulose primary sludge generated on paper and pulp mills. From the results obtained with preliminary studies it was possible to verify the possibility of producing fiber-cement sheets by replacing 25% of the conventional used virgin long fiber by primary effluent treatment cellulose sludge. This amount of incorporation was tested on an industrial scale. Environmental parameters related to water and waste, as well as tests for checking the quality of the final product was performed. These control parameters involved total solids in suspension, dissolved salts, chlorides, sulphates, COD, metals content. In the product, parameters like moisture, density and strength were controlled. The results showed that it is possible to replace the virgin long fibers pulp by primary sludge without impacts in final product characteristics and on the environment. This work ensures the elimination of significant waste amounts, which are nowadays sent to landfill, as well as reduces costs associated with the standard raw materials use in the fiber-cement industrial sector.

  1. Summary of Tests to Determine Effectiveness of Gelatin Strike on SS{ampersand}C Dissolver Solutions

    SciTech Connect (OSTI)

    Murray, A.M. [Westinghouse Savannah River Company, AIKEN, SC (United States); Karraker, D.G.

    1998-05-01T23:59:59.000Z

    The solutions from the dissolution of sand, slag, and crucible (SS&C) material are sufficiently different from previous solutions processed via the F-Canyon Purex process that the effectiveness of individual process steps needed to be ascertained. In this study, the effectiveness of gelatin strike was tested under a variety of conditions. Specifically, several concentrations of silica, fluoride, nitric acid (HNO{sub 3}), boric acid (H{sub 3}BO{sub 3}), and aluminium nitrate nonahydrate (ANN) were studied. The disengagement times of surrogate and plant SS&C dissolver solutions from plant solvent also were measured. The results of the tests indicate that gelatin strike does not coagulate the silica at the low concentration of silica ({tilde 30} ppm) expected in the SS&C dissolver solutions because the silicon is complexed with fluoride ions (e.g., SiF{sub 6}{sup -2}). The silicon fluoride complex is expected to remain with the aqueous phase during solvent extraction. The disengagement times of the dissolver solutions from the plant solvent were not affected by the presence of low concentrations of silica and no third phase formation was observed in the disengagement phase with the low silica concentrations. Tests of surrogate SS&C dissolver solutions with higher concentration of silica (less than 150 ppm) did show that gelatin strike followed by centrifugation resulted in good phase disengagement of the surrogate SS{ampersand}C dissolver solution from the plant dissolver solution. At the higher silica concentrations, there is not sufficient fluoride to complex with the silica, and the silica must be entrained by the gelatin and removed from the dissolver solution prior to solvent extraction.

  2. Special Nuclear Material Portal Monitoring at the Nevada Test Site

    SciTech Connect (OSTI)

    DeAnn Long; Michael Murphy

    2008-07-01T23:59:59.000Z

    Prior to April 2007, acceptance and performance testing of the various Special Nuclear Material (SNM) monitoring devices at the Nevada Test Site (NTS) was performed by the Radiological Health Instrumentation department. Calibration and performance testing on the PM-700 personnel portal monitor was performed, but there was no test program for the VM-250 vehicle portal monitor. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no performance test program. In April of 2007, the Material Control and Accountability Manager volunteered to take over performance testing of all SNM portal monitors at NTS in order to strengthen the program and meet U.S. Department of Energy Order requirements. This paper will discuss the following activities associated with developing a performance testing program: changing the culture, learning the systems, developing and implementing procedures, troubleshooting and repair, validating the process, physical control of equipment, acquisition of new systems, and implementing the performance test program.

  3. Resilient modulus and permanent deformation testing of unbound granular materials

    E-Print Network [OSTI]

    Kancherla, Anuroopa

    2005-11-01T23:59:59.000Z

    Numerous research efforts have been devoted to characterizing the behavior of granular materials, which is one of the main concerns of pavement engineers. For better understanding of this behavior, laboratory tests where in-situ stress conditions...

  4. JOINING ADVANCED MATERIALS BY PLASTIC FLOW PROVIDES SOLUTION FOR OXYGEN SENSOR APPLICATIONS

    E-Print Network [OSTI]

    Kemner, Ken

    JOINING ADVANCED MATERIALS BY PLASTIC FLOW PROVIDES SOLUTION FOR OXYGEN SENSOR APPLICATIONS's unique plastic deformation process. · Abilitytodeploymultipleoxygen sensors (due to their lower cost

  5. Methods of pretreating comminuted cellulosic material with carbonate-containing solutions

    DOE Patents [OSTI]

    Francis, Raymond

    2012-11-06T23:59:59.000Z

    Methods of pretreating comminuted cellulosic material with an acidic solution and then a carbonate-containing solution to produce a pretreated cellulosic material are provided. The pretreated material may then be further treated in a pulping process, for example, a soda-anthraquinone pulping process, to produce a cellulose pulp. The pretreatment solutions may be extracted from the pretreated cellulose material and selectively re-used, for example, with acid or alkali addition, for the pretreatment solutions. The resulting cellulose pulp is characterized by having reduced lignin content and increased yield compared to prior art treatment processes.

  6. Hydrogen-Assisted Fracture: Materials Testing and Variables Governing Fracture

    E-Print Network [OSTI]

    Hydrogen-Assisted Fracture: Materials Testing and Variables Governing Fracture Brian Somerday for producing both strength of materials and fracture mechanics data H H HH H H d/dt > 0 strength of materials: UTS, YS, f, RA H2 H2H2 H2 H2 H2 H2 H2 HH H H H H H H H H d/dt 0 fracture mechanics: KIH, KTH

  7. Solution Phase Routes to Functional Nanostructured Materials for Energy Applications

    E-Print Network [OSTI]

    Rauda, Iris Ester

    2012-01-01T23:59:59.000Z

    bridge between the structural complexity of templated porous materials, and the electronic and optical complexity of semiconductor

  8. Solution Phase Routes to Functional Nanostructured Materials for Energy Applications

    E-Print Network [OSTI]

    Rauda, Iris Ester

    2012-01-01T23:59:59.000Z

    based materials are used as EDLC electrodes due to theiror “mirror” behavior. In an EDLC, the adsorption of ions on

  9. Accelerated Wear Tests on Common Floor-covering Materials.

    E-Print Network [OSTI]

    Stewart, B. R.; Kunze, O. R.; Hobgood, Price.

    1958-01-01T23:59:59.000Z

    *'r** qd** ""~c- web*- !,* . flccelerated Wear Tests e" f loor-couering materials AGRICULTURAL EXPERIMENT STATION R. D. LEWIS, DIRECTOR, COLLEGE STATION. TEXAS SUMMARY I .. - " : 5: Accelerated wear tests made on six common floor covering... coverings make up a large portion of this interior finish. The costs of maintenance and replacement of floor coverings contribute heavily 1 to the cost of home maintenance. Accelerated wear tests on floor covering ma- als were conducted...

  10. Electron beams in material testing for fusion reactors

    SciTech Connect (OSTI)

    Ganley, J.T.; McDonald, J.M.; Youchison, D.L. [Sandia National Laboratories, Albuquerque, NM (United States)

    1995-12-31T23:59:59.000Z

    The Plasma Material Test Facility at Sandia National Laboratory is currently involved in a multi-year program of thermally testing materials and high heat flux components for eventual use in fusion reactors. The major test system in the facility is the EB-1200 System, which uses two EH600S Von Ardenne electron guns to provide up to 1.2 MW of heating for large material samples and components. In this paper, the advantages of using electron guns for this type of testing will be discussed. Gun performance characteristics will be presented, as well as electronic techniques used to provide the rapidly varying power levels and complex scan patterns required for complicated targets. Diagnostic capabilities of importance to the experimental program will also be discussed.

  11. Environmental wear testing of nonmetallic materials for compressor applications

    SciTech Connect (OSTI)

    Parrington, R.J.; Hinchliff, E.M.

    1999-07-01T23:59:59.000Z

    A full-size prototypical test facility was designed and built to test nonmetallic materials in support of reciprocating compressor applications. Conventional test rigs utilize a pin- or ring-on-disk configuration to produce wear data in rotary motion under relatively low applied loads. In contrast, the subject test facility is constructed around a 9-inch (23-cm) stroke compressor frame. The test specimen and counterface configurations are similar to compressor packing rings and piston rods, respectively, and specimens are spring-loaded to variable levels encompassing actual compressor conditions. Testing to date has been performed at 500 rpm, 200 F (93 C), and three different load levels [65, 130 and 195 psi (450, 900 and 1,350 kPa)]. Material wear rate in air versus specimen pressure reveals a linear relationship with a slope of approximately 0.12 mils/day/psi (0.44 {micro}m/day/kPa). The wear performance of six different materials has been ranked in air. Future testing will focus on creating a database for material wear rates in air and nitrogen.

  12. DOE/MSU composite material fatigue database: Test methods, materials, and analysis

    SciTech Connect (OSTI)

    Mandell, J.F.; Samborsky, D.D. [Montana State Univ., Bozeman, MT (United States). Dept. of Chemical Engineering

    1997-12-01T23:59:59.000Z

    This report presents a detailed analysis of the results from fatigue studies of wind turbine blade composite materials carried out at Montana State University (MSU) over the last seven years. It is intended to be used in conjunction with the DOE/MSU composite Materials Fatigue Database. The fatigue testing of composite materials requires the adaptation of standard test methods to the particular composite structure of concern. The stranded fabric E-glass reinforcement used by many blade manufacturers has required the development of several test modifications to obtain valid test data for materials with particular reinforcement details, over the required range of tensile and compressive loadings. Additionally, a novel testing approach to high frequency (100 Hz) testing for high cycle fatigue using minicoupons has been developed and validated. The database for standard coupon tests now includes over 4,100 data points for over 110 materials systems. The report analyzes the database for trends and transitions in static and fatigue behavior with various materials parameters. Parameters explored are reinforcement fabric architecture, fiber content, content of fibers oriented in the load direction, matrix material, and loading parameters (tension, compression, and reversed loading). Significant transitions from good fatigue resistance to poor fatigue resistance are evident in the range of materials currently used in many blades. A preliminary evaluation of knockdowns for selected structural details is also presented. The high frequency database provides a significant set of data for various loading conditions in the longitudinal and transverse directions of unidirectional composites out to 10{sup 8} cycles. The results are expressed in stress and strain based Goodman Diagrams suitable for design. A discussion is provided to guide the user of the database in its application to blade design.

  13. Use of laser extensometer for mechanical test on irradiated materials

    SciTech Connect (OSTI)

    Brillaud, C.; Meylogan, T.; Salathe, P. [Electricite de France, Avoine (France)

    1996-12-31T23:59:59.000Z

    Techniques have been developed by EDF`s hot laboratory in Chinon for performing mechanical tests on irradiated materials. Some of these techniques aim to facilitate strain measurements, which are particularly difficult to perform on irradiated specimens at high temperatures or on subsize specimens. Recent progress has been driven by laser technology combined with software development. The use of this technique, which allows strain measurements without contact on the specimen, is described for tensile (especially on subsize specimens), fatigue and creep tests.

  14. Supplementary material Boundary conditions and numerical solution of Equation 4

    E-Print Network [OSTI]

    Neufeld, Jerome A.

    Supplementary Material for Particle Mass Yield from -Caryophyllene Ozonolysis Qi Chen1 , Yongjie Li in a continuously mixed flow reactor (CMFR) The mass balance of organic aerosol in a CMFR is described by the following equation: org, CMFR org, inflow org, CMFR org org, CMFR CMFR CMFR dM M M F M dt = - + - (A1

  15. Advanced Hot Section Materials and Coatings Test Rig

    SciTech Connect (OSTI)

    Dan Davis

    2006-09-30T23:59:59.000Z

    Phase I of the Hyperbaric Advanced Hot Section Materials & Coating Test Rig Program has been successfully completed. Florida Turbine Technologies has designed and planned the implementation of a laboratory rig capable of simulating the hot gas path conditions of coal gas fired industrial gas turbine engines. Potential uses of this rig include investigations into environmental attack of turbine materials and coatings exposed to syngas, erosion, and thermal-mechanical fatigue. The principle activities during Phase 1 of this project included providing several conceptual designs for the test section, evaluating various syngas-fueled rig combustor concepts, comparing the various test section concepts and then selecting a configuration for detail design. Conceptual definition and requirements of auxiliary systems and facilities were also prepared. Implementation planning also progressed, with schedules prepared and future project milestones defined. The results of these tasks continue to show rig feasibility, both technically and economically.

  16. Materials Solutions for Hydrogen Delivery in Pipelines | 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 RankCombustion | Department of EnergyDevelopment AccidentEnergy Objective: Develop materials

  17. Materials System Inventory Management Practices at Washington River Protection Solutions

    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 RankCombustion | Department of EnergyDevelopment AccidentEnergy Objective: DevelopMaterials System

  18. 3500-hour durability testing of commercial ceramic materials. Interim report

    SciTech Connect (OSTI)

    Carruthers, W.D.; Richerson, D.W.; Benn, K.W.

    1980-07-01T23:59:59.000Z

    A two-year durability testing program was performed by AiResearch Phoenix to evaluate four commercially available ceramic materials under simulated automotive gas turbine combustor discharge conditions. These conditions included extended cyclic thermal exposures up to 2500/sup 0/F and 3500 h. The four materials selected for evaluation were Norton NCX-34 hot pressed silicon nitride, AiResearch RBN 101 reaction bonded silicon nitride, Carborundum pressureless sintered ..cap alpha..-SiC and British Nuclear Fuels, Ltd. Refel reaction sintered silicon carbide marketed by Pure Carbon Co. These materials initially were exposed to 350 h/1750 cycles at 1200 and 1370/sup 0/C (2200 and 2500/sup 0/F). Subsequent exposures to 1050, 2100, and 3500 h were performed on the materials maintaining 50% of baseline strength after the initial exposure. Additional evaluations of exposed bars included dimension changes, weight changes, dye penetrant, specific damping capacity changes, Scanning Electron Microscope (SEM) fractography and x-ray diffraction.

  19. Testing of Gas Reactor Materials and Fuel in the Advanced Test Reactor

    SciTech Connect (OSTI)

    S. Blaine Grover

    2004-10-01T23:59:59.000Z

    The Advanced Test Reactor (ATR) has long been involved in testing gas reactor materials, and has developed facilities well suited for providing the right conditions and environment for gas reactor tests. This paper discusses the different types of irradiation hardware that have been utilized in past ATR irradiation tests of gas reactor materials. The new Gas Test Loop facility currently being developed for the ATR is discussed and the different approaches being considered in the design of the facility. The different options for an irradiation experiment such as active versus passive temperature control, neutron spectrum tailoring, and different types of lead experiment sweep gas monitors are also discussed. The paper is then concluded with examples of different past and present gas reactor material and fuel irradiations.

  20. TESTING OF GAS REACTOR MATERIALS AND FUEL IN THE ADVANCED TEST REACTOR

    SciTech Connect (OSTI)

    Grover, S.B.

    2004-10-06T23:59:59.000Z

    The Advanced Test Reactor (ATR) has long been involved in testing gas reactor materials, and has developed facilities well suited for providing the right conditions and environment for gas reactor tests. This paper discusses the different types of irradiation hardware that have been utilized in past ATR irradiation tests of gas reactor materials. The new Gas Test Loop facility currently being developed for the ATR is discussed and the different approaches being considered in the design of the facility. The different options for an irradiation experiment such as active versus passive temperature control, neutron spectrum tailoring, and different types of lead experiment sweep gas monitors are also discussed. The paper is then concluded with examples of different past and present gas reactor material and fuel irradiations.

  1. Physical test report for drop test of a 9974 radioactive material shipping packaging

    SciTech Connect (OSTI)

    Blanton, P.S. [Westinghouse Savannah River Company, AIKEN, SC (United States)

    1997-10-01T23:59:59.000Z

    This report presents the drop test results for the 9974 radioactive material shipping package being dropped onto 6-inch diameter, 40-inch long puncture pin. Also reported are the drop test resuls for a 30-foot impact that failed the drum confinement boundary. The purpose of these drops was to show that the package lid would remain attached to the drum.

  2. Standard Test Method for Stress-Corrosion of Titanium Alloys by Aircraft Engine Cleaning Materials

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2006-01-01T23:59:59.000Z

    1.1 This test method establishes a test procedure for determining the propensity of aircraft turbine engine cleaning and maintenance materials for causing stress corrosion cracking of titanium alloy parts. 1.2 The evaluation is conducted on representative titanium alloys by determining the effect of contact with cleaning and maintenance materials on tendency of prestressed titanium alloys to crack when subsequently heated to elevated temperatures. 1.3 Test conditions are based upon manufacturer's maximum recommended operating solution concentration. This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. For specific precautionary statements, see and .

  3. Develop the Basis for Plasma Material Interface (PMI) Solutions for FNSF

    E-Print Network [OSTI]

    Develop the Basis for Plasma Material Interface (PMI) Solutions for FNSF FESAC Strategic Planning to resolve the PMI challenge 2014 2025 2050 Predictable boundary plasma control to bridge the transition-plasma solutions to mitigate PMI challenges a. Comprehensive measurements and coordinated multi-machine experiments

  4. DIGITAL RADIOGRAPHY OF SPECIAL NUCLEAR MATERIAL TEST PACKAGES

    SciTech Connect (OSTI)

    HOWARD, BOYD

    2006-02-02T23:59:59.000Z

    The purpose of this document is to provide a brief introduction to digital radiography (DR), and a description of the DR configuration that was used to radiographically image the Special Nuclear Material (SNM) Test Packages before and after function tests that have been conducted. Also included are (1) Attachment 1, a comprehensive index that describes at which phase of the certification process that digital radiographic images were acquired, (2) digital radiographic images of each of the six packages at various stages of the certification process, and (3) Attachment 2, imaging instructions, that specify the setup procedures and detailed parameters of the DR imaging methodology that were used.

  5. Materials Corrosion and Mitigation Strategies for APT: Using Solution Resistivity as an Estimate of Tungsten Corrosion

    E-Print Network [OSTI]

    Materials Corrosion and Mitigation Strategies for APT: Using Solution Resistivity as an Estimate of Tungsten Corrosion in Spallation Neutron Target Cooling Loops R. Scott Lillard, Darryl P. Butt Materials Corrosion and Environmental Effects Laboratory MST-6, Metallurgy Los Alamos National Laboratory Los Alamos

  6. Evaluation of selected glove materials for worker hand protection against exposure to an aqueous aniline solution

    E-Print Network [OSTI]

    Powell, Marc Kendall

    1977-01-01T23:59:59.000Z

    of the requirements for the degree of MASTER OF SCIENCE Nay 1977 Major Subject: Industrial Hygiene EVALUATION OF SELECTED GLOVE MATERIALS FOR WORKER HAND PROTECTION AGAINST EXPOSURE TO AN AQUEOUS ANILINE SOLUTION A Thesis by NARC KENDALL POWELL Approved... glove materials to enable a health or safety professional to justify his selection of protective gloves for aniline workers. The results of this research indicate that any of the four glove materials evaluated would be acceptable to use for hand...

  7. Experience in testing of a solution mined storage cavern

    SciTech Connect (OSTI)

    Goin, K.L.

    1982-01-01T23:59:59.000Z

    Recertification tests were made of the U.S. Department of Energy/Strategic Petroleum Reserve oil storage cavern No. 6 in the West Hackberry, LA, salt dome. The cavern has a volume of 8,600,000 bbl. Tests included hydrostatic tests of the brine filled cavern and nitrogen leak tests of the 3 wells entering the cavern. Test procedures are described and test results are discussed.

  8. Hollow cylinder dynamic pressurization and radial flow through permeability tests for cementitous materials

    E-Print Network [OSTI]

    Jones, Christopher Andrew

    2009-05-15T23:59:59.000Z

    pressurization test is a potential solution for measuring concrete permeability. The hollow cylinder dynamic pressurization (HDP) test is compared with the radial flow through (RFT) test and the solid cylinder dynamic pressurization (SDP) test to assess...

  9. THERMAL PREDICTIONS OF NEW COMPOSITE MATERIAL DURING INPILE TESTING

    SciTech Connect (OSTI)

    Donna Post Guillen; W. David Swank; Heng Ban; Kurt Harris; Adam Zabriskie

    2011-09-01T23:59:59.000Z

    An inpile experiment is currently underway wherein specimens comprised of a newly developed material are being irradiated at Idaho National Laboratory's Advanced Test Reactor (ATR) in conjunction with Utah State University under the auspices of the ATR National Scientific User Facility. This paper provides the thermophysical properties of this new material measured prior to irradiation. After the irradiation campaign is complete, the thermophysical properties of the specimens will be measured and compared to the preirradiation values. A finite-element model was constructed to predict bounding specimen temperatures during irradiation. Results from the thermal hydraulic modeling, including the steady-state temperatures of the specimens within sealed capsules, are presented. After the irradiation campaign is completed, best-estimate thermal predictions will be performed for the individual specimens using the actual as-run irradiation power levels.

  10. 1000–ton testing machine for cyclic fatigue tests of materials at liquid nitrogen temperatures

    SciTech Connect (OSTI)

    Khitruk, A. A.; Klimchenko, Yu. A.; Kovalchuk, O. A.; Marushin, E. L.; Mednikov, A. A.; Nasluzov, S. N.; Privalova, E. K.; Rodin, I. Yu.; Stepanov, D. B.; Sukhanova, M. V. [The D.V. Efremov Scientific Research Institute of Electrophysical Apparatus (NIIEFA), 3 Doroga na Metallostroy, Metallostroy, Saint Petersburg 196641 (Russian Federation)

    2014-01-29T23:59:59.000Z

    One of the main tasks of superconductive magnets R and D is to determine the mechanical and fatigue properties of structural materials and the critical design elements in the cryogenic temperature range. This paper describes a new facility built based on the industrial 1000-ton (10 MN) testing machine Schenk PC10.0S. Special equipment was developed to provide the mechanical and cyclic tensile fatigue tests of large-scale samples at the liquid nitrogen temperature and in a given load range. The main feature of the developed testing machine is the cryostat, in which the device converting a standard compression force of the testing machine to the tensile force affected at the test object is placed. The control system provides the remote control of the test and obtaining, processing and presentation of test data. As an example of the testing machine operation the test program and test results of the cyclic tensile fatigue tests of fullscale helium inlet sample of the PF1 coil ITER are presented.

  11. Utility of transient testing to characterize thermal interface materials

    E-Print Network [OSTI]

    B. Smith; T. Brunschwiler; B. Michel

    2008-01-07T23:59:59.000Z

    This paper analyzes a transient method for the characterization of low-resistance thermal interfaces of microelectronic packages. The transient method can yield additional information about the package not available with traditional static methods at the cost of greater numerical complexity, hardware requirements, and sensitivity to noise. While the method is established for package-level thermal analysis of mounted and assembled parts, its ability to measure the relatively minor thermal impedance of thin thermal interface material (TIM) layers has not yet been fully studied. We combine the transient thermal test with displacement measurements of the bond line thickness to fully characterize the interface.

  12. Testing of Packaging Materials for Improved PV Module Reliability

    SciTech Connect (OSTI)

    Jorgensen, G. J.; Terwilliger, K. M.; Kempe, M. D.; McMahon, T. J.

    2005-02-01T23:59:59.000Z

    A number of candidate alternative encapsulant and soft backsheet materials have been evaluated in terms of their suitability for photovoltaic (PV) module packaging applications. Relevant properties, including interfacial adhesion and moisture transport, have been measured as a function of damp-heat (85 C/85% relative humidity) exposure. Based on these tests, promising new encapsulants with improved properties have been identified. Backsheets prepared by industry and at NREL have been found to provide varying levels of moisture ingress protection. To achieve significantly improved products, further development of these candidates is ongoing. The relative effectiveness of various packaging strategies to protect PV devices has also been investigated.

  13. Utility of transient testing to characterize thermal interface materials

    E-Print Network [OSTI]

    Smith, B; Michel, B

    2008-01-01T23:59:59.000Z

    This paper analyzes a transient method for the characterization of low-resistance thermal interfaces of microelectronic packages. The transient method can yield additional information about the package not available with traditional static methods at the cost of greater numerical complexity, hardware requirements, and sensitivity to noise. While the method is established for package-level thermal analysis of mounted and assembled parts, its ability to measure the relatively minor thermal impedance of thin thermal interface material (TIM) layers has not yet been fully studied. We combine the transient thermal test with displacement measurements of the bond line thickness to fully characterize the interface.

  14. Chalcogenide Glass Radiation Sensor; Materials Development, Design and Device Testing

    SciTech Connect (OSTI)

    Mitkova, Maria; Butt, Darryl; Kozicki, Michael; Barnaby, Hugo

    2013-04-30T23:59:59.000Z

    For many decades, various radiation detecting material have been extensively researched, to find a better material or mechanism for radiation sensing. Recently, there is a growing need for a smaller and effective material or device that can perform similar functions of bulkier Geiger counters and other measurement options, which fail the requirement for easy, cheap and accurate radiation dose measurement. Here arises the use of thin film chalcogenide glass, which has unique properties of high thermal stability along with high sensitivity towards short wavelength radiation. The unique properties of chalcogenide glasses are attributed to the lone pair p-shell electrons, which provide some distinctive optical properties when compared to crystalline material. These qualities are derived from the energy band diagram and the presence of localized states in the band gap. Chalcogenide glasses have band tail states and localized states, along with the two band states. These extra states are primarily due to the lone pair electrons as well as the amorphous structure of the glasses. The localized states between the conductance band (CB) and valence band (VB) are primarily due to the presence of the lone pair electrons, while the band tail states are attributed to the Van der Waalâ??s forces between layers of atoms [1]. Localized states are trap locations within the band gap where electrons from the valence band can hop into, in their path towards the conduction band. Tail states on the other hand are locations near the band gap edges and are known as Urbach tail states (Eu). These states are occupied with many electrons that can participate in the various transformations due to interaction with photons. According to Y. Utsugi et. al.[2], the electron-phonon interactions are responsible for the generation of the Urbach tails. These states are responsible for setting the absorption edge for these glasses and photons with energy near the band gap affect these states. We have studied the effect of x-rays and Îł-rays, on thin film chalcogenide glasses and applied them in conjunction with film incorporating a silver source in a new type of radiation sensor for which we have an US patent application [3]. In this report, we give data about our studies regarding our designed radiation sensor along with the testing and performance at various radiation doses. These studies have been preceded by materials characterization research related to the compositional and structural characteristics of the active materials used in the radiation sensor design. During the work on the project, we collected a large volume of material since every experiment was repeated many times to verify the results. We conducted a comprehensive material research, analysis and discussion with the aim to understand the nature of the occurring effects, design different structures to harness these effects, generated models to aid in the understanding the effects, built different device structures and collected data to quantify device performance. These various aspects of our investigation have been detailed in previous quarterly reports. In this report, we present our main results and emphasize on the results pertaining to the core project goals â?? materials development, sensor design and testing and with an emphasis on classifying the appropriate material and design for the optimal application. The report has three main parts: (i) Presentation of the main data; (ii) Bulleted summary of the most important results; (iii) List of the patent, journal publications, conference proceedings and conferences participation, occurring as a result of working on the project.

  15. Characterization of spent fuel approved testing material: ATM-103

    SciTech Connect (OSTI)

    Guenther, R.J.; Blahnik, D.E.; Campbell, T.K.; Jenquin, U.P.; Mendel, J.E.; Thomas, L.E.; Thornhill, C.K.

    1988-04-01T23:59:59.000Z

    The characterization data obtained to date are described for Approved Testing Material (ATM)-103, which is spent fuel from Assembly D101 of pressurized-water reactor Calvert Cliffs, No. 1. This report is one in a series being written by the Materials Characterization Center (MCC) at Pacific Northwest Laboratory (PNL) on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well-characterized spent fuel for testing in the US nuclear waste repository program. ATM-103 consists of 176 full-length irradiated fuel rods with rod-average burnups of about 2600 GJ/kgM (30 MWd/kgM) and less than 1% fission gas release. Characterization data include 1) as-fabricated fuel design, irradiation history, and subsequent storage and handling; 2) isotopic gamma scans; 3) fission gas analyses; 4) ceramography of the fuel and metallography of the cladding; 5) special fuels studies involving analytical transmission electron microscopy (AEM); 6) calculated nuclide inventories and radioactivities in the fuel and cladding; and 7) radiochemical analyses of the fuel and cladding. Additional analyses of the fuel are being conducted and will be included in planned revisions of this report. 10 refs., 103 figs., 63 tabs.

  16. Characterization of spent fuel approved testing material: ATM-106

    SciTech Connect (OSTI)

    Guenther, R.J.; Blahnik, D.E.; Campbell, T.K.; Jenquin, U.P.; Mendel, J.E.; Thornhill, C.K.

    1988-10-01T23:59:59.000Z

    The characterization data obtained to date are described for Approved Testing Material (ATM)-106 spent fuel from Assembly BT03 of pressurized-water reactor Calvert Cliffs No. 1. This report is one in a series being prepared by the Materials Characterization Center at Pacific Northwest Laboratory on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well- characterized spent fuel for testing in the US Department of Energy Office of Civilian Radioactive Waste Management (OCWRM) program. ATM-106 consists of 20 full-length irradiated fuel rods with rod-average burnups of about 3700 GJ/kgM (43 MWd/kgM) and expected fission gas release of /approximately/10%. Characterization data include (1) as-fabricated fuel design, irradiation history, and subsequent storage and handling; (2) isotopic gamma scans; (3) fission gas analyses; (4) ceramography of the fuel and metallography of the cladding; (5) calculated nuclide inventories and radioactivities in the fuel and cladding; and (6) radiochemical analyses of the fuel and cladding. Additional analyses of the fuel rod are being conducted and will be included in planned revisions of this report. 12 refs., 110 figs., 81 tabs.

  17. Characterization of spent fuel approved testing material---ATM-105

    SciTech Connect (OSTI)

    Guenther, R.J.; Blahnik, D.E.; Campbell, T.K.; Jenquin, U.P.; Mendel, J.E.; Thomas, L.E.; Thornhill, C.K.

    1991-12-01T23:59:59.000Z

    The characterization data obtained to data are described for Approved Testing Material 105 (ATM-105), which is spent fuel from Bundles CZ346 and CZ348 of the Cooper Nuclear Power Plant, a boiling-water reactor. This report is one in a series being prepared by the Materials Characterization Center at Pacific Northwest Laboratory (PNL) on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well-characterized spent fuel for testing in the US Department of Energy Office of Civilian Radioactive Waste Management (OCRWM) Program. ATM-105 consists of 88 full-length irradiated fuel rods with rod-average burnups of about 2400 GJ/kgM (28 MWd/kgM) and expected fission gas release of about 1%. Characterization data include (1) descriptions of as-fabricated fuel design, irradiation history, and subsequent storage and handling; (2) isotopic gamma scans; (3) fission gas analyses; (4) ceramography of the fuel and metallography of the cladding; (5) special fuel studies involving analytical transmission electron microscopy (AEM); (6) calculated nuclide inventories and radioactivities in the fuel and cladding; and (7) radiochemical analyses of the fuel and cladding. Additional analyses of the fuel are being conducted and will be included in planned revisions of this report.

  18. Characterization of spent fuel approved testing material--ATM-104

    SciTech Connect (OSTI)

    Guenther, R.J.; Blahnik, D.E.; Jenquin, U.P.; Mendel, J.E.; Thomas, L.E.; Thornhill, C.K.

    1991-12-01T23:59:59.000Z

    The characterization data obtained to date are described for Approved Testing Material 104 (ATM-104), which is spent fuel from Assembly DO47 of the Calvert Cliffs Nuclear Power Plant (Unit 1), a pressurized-water reactor. This report is one in a series being prepared by the Materials Characterization Center at Pacific Northwest Laboratory (PNL) on spent fuel ATMs. The ATMs are receiving extensive examinations to provide a source of well-characterized spent fuel for testing in the US Department of Energy Office of Civilian Radioactive Waste Management (OCRWM) Program. ATM-104 consists of 128 full-length irradiated fuel rods with rod-average burnups of about 42 MWd/kgM and expected fission gas release of about 1%. A variety of analyses were performed to investigate cladding characteristics, radionuclide inventory, and redistribution of fission products. Characterization data include (1) fabricated fuel design, irradiation history, and subsequent storage and handling history; (2) isotopic gamma scans; (3) fission gas analyses; (4) ceramography of the fuel and metallography of the cladding; (5) special fuel studies involving analytical transmission electron microscopy (AEM) and electron probe microanalyses (EPMA); (6) calculated nuclide inventories and radioactivities in the fuel and cladding; and (7) radiochemical analyses of the fuel and cladding.

  19. Radiochemical analyses of several spent fuel Approved Testing Materials

    SciTech Connect (OSTI)

    Guenther, R.J.; Blahnik, D.E.; Wildung, N.J.

    1994-09-01T23:59:59.000Z

    Radiochemical characterization data are described for UO{sub 2} and UO{sub 2} plus 3 wt% Gd{sub 2}O{sub 3} commercial spent nuclear fuel taken from a series of Approved Testing Materials (ATMs). These full-length nuclear fuel rods include MLA091 of ATM-103, MKP070 of ATM-104, NBD095 and NBD131 of ATM-106, and ADN0206 of ATM-108. ATMs 103, 104, and 106 were all irradiated in the Calvert Cliffs Nuclear Power Plant (Reactor No.1), a pressurized-water reactor that used fuel fabricated by Combustion Engineering. ATM-108 was part of the same fuel bundle designed as ATM-105 and came from boiling-water reactor fuel fabricated by General Electric and irradiated in the Cooper Nuclear Power Plant. Rod average burnups and expected fission gas releases ranged from 2,400 to 3,700 GJ/kgM. (25 to 40 Mwd/kgM) and from less than 1% to greater than 10%, respectively, depending on the specific ATM. The radiochemical analyses included uranium and plutonium isotopes in the fuel, selected fission products in the fuel, fuel burnup, cesium and iodine on the inner surfaces of the cladding, {sup 14}C in the fuel and cladding, and analyses of the gases released to the rod plenum. Supporting examinations such as fuel rod design and material descriptions, power histories, and gamma scans used for sectioning diagrams are also included. These ATMs were examined as part of the Materials Characterization Center Program conducted at Pacific Northwest Laboratory provide a source of well-characterized spent fuel for testing in support of the US Department of Energy Office of Civilian Radioactive Waste Management Program.

  20. Quality Assurance Protocol for AFCI Advanced Structural Materials Testing

    SciTech Connect (OSTI)

    Busby, Jeremy T [ORNL

    2009-05-01T23:59:59.000Z

    The objective of this letter is to inform you of recent progress on the development of advanced structural materials in support of advanced fast reactors and AFCI. As you know, the alloy development effort has been initiated in recent months with the procurement of adequate quantities of the NF616 and HT-UPS alloys. As the test alloys become available in the coming days, mechanical testing, evaluation of optimizing treatments, and screening of environmental effects will be possible at a larger scale. It is therefore important to establish proper quality assurance protocols for this testing effort in a timely manner to ensure high technical quality throughout testing. A properly implemented quality assurance effort will also enable preliminary data taken in this effort to be qualified as NQA-1 during any subsequent licensing discussions for an advanced design or actual prototype. The objective of this report is to describe the quality assurance protocols that will be used for this effort. An essential first step in evaluating quality protocols is assessing the end use of the data. Currently, the advanced structural materials effort is part of a long-range, basic research and development effort and not, as yet, involved in licensing discussions for a specific reactor design. After consultation with Mark Vance (an ORNL QA expert) and based on the recently-issued AFCI QA requirements, the application of NQA-1 quality requirements will follow the guidance provided in Part IV, Subpart 4.2 of the NQA-1 standard (Guidance on Graded Application of QA for Nuclear-Related Research and Development). This guidance mandates the application of sound scientific methodology and a robust peer review process in all phases, allowing for the data to be qualified for use even if the programmatic mission changes to include licensing discussions of a specific design or prototype. ORNL has previously implemented a QA program dedicated to GNEP activities and based on an appropriately graded application of NQA-1 requirements at the site. The current program is being revised to incorporate changes imposed through the recently revised AFCI Technical Integration Office QA requirements. Testing conducted under the AFCI QA program for the advanced structural materials effort shall incorporate the following quality assurance expectations: (1) personnel are adequately trained to perform assigned work; (2) activities are controlled to ensure consistency of results; (3) records necessary to substantiate how the work was performed are maintained (dedicated laboratory notebooks will be used); (4) the pedigree and traceability of the various tested materials are maintained throughout the described processes using consistent sample numbering and adequate record keeping; (5) equipment with the potential to affect the quality of the planned work is calibrated and maintained in accordance with applicable operating requirements. In addition, all reporting or related dissemination by ORNL personnel of the results of the work described in this subcontract shall be conducted in accordance with the requirements described or referenced in the ORNL Standards Based Management System subject area entitled Scientific and Technical Information. Reporting or publications at other institutions will be conducted in accordance with the requirements of that institution. Successful implementation of these protocols will provide a sound basis for future decisions and research. In addition, these steps will also help ensure that results can also be applied to licensing discussions at a future date.

  1. Cosmological solutions in bimetric gravity and their observational tests

    SciTech Connect (OSTI)

    Strauss, Mikael von; Schmidt-May, Angnis; Enander, Jonas; Mörtsell, Edvard; Hassan, S.F., E-mail: mvs@fysik.su.se, E-mail: angnis.schmidt-may@fysik.su.se, E-mail: enander@fysik.su.se, E-mail: edvard@fysik.su.se, E-mail: fawad@fysik.su.se [Department of Physics and The Oskar Klein Centre for Cosmoparticle Physics, Stockholm University, AlbaNova University Centre, SE-106 91 Stockholm (Sweden)

    2012-03-01T23:59:59.000Z

    We obtain the general cosmological evolution equations for a classically consistent theory of bimetric gravity. Their analytic solutions are demonstrated to generically allow for a cosmic evolution starting out from a matter dominated FLRW universe and relaxing towards a de Sitter (anti-de Sitter) phase at late cosmic time. In particular, we examine a subclass of models which contain solutions that are able to reproduce the expansion history of the cosmic concordance model inspite of the nonlinear couplings of the two metrics. This is demonstrated explicitly by fitting these models to observational data from Type Ia supernovae, Cosmic Microwave Background and Baryon Acoustic Oscillations. In the appendix we comment on the relation to massive gravity.

  2. INNOVATIVE DESIGN AND MATERIAL SOLUTIONS OF THERMAL CONTACT LAYERS FOR HIGH HEAT FLUX APPLICATIONS IN FUSION

    E-Print Network [OSTI]

    Tillack, Mark

    INNOVATIVE DESIGN AND MATERIAL SOLUTIONS OF THERMAL CONTACT LAYERS FOR HIGH HEAT FLUX APPLICATIONS of sacrificial plasma facing components that have to handle the high heat and particle fluxes in ITER armour thermal and electrical contact with the cooled sub-structure while promoting remote, in

  3. Post-Test Analysis of Lithium-Ion Battery Materials at Argonne...

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

    Test Analysis of Lithium-Ion Battery Materials at Argonne National Laboratory Post-Test Analysis of Lithium-Ion Battery Materials at Argonne National Laboratory 2013 DOE Hydrogen...

  4. Numerical solution of shock and ramp compression for general material properties

    SciTech Connect (OSTI)

    Swift, D C

    2009-01-28T23:59:59.000Z

    A general formulation was developed to represent material models for applications in dynamic loading. Numerical methods were devised to calculate response to shock and ramp compression, and ramp decompression, generalizing previous solutions for scalar equations of state. The numerical methods were found to be flexible and robust, and matched analytic results to a high accuracy. The basic ramp and shock solution methods were coupled to solve for composite deformation paths, such as shock-induced impacts, and shock interactions with a planar interface between different materials. These calculations capture much of the physics of typical material dynamics experiments, without requiring spatially-resolving simulations. Example calculations were made of loading histories in metals, illustrating the effects of plastic work on the temperatures induced in quasi-isentropic and shock-release experiments, and the effect of a phase transition.

  5. Improved flywheel materials : characterization of nanofiber modified flywheel test specimen.

    SciTech Connect (OSTI)

    Boyle, Timothy J.; Bell, Nelson Simmons; Ehlen, Mark Andrew; Anderson, Benjamin John; Miller, William Kenneth

    2013-09-01T23:59:59.000Z

    As alternative energy generating devices (i.e., solar, wind, etc) are added onto the electrical energy grid (AC grid), irregularities in the available electricity due to natural occurrences (i.e., clouds reducing solar input or wind burst increasing wind powered turbines) will be dramatically increased. Due to their almost instantaneous response, modern flywheel-based energy storage devices can act a mechanical mechanism to regulate the AC grid; however, improved spin speeds will be required to meet the necessary energy levels to balance thesegreen' energy variances. Focusing on composite flywheels, we have investigated methods for improving the spin speeds based on materials needs. The so-called composite flywheels are composed of carbon fiber (C-fiber), glass fiber, and aglue' (resin) to hold them together. For this effort, we have focused on the addition of fillers to the resin in order to improve its properties. Based on the high loads required for standard meso-sized fillers, this project investigated the utility of ceramic nanofillers since they can be added at very low load levels due to their high surface area. The impact that TiO2 nanowires had on the final strength of the flywheel material was determined by athree-point-bend' test. The results of the introduction of nanomaterials demonstrated an increase instrength' of the flywheel's C-fiber-resin moiety, with an upper limit of a 30% increase being reported. An analysis of the economic impact concerning the utilization of the nanowires was undertaken and after accounting for new-technology and additional production costs, return on improved-nanocomposite investment was approximated at 4-6% per year over the 20-year expected service life. Further, it was determined based on the 30% improvement in strength, this change may enable a 20-30% reduction in flywheel energy storage cost (%24/kW-h).

  6. ESP - Data From Restarted Life Tests of Various Silicone Materials - 2009

    SciTech Connect (OSTI)

    J. W. Schneider

    2010-02-24T23:59:59.000Z

    Enhanced Surveillance Project (ESP) funding has allowed the restart of testing of various silicone materials placed in Life Tests or Aging Studies from past efforts. Some of these materials have been in test since 1982, with no testing for approximately 10 years, until ESP funding allowed the restart in FY97. This report will provide data on materials used on various programs and on experimental materials not used in production. Charts for the various materials at different thickness, compression, and temperature combinations illustrate trends for the load-bearing properties of the materials.

  7. ESP – Data from Restarted Life Tests of Various Silicone Materials - 2011

    SciTech Connect (OSTI)

    Jim Schneider

    2011-12-31T23:59:59.000Z

    Current funding has allowed the restart of testing of various silicone materials placed in Life Tests or Aging Studies from past efforts. Some of these materials have been in test since 1982, with no testing for approximately 10 years, until funding allowed the restart in FY97. This report will provide data on materials used in production and on experimental materials not used in production. Charts for the various materials at different thickness, compression, and temperature combinations illustrate trends for the load-bearing properties of the materials.

  8. Nondestructive assay (NDA) of fissile material solutions in tanks at Rocky Flats Environmental Technology Site

    SciTech Connect (OSTI)

    Fleissner, J.G.; Lamb, F.W.; Maul, M.R.

    1995-07-01T23:59:59.000Z

    Nondestructive assay of holdup in solution tanks at Rocky Flats has been performed to address criticality safety concerns since 1974. Destructive analysis techniques were used for quantification of the fissile material content of the tanks. With termination of operations in 1989, including sparging and sampling of tanks, a need arose for nondestructive assay of solutions in tanks to confirm previous inventory values. Gamma ray measurement methodologies were investigated and several techniques, including Poor Man`s Densitometry were implemented. These techniques have been applied to several different types of tanks including: annular, raschig ring filled, and pencil tanks. For the annular tanks ``Poor Man`s Densitometry`` is used, with the densities of the measured solutions normalized to the value of one ``accepted`` concentration tank. Measurement uncertainties for this technique has been better than was anticipated. Measurements are also performed at several levels to attempt to detect variations in density. For the current tank draining program, solution in tanks is assayed by the NDA gamma-ray technique before draining. Measurement results were obtained for plutonium, uranium, and mixtures of U/Pu solutions for concentrations ranging from less than 0.5 g/l to 150 g/l. Tanks with expected concentrations were used to establish a relationship between concentration and count rate. ``Bootstrapping`` calibration techniques were used in some cases to obtain quantitative results.

  9. Analytic Solutions to 3-D Finite Deformation Problems Governed by St Venant-Kirchhoff Material

    E-Print Network [OSTI]

    David Yang Gao; Eldar Hajilarov

    2015-04-11T23:59:59.000Z

    This paper presents a detailed study on analytical solutions to a general nonlinear boundary-value problem in finite deformation theory. Based on canonical duality theory and the associated pure complementary energy principle in nonlinear elasticity proposed by Gao in 1999, we show that the general nonlinear partial differential equation for deformation is actually equivalent to an algebraic (tensor) equation in stress space. For St Venant-Kirchhoff materials, this coupled cubic algebraic equation can be solved principally to obtain all possible solutions. Our results show that for any given external source field such that the statically admissible first Piola-Kirchhoff stress field has no-zero eigenvalues, the problem has a unique global minimal solution, which is corresponding to a positive-definite second Piola-Kirchhoff stress S, and at most eight local solutions corresponding to negative-definite S. Additionally, the problem could have 15 unstable solutions corresponding to indefinite S. This paper demonstrates that the canonical duality theory and the pure complementary energy principle play fundamental roles in nonconvex analysis and finite deformation theory.

  10. Radioisotope Thermoelectric Generator Package O-Ring Seal Material Validation Testing

    SciTech Connect (OSTI)

    Adkins, H.E.; Ferrell, P.C.; Knight, R.C.

    1994-09-30T23:59:59.000Z

    The Radioisotope Thermoelectric Generator Package O-Ring Seal Material Validation Test was conducted to validate the use of the Butyl material as a primary seal throughout the required temperature range. Three tests were performed at (1) 233 K ({minus}40 {degrees}F), (2) a specified operating temperature, and (3) 244 K ({minus}20 {degrees}F) before returning to room temperature. Helium leak tests were performed at each test point to determine seal performance. The two major test objectives were to establish that butyl rubber material would maintain its integrity under various conditions and within specified parameters and to evaluate changes in material properties.

  11. Physical test report to drop test of a 9975 radioactive material shipping packaging

    SciTech Connect (OSTI)

    Blanton, P.S.

    1997-11-11T23:59:59.000Z

    This report presents the drop test results for the 9975 radioactive material shipping package being dropped 30 feet onto a unyielding surface followed by a 40-inch puncture pin drop. The purpose of these drops was to show that the package lid would remain attached to the drum. The 30-foot drop was designed to weaken the lid closure lug while still maintaining maximum extension of the lugs from the drum surface. This was accomplished by angling the drum approximately 30 degrees from horizontal in an inverted position. In this position, the drum was rotated slightly so as not to embed the closure lugs into the drum as a result of the 30-foot drop. It was determined that this orientation would maximize deformation to the closure ring around the closure lug while still maintaining the extension of the lugs from the package surface. The second drop was from 40 inches above a 40-inch tall 6-inch diameter puncture pin. The package was angled 10 degrees from vertical and aligned over the puncture pin to solidly hit the drum lug(s) in an attempt to disengage the lid when dropped.Tests were performed in response to DOE EM-76 review Q5 inquires that questioned the capability of the 9975 drum lid to remain in place under this test sequence. Two packages were dropped utilizing this sequence, a 9974 and 9975. Test results for the 9974 package are reported in WSRC-RP-97-00945. A series of 40-inch puncture pin tests were also performed on undamaged 9975 and 9974 packages.

  12. Scale-up and Testing of Advanced Materials from the BATT Program...

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

    Scale-up and Testing of Advanced Materials from the BATT Program Vince Battaglia LBNL May 09, 2011 This presentation does not contain any proprietary, confidential, or otherwise...

  13. Material test machine for tension-compression tests at high temperature

    DOE Patents [OSTI]

    Cioletti, Olisse C. (Pittsburgh, PA)

    1988-01-01T23:59:59.000Z

    Apparatus providing a device for testing the properties of material specimens at high temperatures and pressures in controlled water chemistries includes, inter alia, an autoclave housing the specimen which is being tested. The specimen is connected to a pull rod which couples out of the autoclave to an external assembly which includes one or more transducers, a force balance chamber and a piston type actuator. The pull rod feeds through the force balance chamber and is compensated thereby for the pressure conditions existing within the autoclave and tending to eject the pull rod therefrom. The upper end of the push rod is connected to the actuator through elements containing a transducer comprising a linear variable differential transformer (LVDT). The housing and coil assembly of the LVDT is coupled to a tube which runs through a central bore of the pull rod into the autoclave where it is connected to one side of the specimen. The movable core of the LVDT is coupled to a stem which runs through the tube where it is then connected to the other side of the specimen through a coupling member. A transducer in the form of a load cell including one or more strain gages is located on a necked-down portion of the upper part of the pull rod intermediate the LVDT and force balance chamber.

  14. Long-Term Materials-Test Program. Annual report and Qualification Test Plan, October 1979-September 1980

    SciTech Connect (OSTI)

    None

    1981-04-01T23:59:59.000Z

    Progress made on the Long Term Materials Test Program during its first year is summarized and the test planning required to perform the Qualification Test is documented. The objective of the Qualification Test is to check out the proper functioning of the Test Rig and to demonstrate its capability to produce a representative PFB off-gas environment for long term candidate-material testing. During the first year of the program, the project has progressed from the concept stage to the start of construction. Ninety-five percent of the equipment has been ordered and renovations to accommodate the test rig have been initiated at the Malta Site. The initial effort focused on the test rig configuration and selection of the candidate turbine materials. The preliminary design phase was officially culminated by the presentation and acceptance of the Preliminary Operations Plan to DOE during April 1980. By mid-June, 1981, the design of the major components was substantially complete allowing a detailed external design review to be performed. The design was accepted, and purchase orders for the major components were placed. In parallel with the design effort, two materials-screening tests have been initiated. One thousand hours of testing on the oil-fired small burner rig and the first 250-h segment on the erosion/corrosion simulator has been completed.

  15. A Materials Science Driven Pattern Generation Solution to Fracturing Computer Generated Glass for Films and Games

    E-Print Network [OSTI]

    Monroe, David Charles

    2014-08-11T23:59:59.000Z

    include some plastics like polymethylmethacrylate (PMMA), laminated, toughened glasses, safety glasses, other ceramics, most non-metals, and some metals when subjected to low temperatures. Brittleness, ductility, malleability, plasticity, stiffness...]. Their formula accurately models the brittle materials tested: flat PMMA and glass plates of various thickness. The continuous line in Figure 26 (B) is n=1.7(V^)1/2, where n is the number of radial cracks. 26 II.3. Visual Effects Approaches to Fracturing...

  16. Testing of novel desiccant materials and dehumidifier matrices for desiccant cooling applications

    SciTech Connect (OSTI)

    Pesaran, A.A.; Bingham, C.E.

    1989-03-01T23:59:59.000Z

    This paper presents the results of testing of desiccant materials and dehumidifier matrices for desiccant cooling and dehumidification applications. In testing desiccant materials, we used a gravimetric technique to measure the moisture capacity of four desiccant materials. These materials were microporous silica gel powder, macroporous silica gel powder, polystyrene sulfonic acid sodium salt, and a silica-gel/epoxy composite. The microporous silica gel powder had the most desirable moisture capacity properties of the four materials tested for desiccant cooling applications. The polystyrene sulfonic acid sodium salt showed some promise. Our testing of dehumidifier matrices included measuring the pressure drop and heat- and mass-transfer rate characteristics of a silica-gel/corrugated dehumidifier matrix under conditions typical of desiccant cooling systems. The matrix is a section of a commercial dehumidifier. The transient dehumidification capacity of the matrix was calculated from the tests and compared with previously tested matrices. 9 refs., 10 figs., 2 tabs.

  17. Test blanket modules in ITER: An overview on proposed designs and required DEMO-relevant materials

    E-Print Network [OSTI]

    Abdou, Mohamed

    Test blanket modules in ITER: An overview on proposed designs and required DEMO-relevant materials, Russian Federation Abstract Within the framework of the ITER Test Blanket Working Group, the ITER Parties have made several proposals for test blanket modules to be tested in ITER from the first day of H

  18. Qualification tests of materials for spallation neutron sources

    SciTech Connect (OSTI)

    Sommer, W.F.

    1996-12-31T23:59:59.000Z

    Several existing and planned facilities, worldwide, use protons at 650-2000 MeV to produce neutrons by spallation reactions. In the advanced spallation neutron sources, materials in the target and blanket structures will be exposed to high-energy proton fluences at 10{sup 25}-10{sup 26}/m{sup 2} per year. Information obtained in fusion reactor studies are being applied to the design of spallation neutron sources. The APT project is sponsoring a materials qualification program including irradiations in the proton beam and neutron field at the Los Alamos Spallation Radiation Damage Facility.

  19. Long Term Materials Test Program. Quarterly progress report, January-March 1980

    SciTech Connect (OSTI)

    None

    1980-04-01T23:59:59.000Z

    Objective of the program is to identify corrosion-resistant materials for potential use in a gas turbine. A test rig has been devised for determining the long-term effects of coal-fueled pressurized fluidized-bed combustor exhaust gas on such materials. The test is described. (DLC)

  20. Similarity solutions and applications to turbulent upward flame spread on noncharring materials

    SciTech Connect (OSTI)

    Delichatsios, M.A.; Delichatsios, M.; Chen, Y. [Factory Mutual Research Corporation, Norwood, MA (United States)] [Factory Mutual Research Corporation, Norwood, MA (United States); Hasemi, Y. [Ministry of Construction, Tsukuba (Japan). Building Research Inst.] [Ministry of Construction, Tsukuba (Japan). Building Research Inst.

    1995-08-01T23:59:59.000Z

    The primary achievement in this work has been the discovery that turbulent upward flame spread on noncharring materials (for pyrolysis lengths less than 1.8m) can be directly predicted by using measurable flammability parameters. These parameters are: a characteristic length scale which is proportional to a turbulent combustion and mixing related length scale parameter ({dot q}{double_prime}{sub net}({Delta}H{sub c}/{Delta}H{sub v})){sup 2}, a pyrolysis or ignition time {tau}{sub p}, and a parameter which determines the transient pyrolysis history of a non-charring material: {lambda} = L/c{Delta}T{sub p} = ratio of the latent heat to the sensible heat of the pyrolysis temperature of the material. In the length scale parameter, {dot q}{double_prime}{sub net} is the total net heat flux from the flames to the wall (i.e., total heat flux minus reradiation losses), {Delta}H{sub c} is the heat of combustion and {Delta}H{sub v} is an effective heat of gasification for the material. The pyrolysis or ignition time depends (for thermally thick conditions) on the material thermal inertia, the pyrolysis temperature, and the total heat flux from the flames to the wall, {dot q}{double_prime}{sub fw}. The present discovery was made possible by using both a numerical simulation, developed earlier, and exact similarity solutions, which are developed in this work. The predictions of the analysis have been validated by comparison with upward flame spread experiments on PMMA.

  1. ENG 4793: Composite Materials and Processes 1 Non-Destructive Testing (NDT)

    E-Print Network [OSTI]

    Colton, Jonathan S.

    1 ENG 4793: Composite Materials and Processes 1 Non-Destructive Testing (NDT) ver 1 ENG 4793: Composite Materials and Processes 2 Types of NDT · Visual · Ultrasonic · X-ray · Thermographic · Acoustic Emission · Eddy Current · Shearography ENG 4793: Composite Materials and Processes 3 Visual Inspection

  2. Material Testing Priorities for Hydrogen (H2) Infrastructure | 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 RankCombustion | Department of EnergyDevelopment Accident TolerantDepartment ofMaterial Balance Reportof

  3. Materials testing for in situ stabilization treatability study of INEEL mixed wastes soils

    SciTech Connect (OSTI)

    Heiser, J.; Fuhrmann, M. [Brookhaven National Lab., Upton, NY (United States)

    1997-09-01T23:59:59.000Z

    This report describes the contaminant-specific materials testing phase of the In Situ Stabilization Comprehensive Environment Response, Compensation, and Liability Act (CERCLA) Treatability Study (TS). The purpose of materials testing is to measure the effectiveness of grouting agents to stabilize Idaho National Engineering and Environmental Laboratory (INEEL) Acid Pit soils and select a grout material for use in the Cold Test Demonstration and Acid Pit Stabilization Treatability Study within the Subsurface Disposal Area (SDA) at the Radioactive Waste Management Complex (RWMC). Test results will assist the selecting a grout material for the follow-on demonstrations described in Test Plan for the Cold Test Demonstration and Acid Pit Stabilization Phases of the In Situ Stabilization Treatability Study at the Radioactive Waste Management Complex.

  4. An outdoor exposure testing program for optical materials used in solar thermal electric technologies

    SciTech Connect (OSTI)

    Wendelin, T.; Jorgensen, G.

    1994-01-01T23:59:59.000Z

    Developing low-cost, durable advanced optical materials is important for making solar thermal energy. technologies viable for electricity production. The objectives of a new outdoor testing program recently initiated by the National Renewable Energy Laboratory (NREL) are to determine the expected lifetimes of candidate reflector materials and demonstrate their optical durability in real-world service conditions. NREL is working with both utilities and industry in a collaborative effort to achieve these objectives. To date, simulated/accelerated exposure testing of these materials has not been correlated with actual outdoor exposure testing. Such a correlation is desirable to provide confidence in lifetime predictions based upon accelerated weathering results. This outdoor testing program will allow outdoor exposure data to be obtained for realistic environments and will establish a data base for correlating simulated/accelerated outdoor exposure data with actual outdoor exposure data. In this program, candidate reflector materials are subjected to various outdoor exposure conditions in a network of sites across the southwestern United States. Important meteorological data are continuously recorded at these sites; these data will be analyzed for possible correlations with material optical performance. Weathered samples are characterized on a regular basis using a series of optical tests. These tests provide the basis for tracking material performance and durability with exposure time in the various outdoor environments. This paper describes the outdoor testing program in more detail including meteorological monitoring capabilities and the optical tests that are performed on these materials.

  5. Enhanced In-pile Instrumentation for Material Testing Reactors

    SciTech Connect (OSTI)

    Joy Rempe; Darrell Knudson; Joshua Daw; Troy Unruh; Benjamin Chase; Kurt Davis; Robert Schley

    2012-07-01T23:59:59.000Z

    An increasing number of U.S. nuclear research programs are requesting enhanced in-pile instrumentation capable of providing real-time measurements of key parameters during irradiations. For example, fuel research and development funded by the U.S. Department of Energy now emphasize approaches that rely on first principle models to develop optimized fuel designs that offer significant improvements over current fuels. To facilitate this approach, high fidelity, real-time data are essential for characterizing the performance of new fuels during irradiation testing. Furthermore, sensors that obtain such data must be miniature, reliable and able to withstand high flux/high temperature conditions. Depending on user requirements, sensors may need to obtain data in inert gas, pressurized water, or liquid metal environments. To address these user needs, in-pile instrumentation development efforts have been initiated as part of the Advanced Test Reactor (ATR) National Scientific User Facility (NSUF), the Fuel Cycle Research & Development (FCR&D), and the Nuclear Energy Enabling Technology (NEET) programs. This paper reports on recent INL achievements to support these programs. Specifically, an overview of the types of sensors currently available to support in-pile irradiations and those sensors currently available to MTR users are identified. In addition, recent results and products available from sensor research and development are detailed. Specifically, progress in deploying enhanced in-pile sensors for detecting elongation and thermal conductivity are reported. Results from research to evaluate the viability of ultrasonic and fiber optic technologies for irradiation testing are also summarized.

  6. Corrosion tests of 316L and Hastelloy C-22 in simulated tank waste solutions

    SciTech Connect (OSTI)

    MJ Danielson; SG Pitman

    2000-02-23T23:59:59.000Z

    Both the 316L stainless steel and Hastelloy{reg_sign} C-22 gave satisfactory corrosion performance in the simulated test environments. They were subjected to 100 day weight loss corrosion tests and electrochemical potentiodynamic evaluation. This activity supports confirmation of the design basis for the materials of construction of process vessels and equipment used to handle the feed to the LAW-melter evaporator. BNFL process and mechanical engineering will use the information derived from this task to select material of construction for process vessels and equipment.

  7. Life and stability testing of packaged low-cost energy storage materials

    SciTech Connect (OSTI)

    Frysinger, G.R.

    1980-07-01T23:59:59.000Z

    A low-cost laminated plastic film which is used to contain a Glauber's salt-based phase change thermal energy storage material in sausage-like containers called Chubs is discussed. The results of tests performed on the Chub packages themselves and on the thermal energy storage capacity of the packaged phase change material are described. From the test results, a set of specifications have been drawn up for a film material which will satisfactorily contain the phase change material under anticipated operating conditions. Calorimetric testing of the phase change material with thermal cycling indicates that a design capacity of 45 to 50 Btu/lb for a ..delta..T of 30/sup 0/F can be used for the packaged material.

  8. Radioisotope thermoelectric generator package o-ring seal material validation testing

    SciTech Connect (OSTI)

    Adkins, H.E.; Ferrell, P.C.; Knight, R.C. [Westinghouse Hanford Company, P. O. Box 1970, MSIN N1-25, Richland, Washington 99352 (United States)

    1995-01-20T23:59:59.000Z

    The Radioisotope Thermoelectric Generator Package O-Ring Seal Material Validation Test was conducted to validate the use of the Butyl material as a primary seal throughout the required temperature range. Three tests were performed at (I) 233 K ({minus}40 {degree}F), (2) a specified operating temperature, and (3) 244 K ({minus}20 {degree}F) before returning to room temperature. Helium leak tests were performed at each test point to determine seal performance. The two major test objectives were to establish that butyl rubber material would maintain its integrity under various conditions and within specified parameters and to evaluate changes in material properties. {copyright} {ital 1995} {ital American} {ital Institute} {ital of} {ital Physics}

  9. Initial ACTR retrieval technology evaluation test material recommendations

    SciTech Connect (OSTI)

    Powell, M.R.

    1996-04-01T23:59:59.000Z

    Millions of gallons of radiaoctive waste are contained in underground storage tanks at Hanford (SE Washington). Techniques for retrieving much of this waste from the storage tanks have been developed. Current baseline approach is to use sluice jets for single-shell tanks and mixer pumps for double-shell tanks. The Acquire Commercial Technology for Retrieval (ACTR) effort was initiated to identify potential improvements in or alternatives to the baseline waste retrieval methods. Communications with a variety of vendors are underway to identify improved methods that can be implemented at Hanford with little or no additional development. Commercially available retrieval methods will be evaluated by a combination of testing and system-level cost estimation. Current progress toward developing waste simulants for testing ACTR candidate methods is reported; the simulants are designed to model 4 different types of tank waste. Simulant recipes are given for wet sludge, hardpan/dried sludge,hard saltcake, and soft saltcake. Comparisons of the waste and simulant properties are documented in this report.

  10. Outdoor testing of advanced optical materials for solar thermal electric applications

    SciTech Connect (OSTI)

    Wendelin, T.J.; Jorgensen, G.; Goggin, R.M.

    1992-05-01T23:59:59.000Z

    The development of low-cost, durable advanced optical materials is an important element in making solar energy viable for electricity production. It is important to determine the expected lifetime of candidate reflector materials in real-world service conditions. The demonstration of the optical durability of such materials in outdoor environments is critical to the successful commercialization of solar thermal electric technologies. For many years optical performance data have been collected and analyzed by the National Renewable Energy Laboratory (NREL) for candidate reflector materials subjected to simulated outdoor exposure conditions. Much of this testing is accelerated in order to predict service durability. Some outdoor testing has occurred but not in a systematic manner. To date, simulated/accelerated testing has been limited correlation with actual outdoor exposure testing. Such a correlation is desirable to provide confidence in lifetime predictions based upon accelerated weathering methods. To obtain outdoor exposure data for realistic environments and to establish a data base for correlating simulated/accelerated outdoor exposure data with actual outdoor exposure data, the development of an expanded outdoor testing program has recently been initiated by NREL. Several outdoor test sites will be selected based on the solar climate, potential for solar energy utilization by industry, and cost of installation. Test results are site dependent because exposure conditions vary with geographical location. The importance of this program to optical materials development is outlined, and the process used to determine and establish the outdoor test sites is described. Candidate material identification and selection is also discussed. 10 refs.

  11. Transient Testing of Nuclear Fuels and Materials in United States

    SciTech Connect (OSTI)

    Daniel M. Wachs

    2012-12-01T23:59:59.000Z

    The US Department of Energy (DOE) has been engaged in an effort to develop and qualify next generation LWR fuel with enhanced performance and safety and reduced waste generation since 2010. This program, which has emphasized collaboration between the DOE, U.S. national laboratories and nuclear industry, was refocused from enhanced performance to enhanced accident tolerance following the events at Fukushima in 2011. Accident tolerant fuels have been specifically described as fuels that, in comparison with standard UO2-Zircaloy, can tolerate loss of active cooling in the reactor core for a considerably longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, operational transients, as well as design-basis and beyond design-basis events. The program maintains an ambitious goal to insert a lead test assembly (LTA) of the new design into a commercial power reactor by 2022 .

  12. Classic tests of General Relativity described by brane-based spherically symmetric solutions

    E-Print Network [OSTI]

    R. R. Cuzinatto; P. J. Pompeia; M. de Montigny; F. C. Khanna; J. M. Hoff da Silva

    2014-09-03T23:59:59.000Z

    We discuss a way to obtain information about higher dimensions from observations by studying a brane-based spherically symmetric solution. The three classic tests of General Relativity are analyzed in details: the perihelion shift of the planet Mercury, the deflection of light by the Sun, and the gravitational redshift of atomic spectral lines. The braneworld version of these tests exhibits an additional parameter $b$ related to the fifth-coordinate. This constant $b$ can be constrained by comparison with observational data for massive and massless particles.

  13. Scale-up and Testing of Advanced Materials from the BATT Program...

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

    AMR Berkeley Lab 129 Scale-up and Testing of Advanced Materials from the BATT Program Vincent Battaglia, Ph.D. Lawrence Berkeley National Laboratory May 16, 2012 es029 This...

  14. Scale-up and Testing of Advanced Materials from the BATT Program...

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

    Scale-up and Testing of Advanced Materials from the BATT Program Vincent Battaglia, Ph.D. Lawrence Berkeley National Laboratory May 15, 2013 ES029) This presentation does not...

  15. Nonaqueous solution synthesis process for preparing oxide powders of lead zirconate titanate and related materials

    DOE Patents [OSTI]

    Voigt, J.A.; Sipola, D.L.; Tuttle, B.A.; Anderson, M.T.

    1999-06-01T23:59:59.000Z

    A process is disclosed for producing powders of perovskite-type compounds which comprises mixing a metal alkoxide solution with a lead acetate solution to form a homogeneous, clear metal solution, adding an oxalic acid/n-propanol solution to this metal solution to form an easily filterable, free-flowing precursor powder and then calcining this powder. This process provides fine perovskite-phase powders with ferroelectric properties which are particularly useful in a variety of electronic applications. 4 figs.

  16. Performance testing of elastomeric seal materials under low and high temperature conditions: Final report

    SciTech Connect (OSTI)

    BRONOWSKI,DAVID R.

    2000-06-01T23:59:59.000Z

    The US Department of Energy Offices of Defense Programs and Civilian Radioactive Waste Management jointly sponsored a program to evaluate elastomeric O-ring seal materials for radioactive material shipping containers. The report presents the results of low- and high-temperature tests conducted on 27 common elastomeric compounds.

  17. Studies of solution-processed organic light-emitting diodes and their materials

    SciTech Connect (OSTI)

    Hellerich, Emily [Ames Laboratory] [Ames Laboratory

    2013-05-15T23:59:59.000Z

    A hitherto unexplored approach is presented in which a small molecule is used as a host to polymer guests in solution-processed OLEDs. We find that the small molecule host results in much more efficient devices than the often-used alternative polymer host when used for the guests presented. It is likely that nano- and microstructural differences between the hosts contribute to the improvements, which highlights some interesting characteristics that can help to better understand the nature of these mixtures. A number of the guests used in this study were newly synthesized benzobisoxazole-based copolymers. New organic copolymers are presented that are based on the chemical structure of benzobisoxazoles, which have been shown in the past to have good electron transporting properties. The novel concept in this publication pertains to a change in the direction of polymerization, also known as the conjugation pathway, which we show increases the emission efficiency. This work highlights a unique and useful property of organic semiconducting materials in that they can be synthesized to create the desired characteristics. Earlier work is described that kick-started in our research group the use of small molecules in solution-processed OLEDs. Originally these devices were to be used in magnetoresistance studies, but the project took a different path when the devices were more efficient than expected. The efficient use of small molecules in solution-processed OLEDs is highlighted, which at the time was not often the case. Also, the important observation of the effect of solvent choice on the resultant film is emphasized, with discussion of the likely cause of these effects. Microcavity OLEDs are introduced in which the transparent anode ITO is replaced with semi-transparent thin silver, which creates an optical cavity within the devices. The goal was to expand a previous work that created an on-chip spectrometer covering wavelengths 493 to 639 nm. In this case, a spin-coated mixed emitting layer (EML) is used, consisting of a polymer and a small molecule that both emit in the near UV and blue. The resulting combined spectra gives a wide band that can be used to create narrow microcavity emission peaks of 373 to 469 nm, depending on the device thickness (i.e. the cavity’s optical length). In the process of this effort, the mixed EML presented interesting complexities that we attempt to explain via simulation and morphology study.

  18. Field Testing of Low-Cost Bio-Based Phase Change Material

    SciTech Connect (OSTI)

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

    2013-03-01T23:59:59.000Z

    A test wall built with phase change material (PCM)-enhanced loose-fill cavity insulation was monitored for a period of about a year in the warm-humid climate of Charleston, South Carolina. The test wall was divided into various sections, one of which contained only loose-fill insulation and served as a control for comparing and evaluating the wall sections with the PCM-enhanced insulation. This report summarizes the findings of the field test.

  19. Regulatory and extra-regulatory testing to demonstrate radioactive material packaging safety

    SciTech Connect (OSTI)

    Ammerman, D.J.

    1997-06-01T23:59:59.000Z

    Packages for the transportation of radioactive material must meet performance criteria to assure safety and environmental protection. The stringency of the performance criteria is based on the degree of hazard of the material being transported. Type B packages are used for transporting large quantities of radioisotopes (in terms of A{sub 2} quantities). These packages have the most stringent performance criteria. Material with less than an A{sub 2} quantity are transported in Type A packages. These packages have less stringent performance criteria. Transportation of LSA and SCO materials must be in {open_quotes}strong-tight{close_quotes} packages. The performance requirements for the latter packages are even less stringent. All of these package types provide a high level of safety for the material being transported. In this paper, regulatory tests that are used to demonstrate this safety will be described. The responses of various packages to these tests will be shown. In addition, the response of packages to extra-regulatory tests will be discussed. The results of these tests will be used to demonstrate the high level of safety provided to workers, the public, and the environment by packages used for the transportation of radioactive material.

  20. Testing for characterization of the materials from radiological point of view

    SciTech Connect (OSTI)

    Bercea, Sorin; Iliescu, Elena; Dudu, Dorin; Iancso, Georgeta [National Institute of R and D for Physics and Nuclear Engineering-Horia Hulubei , Reactorului 30 St, P.O.BOX MG-6,Magurele, cod 077125 (Romania)

    2013-12-16T23:59:59.000Z

    The nuclear techniques and materials are now used in a large number of applications, both in medicine and industry. Due to this fact, new materials are needed in order to assure the radiological protection of the personnel involved in these activities. But, finally, all these materials have to be tested for some specific parameters, in order to prove that they are adequate for the purposed for which they were created. One of the important parameters of the materials used for the radiological protection is the attenuation coefficient. The attenuation coefficient of the ionizing radiation composed by particles without electrical charge (X,?-ray and neutron) is the most important parameter for the materials used for the shielding of these ionizing radiation. This paper deals with the experimental methods developed for the determination of the attenuation of fast and thermal neutrons. These experimental methods, involved the use of Am-Be source and U-120 Cyclotron of IFIN-HH. For the tests which were done at the U-120 Cyclotron, a number of experiments had to be performed, in order to establish the irradiation geometry and the dose equivalent rates in front of and behind the material samples. The experimental results obtained for samples of several materials, confirmed the methods as adequate for the aim of the test.

  1. Use of Melt Flow Rate Test in Reliability Study of Thermoplastic Encapsulation Materials in Photovoltaic Modules

    SciTech Connect (OSTI)

    Moseley, J.; Miller, D.; Shah, Q.-U.-A. S. J.; Sakurai, K.; Kempe, M.; Tamizhmani, G.; Kurtz, S.

    2011-10-01T23:59:59.000Z

    Use of thermoplastic materials as encapsulants in photovoltaic (PV) modules presents a potential concern in terms of high temperature creep, which should be evaluated before thermoplastics are qualified for use in the field. Historically, the issue of creep has been avoided by using thermosetting polymers as encapsulants, such as crosslinked ethylene-co-vinyl acetate (EVA). Because they lack crosslinked networks, however, thermoplastics may be subject to phase transitions and visco-elastic flow at the temperatures and mechanical stresses encountered by modules in the field, creating the potential for a number of reliability and safety issues. Thermoplastic materials investigated in this study include PV-grade uncured-EVA (without curing agents and therefore not crosslinked); polyvinyl butyral (PVB); thermoplastic polyurethane (TPU); and three polyolefins (PO), which have been proposed for use as PV encapsulation. Two approaches were used to evaluate the performance of these materials as encapsulants: module-level testing and a material-level testing.

  2. Irradiation Testing of Blanket Materials at the HFR Petten with On Line Tritium Monitoring

    SciTech Connect (OSTI)

    Magielsen, A.J.; Laan, J.G. van der; Hegeman, J.B.J.; Stijkel, M.P.; Ooijevaar, M.A.G

    2005-07-15T23:59:59.000Z

    Irradiation experiments are performed in support of fusion blanket technology development. These comprise ceramic solid breeder materials, and a liquid Lithium Lead alloy, as well as blanket subassemblies and components. Experimental facilities at the HFR to study tritium release, permeation characteristics, and neutron irradiation performance, have recently been extended. This paper gives an overview on the tritium breeding materials irradiation programme and describes the facilities required for irradiation testing and on-line tritium measurement.

  3. Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium nitrate solutions

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01T23:59:59.000Z

    1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade plutonium nitrate solutions to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Plutonium by Controlled-Potential Coulometry Plutonium by Amperometric Titration with Iron(II) Plutonium by Diode Array Spectrophotometry Free Acid by Titration in an Oxalate Solution 8 to 15 Free Acid by Iodate Precipitation-Potentiometric Titration Test Method 16 to 22 Uranium by Arsenazo I Spectrophotometric Test Method 23 to 33 Thorium by Thorin Spectrophotometric Test Method 34 to 42 Iron by 1,10-Phenanthroline Spectrophotometric Test Method 43 to 50 Impurities by ICP-AES Chloride by Thiocyanate Spectrophotometric Test Method 51 to 58 Fluoride by Distillation-Spectrophotometric Test Method 59 to 66 Sulfate by Barium Sulfate Turbidimetric Test Method 67 to 74 Isotopic Composition by Mass Spectrom...

  4. 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

  5. Evaluation of methods, instrumentation and materials pertinent to quality assurance filter penetration testing

    SciTech Connect (OSTI)

    Scripsick, R.C.; Soderholm, S.C.; Tillery, M.I.

    1984-01-01T23:59:59.000Z

    Every high efficiency aerosol filter used in the Unites States Department of Energy (DOE) facilities is quality assurance (QA) tested at one of the DOE filter test facilities prior to installation. This testing presently includes measurement of filter penetration at rated airflow using a hot DOP aerosol generator, an Owl aerosol size analyzer, and a scattered-light photometer aerosol concentration monitor. Alternative penetration measurement methods for testing size 5 high efficiency aerosol filters which have rated airflow capacities of 1000 cubic feet/min (cfm, approx. 28 m/sup 3//min) are being studied at Los Alamos National Laboratory. These methods are intended to take advantage of commercially available aerosol instrumentation. A penetration test using a polydisperse aerosol produced with a modified Laskin nozzle aerosol generator was found to have promise as an alternative to the present test method. Such a test eliminates the difficulty in producing a monodisperse challenge aerosol, and takes advantage of state-of-the-art aerosol sizing instruments. Aerosol sizing and concentration measuring capabilities of a laser aerosol spectrometer (LAS) were evaluated with respect to the needs of QA filter penetration testing. An aerosol diluter was selected and evaluated for use with the LAS in making filter penetration measurements. Potential alternative test materials were scrutinized with respect to certain toxicological and physical criteria. Certain of these alternative materials were selected for further evaluation. Results of this evaluation and findings cited in the literature indicate that the selected materials could be easily adapted for use with the modified Laskin aerosol generator.

  6. Developing an Innovative Field Expedient Fracture Toughness Testing Protocol for Concrete Materials

    SciTech Connect (OSTI)

    Wang, Jy-An John [ORNL; Liu, Ken C [ORNL; Naus, Dan J [ORNL

    2008-09-01T23:59:59.000Z

    The Spiral Notch Torsion Fracture Toughness Test (SNTT) was developed recently to determine the intrinsic fracture toughness (KIC) of structural materials. The SNTT system operates by applying pure torsion to uniform cylindrical specimens with a notch line that spirals around the specimen at a 45? pitch. KIC values are obtained with the aid of a three-dimensional finite-element computer code, TOR3D-KIC. The SNTT method is uniquely suitable for testing a wide variety of materials used extensively in pressure vessel and piping structural components and weldments. Application of the method to metallic, ceramic, and graphite materials has been demonstrated. One important characteristic of SNTT is that neither a fatigue precrack or a deep notch are required for the evaluation of brittle materials, which significantly reduces the sample size requirement. In this paper we report results for a Portland cement-based mortar to demonstrate applicability of the SNTT method to cementitious materials. The estimated KIC of the tested mortar samples with compressive strength of 34.45 MPa was found to be 0.19 MPa m.

  7. Material Modeling and Development of a Realistic Dummy Testing Blast Induced Traumatic Brain Injury

    E-Print Network [OSTI]

    Farritor, Shane

    Material Modeling and Development of a Realistic Dummy Head for Testing Blast Induced Traumatic Brain Injury S. G. M. Hossain1, C. A. Nelson1, T. Boulet2, M. Arnoult2, L. Zhang2, A. Holmberg2, J. Hein occurrence rate of traumatic brain injury (TBI) ­ 1.4 million people in US per year ­ 50,000 deaths ­ 235

  8. 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

  9. Fully Solution-Processed Copper Chalcopyrite Thin Film Solar Cells: Materials Chemistry, Processing, and Device Physics

    E-Print Network [OSTI]

    Chung, Choong-Heui

    2012-01-01T23:59:59.000Z

    nanowire networks as window layers in thin film solar cells.window layer for fully solution-deposited thin filmITO) thin films by silver nanowire composite window layers

  10. Recent progress and tests of radiation resistant impregnation materials for Nb{sub 3}Sn coils

    SciTech Connect (OSTI)

    Bossert, R.; Krave, S.; Ambrosio, G.; Andreev, N.; Chlachidze, G.; Nobrega, A.; Novitski, I.; Yu, M.; Zlobin, A. V. [Technical Division, Fermi National Accelerator Laboratory, P.O. Box 500, Batavia, IL, 60510 (United States)

    2014-01-27T23:59:59.000Z

    Fermilab is collaborating with Lawrence Berkeley National Laboratory (LBNL) and Brookhaven National Laboratory (BNL) (US-LARP collaboration) to develop a large-aperture Nb{sub 3}Sn superconducting quadrupole for the Large Hadron Collider (LHC) luminosity upgrade. An important component of this work is the development of materials that are sufficiently radiation resistant for use in critical areas of the upgrade. This paper describes recent progress in characterization of materials, including the baseline CTD101K epoxy, cyanate ester blends, and Matrimid 5292, a bismaleimide-based system. Structural properties of “ten stacks” of cable impregnated with these materials are tested at room and cryogenic temperatures and compared to the baseline CT-101K. Experience with potting 1 and 2 meter long coils with Matrimid 5292 are described. Test results of a single 1-m coil impregnated with Matrimid 5292 are reported and compared to similar coils impregnated with the traditional epoxy.

  11. Examination of a Size-Change Test for Photovoltaic Encapsulation Materials (Presentation)

    SciTech Connect (OSTI)

    Miller, D. C.; Ji, L.; Kelly, G.; Gu, X.; Nickel, N.; Norum, P.; Shioda, T.; Tamizhmani, G.; Wohlgemuth, J. H.

    2012-08-01T23:59:59.000Z

    We examine a proposed test standard that can be used to evaluate the maximum representative change in linear dimensions of sheet encapsulation products for photovoltaic modules (resulting from their thermal processing). The proposed protocol is part of a series of material-level tests being developed within Working Group 2 of the Technical Committee 82 of the International Electrotechnical Commission. The characterization tests are being developed to aid module design (by identifying the essential characteristics that should be communicated on a datasheet), quality control (via internal material acceptance and process control), and failure analysis. Discovery and interlaboratory experiments were used to select particular parameters for the size-change test. The choice of a sand substrate and aluminum carrier is explored relative to other options. The temperature uniformity of +/- 5C for the substrate was confirmed using thermography. Considerations related to the heating device (hot-plate or oven) are explored. The time duration of 5 minutes was identified from the time-series photographic characterization of material specimens (EVA, ionomer, PVB, TPO, and TPU). The test procedure was revised to account for observed effects of size and edges. The interlaboratory study identified typical size-change characteristics, and also verified the absolute reproducibility of +/- 5% between laboratories.

  12. Examination of a Size-Change Test for Photovoltaic Encapsulation Materials: Preprint

    SciTech Connect (OSTI)

    Miller, D. C.; Wohlgemuth, J. H.; Gu, X.; Ji, L.; Kelly, G.; Gu, X.; Nickel, N.; Norum, P.; Shioda, T.; Tamizhmani, G.

    2012-08-01T23:59:59.000Z

    We examine a proposed test standard that can be used to evaluate the maximum representative change in linear dimensions of sheet encapsulation products for photovoltaic modules (resulting from their thermal processing). The proposed protocol is part of a series of material-level tests being developed within Working Group 2 of the Technical Committee 82 of the International Electrotechnical Commission. The characterization tests are being developed to aid module design (by identifying the essential characteristics that should be communicated on a datasheet), quality control (via internal material acceptance and process control), and failure analysis. Discovery and interlaboratory experiments were used to select particular parameters for the size-change test. The choice of a sand substrate and aluminum carrier is explored relative to other options. The temperature uniformity of +/- 5C for the substrate was confirmed using thermography. Considerations related to the heating device (hot-plate or oven) are explored. The time duration of 5 minutes was identified from the time-series photographic characterization of material specimens (EVA, ionomer, PVB, TPO, and TPU). The test procedure was revised to account for observed effects of size and edges. The interlaboratory study identified typical size-change characteristics, and also verified the absolute reproducibility of +/- 5% between laboratories.

  13. A field test of electromagnetic geophysical techniques for locating simulated in situ mining leach solution

    SciTech Connect (OSTI)

    Tweeton, D.R.; Hanson, J.C.; Friedel, M.J.; Sternberg, B.K.; Dahl, L.J.

    1994-01-01T23:59:59.000Z

    The US Bureau of Mines, The University of Arizona, Sandia National Laboratories, and Zonge Engineering and Research Organization, Inc., conducted cooperative field tests of six electromagnetic (EM) geophysical methods to compare their effectiveness in locating a brine solution simulating in situ leach solution or a high-conductivity plume of contamination. The brine was approximately 160 m below the surface. The testsite was the University's San Xavier experimental mine near Tucson, AZ. Geophysical surveys using surface and surface-borehole, time-domain electromagnetic (TEM) induction; surface controlled-source audiofrequency magnetotellurics (CSAMT); surface-borehole, frequency-domain electromagnetic (FEM) induction; crosshole FEM; and surface magnetic field ellipticity were conducted before and during brine injection. The surface TEM data showed a broad decrease in resistivity. CSAMT measurements with the conventional orientation did not detect the brine, but measurements with another orientation indicated some decrease in resistivity. The surface-borehole and crosshole methods located a known fracture and other fracture zones inferred from borehole induction logs. Surface magnetic field ellipticity data showed a broad decrease in resistivity at depth following brine injection.

  14. RADIATION HEAT TRANSFER ENVIRONMENT IN FIRE AND FURNACE TESTS OF RADIOACTIVE MATERIALS PAKCAGES

    SciTech Connect (OSTI)

    Smith, A

    2008-12-31T23:59:59.000Z

    The Hypothetical Accident Conditions (HAC) sequential test of radioactive materials packages includes a thermal test to confirm the ability of the package to withstand a transportation fire event. The test specified by the regulations (10 CFR 71) consists of a 30 minute, all engulfing, hydrocarbon fuel fire, with an average flame temperature of at least 800 C. The requirements specify an average emissivity for the fire of at least 0.9, which implies an essentially black radiation environment. Alternate test which provide equivalent total heat input at the 800 C time averaged environmental temperature may also be employed. When alternate tests methods are employed, such as furnace or gaseous fuel fires, the equivalence of the radiation environment may require justification. The effects of furnace and open confinement fire environments are compared with the regulatory fire environment, including the effects of gases resulting from decomposition of package overpack materials. The results indicate that furnace tests can produce the required radiation heat transfer environment, i.e., equivalent to the postulated pool fire. An open enclosure, with transparent (low emissivity) fire does not produce an equivalent radiation environment.

  15. Standard test method for analysis of isotopic composition of uranium in nuclear-grade fuel material by quadrupole inductively coupled plasma-mass spectrometry

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2000-01-01T23:59:59.000Z

    1.1 This test method is applicable to the determination of the isotopic composition of uranium (U) in nuclear-grade fuel material. The following isotopic weight percentages are determined using a quadrupole inductively coupled plasma-mass spectrometer (Q-ICP-MS): 233U, 234U, 235U, 236U, and 238U. The analysis can be performed on various material matrices after acid dissolution and sample dilution into water or dilute nitric (HNO3) acid. These materials include: fuel product, uranium oxide, uranium oxide alloys, uranyl nitrate (UNH) crystals, and solutions. The sample preparation discussed in this test method focuses on fuel product material but may be used for uranium oxide or a uranium oxide alloy. Other preparation techniques may be used and some references are given. Purification of the uranium by anion-exchange extraction is not required for this test method, as it is required by other test methods such as radiochemistry and thermal ionization mass spectroscopy (TIMS). This test method is also described i...

  16. Advanced Test Reactor National Scientific User Facility: Addressing advanced nuclear materials research

    SciTech Connect (OSTI)

    John Jackson; Todd Allen; Frances Marshall; Jim Cole

    2013-03-01T23:59:59.000Z

    The Advanced Test Reactor National Scientific User Facility (ATR NSUF), based at the Idaho National Laboratory in the United States, is supporting Department of Energy and industry research efforts to ensure the properties of materials in light water reactors are well understood. The ATR NSUF is providing this support through three main efforts: establishing unique infrastructure necessary to conduct research on highly radioactive materials, conducting research in conjunction with industry partners on life extension relevant topics, and providing training courses to encourage more U.S. researchers to understand and address LWR materials issues. In 2010 and 2011, several advanced instruments with capability focused on resolving nuclear material performance issues through analysis on the micro (10-6 m) to atomic (10-10 m) scales were installed primarily at the Center for Advanced Energy Studies (CAES) in Idaho Falls, Idaho. These instruments included a local electrode atom probe (LEAP), a field-emission gun scanning transmission electron microscope (FEG-STEM), a focused ion beam (FIB) system, a Raman spectrometer, and an nanoindentor/atomic force microscope. Ongoing capability enhancements intended to support industry efforts include completion of two shielded, irradiation assisted stress corrosion cracking (IASCC) test loops, the first of which will come online in early calendar year 2013, a pressurized and controlled chemistry water loop for the ATR center flux trap, and a dedicated facility intended to house post irradiation examination equipment. In addition to capability enhancements at the main site in Idaho, the ATR NSUF also welcomed two new partner facilities in 2011 and two new partner facilities in 2012; the Oak Ridge National Laboratory, High Flux Isotope Reactor (HFIR) and associated hot cells and the University California Berkeley capabilities in irradiated materials analysis were added in 2011. In 2012, Purdue University’s Interaction of Materials with Particles and Components Testing (IMPACT) facility and the Pacific Northwest Nuclear Laboratory (PNNL) Radiochemistry Processing Laboratory (RPL) and PIE facilities were added. The ATR NSUF annually hosts a weeklong event called User’s Week in which students and faculty from universities as well as other interested parties from regulatory agencies or industry convene in Idaho Falls, Idaho to see presentations from ATR NSUF staff as well as select researchers from the materials research field. User’s week provides an overview of current materials research topics of interest and an opportunity for young researchers to understand the process of performing work through ATR NSUF. Additionally, to increase the number of researchers engaged in LWR materials issues, a series of workshops are in progress to introduce research staff to stress corrosion cracking, zirconium alloy degradation, and uranium dioxide degradation during in-reactor use.

  17. Testing of organic waste surrogate materials in support of the Hanford organic tank program. Final report

    SciTech Connect (OSTI)

    Turner, D.A. [Westinghouse Hanford Co., Richland, WA (United States); Miron, Y. [Bureau of Mines (United States)

    1994-01-01T23:59:59.000Z

    To address safety issues regarding effective waste management efforts of underground organic waste storage tanks at the Hanford Site, the Bureau of Mines conducted a series of tests, at the request of the Westinghouse Hanford company. In this battery of tests, the thermal and explosive characteristics of surrogate materials, chosen by Hanford, were determined. The surrogate materials were mixtures of inorganic and organic sodium salts, representing fuels and oxidants. The oxidants were sodium nitrate and sodium nitrite. The fuels were sodium salts of oxalate, citrate and ethylenediamine tetraacetic acid (EDTA). Polyethylene powder was also used as a fuel with the oxidant(s). Sodium aluminate was used as a diluent. In addition, a sample of FeCN, supplied by Hanford was also investigated.

  18. Investigation of test methods, material properties, and processes for solar-cell encapsulants. Annual report

    SciTech Connect (OSTI)

    Willis, P. B.; Baum, B.

    1982-07-01T23:59:59.000Z

    Potentially useful low cost encapsulation materials are evaluated. The goal of the program is to identify, evaluate, test, and recommend encapsulant materials and processes for the production of cost-effective, long life solar cell modules. Technical investigations have concerned the development of advanced cure chemistries for lamination type pottants, the continued evaluation of soil resistant surface treatments, and the results of an accelerated aging test program for the comparison of material stabilities. Experiments are underway to assess the durability and cost effectiveness of coatings for protection of steel. Investigations are continuing with commercial maintenance coatings based on fluorocarbon and silicone-alkyd chemistries. Experiments were conducted to determine the effectiveness of occlusive coatings for wood products such as hard-board. An experimental program continued to determine the usefulness of soil resistant coatings. Primers were evaluated for effectiveness in bonding candidate pottants to outer covers, glass and substate materials. A program of accelerated aging and life predictive strategies is being conducted and data are reported for sunlamp exposure and thermal aging. Supporting activities are also discussed briefly. (LEW)

  19. Portal solution for external test system Each year a number of driven and dedicated students write their thesis in collaboration with

    E-Print Network [OSTI]

    : Test & Verifications Services Position: Student Skills Methodology: System design, user interface design, software testing analysis. Techniques: Experience from web development, good programming skillsPortal solution for external test system Each year a number of driven and dedicated students write

  20. Performance testing of aged hydrogen getters against criteria for interim safe storage of plutonium bearing materials.

    SciTech Connect (OSTI)

    Shepodd, Timothy J.; Nissen, April; Buffleben, George M.

    2006-01-01T23:59:59.000Z

    Hydrogen getters were tested for use in storage of plutonium-bearing materials in accordance with DOE's Criteria for Interim Safe Storage of Plutonium Bearing Materials. The hydrogen getter HITOP was aged for 3 months at 70 C and tested under both recombination and hydrogenation conditions at 20 and 70 C; partially saturated and irradiated aged getter samples were also tested. The recombination reaction was found to be very fast and well above the required rate of 45 std. cc H2h. The gettering reaction, which is planned as the backup reaction in this deployment, is slower and may not meet the requirements alone. Pressure drop measurements and {sup 1}H NMR analyses support these conclusions. Although the experimental conditions do not exactly replicate the deployment conditions, the results of our conservative experiments are clear: the aged getter shows sufficient reactivity to maintain hydrogen concentrations below the flammability limit, between the minimum and maximum deployment temperatures, for three months. The flammability risk is further reduced by the removal of oxygen through the recombination reaction. Neither radiation exposure nor thermal aging sufficiently degrades the getter to be a concern. Future testing to evaluate performance for longer aging periods is in progress.

  1. Model-based testing in the automotive industry challenges and solutions

    E-Print Network [OSTI]

    Peleska, Jan - Fachbereich 3

    Test specification System integration testing ­ model-based Test executionTest model Documentation... Requirements System integration testing ­ model-based SUT Sensors/busses Input interfaces Actors/busses Output interfaces #12;9 Overview 1. Model-based system integration testing 2. Integrating external models in the HW

  2. Influence of the electrode material on carbon monoxide adsorption and electroreduction in aqueous solutions

    SciTech Connect (OSTI)

    Osetrova, N.V.; Vasil'ev, Yu.B.

    1987-12-01T23:59:59.000Z

    Carbon monoxide electroreduction was studied at rotating disk electrodes made of different materials (Cu, Au, Zn, Cd; amalgamated Cu; Al, Ga, In, glassy carbon, Sn, Pb, Mo, Fe, Ni, and certain binary systems). Positive partial currents which are evidence for a direct electroreduction of CO have been observed only at Zn, Ga, and Cd. The observation that CO is less susceptible to electroreduction than carbon dioxide is explained by the stronger chemisorption of carbon monoxide on the electrodes.

  3. Elizabeth. K. Ervin JAM-10-1036 1 First Principles Estimation of Shock Tube Tests on Nanoreinforced Composite Materials

    E-Print Network [OSTI]

    Ervin, Elizabeth K.

    Composite Materials Weiping Xu1 , Elizabeth K. Ervin2 1 Lecturer, Civil Engineering, Southwest Jiaotong is necessary to more rapidly address dangerous shock problems. Composite materials have replaced metals of the specific complex case of composite materials tested in a shock tube. A modal analysis simulation of a beam

  4. Examination of an Optical Transmittance Test for Photovoltaic Encapsulation Materials (Presentation)

    SciTech Connect (OSTI)

    Miller, D.; Bengoechea, J.; Bokria, J.; Kohl, M.; Powell, N. E.; Smith, M. E.; White, M. D.; Wilson, H. R.; Wohlgemuth, J. H.

    2013-09-01T23:59:59.000Z

    The optical transmittance of encapsulation materials is a key characteristic for their use in photovoltaic (PV) modules. Changes in transmittance with time in the field affect module performance, which may impact product warranties. Transmittance is important in product development, module manufacturing, and field power production (both immediate and long-term). Therefore, an international standard (IEC 62788-1-4) has recently been proposed by the Encapsulation Task-Group within the Working Group 2 (WG2) of the International Electrotechnical Commission (IEC) Technical Committee 82 (TC82) for the quantification of the optical performance of PV encapsulation materials. Existing standards, such as ASTM E903, are general and more appropriately applied to concentrated solar power than to PV. Starting from the optical transmittance measurement, the solar-weighted transmittance of photon irradiance, yellowness index (which may be used in aging studies to assess durability), and ultraviolet (UV) cut-off wavelength may all be determined using the proposed standard. The details of the proposed test are described. The results of a round-robin experiment (for five materials) conducted at seven laboratories to validate the test procedure using representative materials are also presented. For example, the Encapsulation Group actively explored the measurement requirements (wavelength range and resolution), the requirements for the spectrophotometer (including the integrating sphere and instrument accessories, such as a depolarizer), specimen requirements (choice of glass-superstrate and -substrate), and data analysis (relative to the light that may be used in the PV application). The round-robin experiment identified both intra- and inter-laboratory instrument precision and bias for five encapsulation materials (encompassing a range of transmittance and haze-formation characteristics).

  5. Examination of an Optical Transmittance Test for Photovoltaic Encapsulation Materials: Preprint

    SciTech Connect (OSTI)

    Miller, D. C.; Bengoechea, J.; Bokria, J. G.; Kohl, M.; Powell, N. E.; Smith, M. E.; White, M. D.; Wilson, H. R.; Wohlgemuth, J. H.

    2013-09-01T23:59:59.000Z

    The optical transmittance of encapsulation materials is a key characteristic for their use in photovoltaic (PV) modules. Changes in transmittance with time in the field affect module performance, which may impact product warranties. Transmittance is important in product development, module manufacturing, and field power production (both immediate and long-term). Therefore, an international standard (IEC 62788-1-4) has recently been proposed by the Encapsulation Task-Group within the Working Group 2 (WG2) of the International Electrotechnical Commission (IEC) Technical Committee 82 (TC82) for the quantification of the optical performance of PV encapsulation materials. Existing standards, such as ASTM E903, are general and more appropriately applied to concentrated solar power than to PV. Starting from the optical transmittance measurement, the solar-weighted transmittance of photon irradiance, yellowness index (which may be used in aging studies to assess durability), and ultraviolet (UV) cut-off wavelength may all be determined using the proposed standard. The details of the proposed test are described. The results of a round-robin experiment (for five materials) conducted at seven laboratories to validate the test procedure using representative materials are also presented. For example, the Encapsulation Group actively explored the measurement requirements (wavelength range and resolution), the requirements for the spectrophotometer (including the integrating sphere and instrument accessories, such as a depolarizer), specimen requirements (choice of glass-superstrate and -substrate), and data analysis (relative to the light that may be used in the PV application). The round-robin experiment identified both intra- and inter-laboratory instrument precision and bias for five encapsulation materials (encompassing a range of transmittance and haze-formation characteristics).

  6. Standard test method for isotopic analysis of hydrolyzed uranium hexafluoride and uranyl nitrate solutions by thermal ionization mass spectrometry

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2005-01-01T23:59:59.000Z

    1.1 This method applies to the determination of isotopic composition in hydrolyzed nuclear grade uranium hexafluoride. It covers isotopic abundance of 235U between 0.1 and 5.0 % mass fraction, abundance of 234U between 0.0055 and 0.05 % mass fraction, and abundance of 236U between 0.0003 and 0.5 % mass fraction. This test method may be applicable to other isotopic abundance providing that corresponding standards are available. 1.2 This test method can apply to uranyl nitrate solutions. This can be achieved either by transforming the uranyl nitrate solution to a uranyl fluoride solution prior to the deposition on the filaments or directly by depositing the uranyl nitrate solution on the filaments. In the latter case, a calibration with uranyl nitrate standards must be performed. 1.3 This test method can also apply to other nuclear grade matrices (for example, uranium oxides) by providing a chemical transformation to uranyl fluoride or uranyl nitrate solution. 1.4 This standard does not purport to address al...

  7. 2006/07 Field Testing of Cellulose Fiber Insulation Enhanced with Phase Change Material

    SciTech Connect (OSTI)

    Kosny, Jan [ORNL; Yarbrough, David W [ORNL; Miller, William A [ORNL; Petrie, Thomas [ORNL; Childs, Phillip W [ORNL; Syed, Azam M [ORNL

    2008-12-01T23:59:59.000Z

    Most recent improvements in building envelope technologies suggest that in the near future, residences will be routinely constructed to operate with very low heating and cooling loads. In that light, the application of novel building materials containing active thermal components (e.g., phase change materials [PCMs,] sub-venting, radiant barriers, and integrated hydronic systems) is like a final step in achieving relatively significant heating and cooling energy savings from technological improvements in the building envelope. It is expected that optimized building envelope designs using PCMs for energy storage can effectively bring notable savings in energy consumption and reductions in peak hour power loads. During 2006/07, a research team at Oak Ridge National Laboratory (ORNL) performed a series of laboratory and field tests of several wall and roof assemblies using PCM-enhanced cellulose insulation. This report summarizes the test results from the perspective of energy performance. The ORNL team is working on both inorganic and organic PCMs; this report discusses only paraffinic PCMs. A limited economical analysis also is presented. PCMs have been tested as a thermal mass component in buildings for at least 40 years. Most of the research studies found that PCMs enhanced building energy performance. In the case of the application of organic PCMs, problems such as high initial cost and PCM leaking (surface sweating) have hampered widespread adoption. Paraffinic hydrocarbon PCMs generally performed well, with the exception that they increased the flammability of the building envelope.

  8. Use of Silicon Carbide as Beam Intercepting Device Material: Tests, Issues and Numerical Simulations

    E-Print Network [OSTI]

    Delonca, M; Gil Costa, M; Vacca, A

    2014-01-01T23:59:59.000Z

    Silicon Carbide (SiC) stands as one of the most promising ceramic material with respect to its thermal shock resistance and mechanical strengths. It has hence been considered as candidate material for the development of higher performance beam intercepting devices at CERN. Its brazing with a metal counterpart has been tested and characterized by means of microstructural and ultrasound techniques. Despite the positive results, its use has to be evaluated with care, due to the strong evidence in literature of large and permanent volumetric expansion, called swelling, under the effect of neutron and ion irradiation. This may cause premature and sudden failure, and can be mitigated to some extent by operating at high temperature. For this reason limited information is available for irradiation below 100°C, which is the typical temperature of interest for beam intercepting devices like dumps or collimators. This paper describes the brazing campaign carried out at CERN, the results, and the theoretical and numeric...

  9. Experience in testing of a solution mined storage cavern. [Strategic Petroleum Reserve

    SciTech Connect (OSTI)

    Goin, K.L.

    1982-01-01T23:59:59.000Z

    Recertification tests were made of the Department of Energy/Strategic Petroleum Reserve oil storage cavern number 6 in the West Hackberry, Louisiana Salt Dome. The cavern has a volume of 8,600,000 barrels. Tests included hydrostatic tests of the brine filled cavern and nitrogen leak tests of the three wells entering the cavern. Test procedures are described and test results are discussed.

  10. EA-1954: Resumption of Transient Testing of Nuclear Fuels and Materials at the Idaho National Laboratory, Idaho

    Broader source: Energy.gov [DOE]

    This Environmental Assessment (EA) evaluates U.S. Department of Energy (DOE) activities associated with its proposal to resume testing of nuclear fuels and materials under transient high-power test conditions at the Transient Reactor Test (TREAT) Facility at the Idaho National Laboratory. The State of Idaho and Shoshone-Bannock Tribes are cooperating agencies.

  11. Standard Test Method for Determination of the Susceptibility of Metallic Materials to Hydrogen Gas Embrittlement (HGE)

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2006-01-01T23:59:59.000Z

    1.1 This test method covers the quantitative determination of the susceptibility of metallic materials to hydrogen embrittlement, when exposed to high pressure gaseous hydrogen. 1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only. This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

  12. Field corrosion testing and performance of cable shielding materials in soils

    SciTech Connect (OSTI)

    Haynes, G.; Baboian, R. (Texas Instruments Inc., Electrochemical and Corrosion Lab., 34 Forest St., Mail Station 10-13, Attleboro, MA (US))

    1989-09-01T23:59:59.000Z

    This article discusses the importance of corrosion resistance in cable-shielding materials, describes the mechanisms of shielding corrosion that occur in buried telephone cable, and evaluates the results of the six-year REA Horry Cooperative buried telephone cable corrosion test. In this study, both active and static cables were included. Withdrawals were made over a six-year period. These cables were evaluated for cable-shielding corrosion. Special attention was paid to the comparative behavior of active and static cables. Results indicate that steel shieldings are most susceptible to the effects of alternating current (AC) in active cables. Results of a wide range of shieldings are presented and evaluated.

  13. The interactive effects of pH, surface tension, and solution density for flotation systems for separation of equivalent-density materials: separation of ABS from HIPS

    SciTech Connect (OSTI)

    Karvelas, D.E.; Jody, B.J.; Pomykala, J.A.; Daniels, E.J.

    1996-07-01T23:59:59.000Z

    This paper presents the results of research being conducted at Argonne National Laboratory, to develop a cost-effective and environmentally acceptable process for the separation of high-value plastics from discarded household appliances. The process under development has separated high-purity (greater than 99.5%) acrylonitrile-butadiene-styrene (ABS) and high-impact polystyrene (HIPS) from commingled plastics generated by appliance-shredding and metal recovery operations. Plastics of similar densities, such as ABS and HIPS are further separated by using a chemical solution. By controlling the surface tension, the density and the temperature of the chemical solution, we are able to selectively float/separate plastics that have equivalent densities. In laboratory-scale tests, this technique has proven highly effective in recovering high-purity plastics materials from discarded household appliances and other obsolete durable goods. A pilot plant is under construction to demonstrate and assess the technical and economic performance of this process. In this paper, we examine the technical and economic issues that affect the recovery and separation of plastics and provide an update on Argonne`s plastics separation research and development activities.

  14. 100-NR-2 Apatite Treatability Test FY09 Status: High Concentration Calcium-Citrate-Phosphate Solution Injection for In Situ Strontium-90 Immobilization

    SciTech Connect (OSTI)

    Vermeul, Vincent R.; Fritz, Brad G.; Fruchter, Jonathan S.; Szecsody, James E.; Williams, Mark D.

    2009-12-16T23:59:59.000Z

    100-NR-2 Apatite Treatability Test FY09 Status: High Concentration Calcium-Citrate-Phosphate Solution Injection for In Situ Strontium-90 Immobilization INTERIM LETTER REPORT

  15. Standard test method for isotopic abundance analysis of uranium hexa?uoride and uranyl nitrate solutions by multi-collector, inductively coupled plasma-mass spectrometry

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2008-01-01T23:59:59.000Z

    Standard test method for isotopic abundance analysis of uranium hexa?uoride and uranyl nitrate solutions by multi-collector, inductively coupled plasma-mass spectrometry

  16. Materials

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

    2 MAG LAB REPORTS Volume 18 No. 1 CONDENSED MATTER SCIENCE Technique development, graphene, magnetism & magnetic materials, topological insulators, quantum fl uids & solids,...

  17. FUNDAMENTAL ENVIRONMENTAL REACTIVITY TESTING AND ANALYSIS OF THE HYDROGEN STORAGE MATERIAL 2LIBH4 MGH2

    SciTech Connect (OSTI)

    James, C.; Anton, D.; Cortes-Concepcion, J.; Brinkman, K.; Gray, J.

    2012-01-10T23:59:59.000Z

    While the storage of hydrogen for portable and stationary applications is regarded as critical in bringing PEM fuel cells to commercial acceptance, little is known of the environmental exposure risks posed in utilizing condensed phase chemical storage options as in complex hydrides. It is thus important to understand the effect of environmental exposure of metal hydrides in the case of accident scenarios. Simulated tests were performed following the United Nations standards to test for flammability and water reactivity in air for a destabilized lithium borohydride and magnesium hydride system in a 2 to 1 molar ratio respectively. It was determined that the mixture acted similarly to the parent, lithium borohydride, but at slower rate of reaction seen in magnesium hydride. To quantify environmental exposure kinetics, isothermal calorimetry was utilized to measure the enthalpy of reaction as a function of exposure time to dry and humid air, and liquid water. The reaction with liquid water was found to increase the heat flow significantly during exposure compared to exposure in dry or humid air environments. Calorimetric results showed the maximum normalized heat flow the fully charged material was 6 mW/mg under liquid phase hydrolysis; and 14 mW/mg for the fully discharged material also occurring under liquid phase hydrolysis conditions.

  18. Long term materials test program. Quarterly report, October-December 1983

    SciTech Connect (OSTI)

    Not Available

    1984-01-01T23:59:59.000Z

    The long-term exposure of gas turbine vane and blade base alloys and a variety of protective coating systems to the effluent from a pressurized fluidized bed coal combustor has reached 4398 hours. After 4053 hours, FeCrAlY overlay coatings and platinum/rhodium-aluminide pack diffusion coatings show excellent resistance to corrosion attack at 1500/sup 0/F. Cobalt-base coatings are somewhat more susceptible to hot corrosion, and the unprotected nickel and cobalt-base alloys are most susceptible to corrosion, although corrosion rates have decreased to less than 1 mil/1000 hours for all materials at 1500/sup 0/F; i.e., corrosion penetration data is evolving parabolically. The three-stage cyclone cleanup system became severely distorted after approximately 5600 hours total service life. Distortion of the cyclones contributed to an increased dust loading to the material test sections, 110 to 250 ppM versus normal loadings of 30 to 90 ppM, for a period of about 75 hours. This increase in dust loading caused severe erosion of the airfoils in the high-velocity test section. Metal recession ranged 4 to 18 mils of leading edge loss on the impulse airfoils, and 11 to 27 mils of leading edge loss on the reaction airfoils. A new three-stage cyclone system was installed and dust loadings now range from 15 to 45 ppM.

  19. Department of Materials Science and Engineering Fall 2012 The Development and Testing of Composite Materials for Pump Wear Rings

    E-Print Network [OSTI]

    Demirel, Melik C.

    of Composite Materials for Pump Wear Rings Overview Flowserve currently uses two hardened steel wear rings, one rotating with the impellor, the other sitting stationary along the casing of their centrifugal pumps materials in the pump is believed to cut down on pump operating, maintenance, and assembly costs. Objectives

  20. Characterization of LWR spent fuel MCC-approved testing material-ATM-101

    SciTech Connect (OSTI)

    Barner, J.O.

    1984-06-01T23:59:59.000Z

    The characterization data, obtained to date, for Materials Characterization Center (MCC) Approved Testing Materials (ATM)-101, spent fuel from H.B. Robinson, Unit 2, Assembly BO-5, are described. ATM-101 consists of 27 equal-length segments from nine fuel rods. Characterizations provided for ATM-101 include, (1) reactor, assembly, and fuel rod descriptions, (2) Assembly BO-5 irradiation history, (3) a description of unusual incidents that occurred to the rods, (4) fission gas release measurements, (5) results of ceramography/metallography examinations, (6) fuel burnup measurement results and correlations, (7) results of gamma scanning, (8) calculated values of the radionuclide inventory, and (9) results of a radionuclide chemical overcheck. Calculations for and measurement of radial distributions of selected radionuclides are planned. A description of pertinent results from other studies on sibling rods from Assembly BO-5 is also included. The distribution of ATM-101 to date is described along with characterization results on specially processed material. It is intended that this report be revised and updated as additional characterization data become available. 6 references, 23 figures, 19 tables.

  1. FIFTH STATUS REPORT: TESTING OF AGED SOFTWOOD FIBERBOARD MATERIAL FOR THE 9975 SHIPPING PACKAGE

    SciTech Connect (OSTI)

    Daugherty, W.; Skidmore, E.; Dunn, K.

    2014-04-15T23:59:59.000Z

    Samples have been prepared from a 9975 lower fiberboard subassembly fabricated from softwood fiberboard. Physical, mechanical and thermal properties have been measured following varying periods of conditioning in each of several environments. These tests have been conducted in the same manner as previous testing on cane fiberboard samples. Overall, similar aging trends are observed for softwood and cane fiberboard samples, with a few differences. Some softwood fiberboard properties tend to degrade faster in elevated humidity environments, while some cane fiberboard properties degrade faster in the hotter dry environments. As a result, it is premature to assume both materials will age at the same rates, and the preliminary aging models developed for cane fiberboard might not apply to softwood fiberboard. However, it is expected that both cane and softwood fiberboard assemblies will perform satisfactorily in conforming packages stored in a typical KAC storage environment for up to 15 years. Aging and testing of softwood fiberboard will continue and additional data will be collected. Additional samples will be added to each aging environment, to support development of an aging model specific to softwood fiberboard. Post-conditioning data have been measured on samples from a single softwood fiberboard assembly, and baseline data are also available from a limited number of vendor-provided samples. This provides minimal information on the possible sample-to-sample variation exhibited by softwood fiberboard. Data to date are generally consistent with the range seen in cane fiberboard, but some portions of the data trends are skewed toward the lower end of that range. Two additional softwood fiberboard source packages have been obtained and will begin to provide data on the range of variability of this material.

  2. Testing large mixing MSW solutions of the solar neutrino problem through Earth regeneration effects

    E-Print Network [OSTI]

    Antonio Palazzo

    2001-03-02T23:59:59.000Z

    Large mixing MSW solutions to the solar neutrino problem appear to be currently favored by the data. We discuss the possibility of discriminating them by means of present and future experiments. In particular, we show that the study of energy and time dependence of the Earth regeneration effect can be useful in this respect.

  3. Closure Report for Corrective Action Unit 392: Spill Sites and Construction Materials, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    R. B. Jackson

    2002-02-01T23:59:59.000Z

    This Closure Report documents the closure activities that were conducted to close Corrective Action Unit (CAU) 392--Spill Sites and Construction Materials located on the Nevada Test Site (NTS). CAU 392 is listed on in Appendix III of the Federal Facility Agreement and Consent Order (FFACO) (FFACO, 1996) and consists of the following six Corrective Action Sites (CASs) located in Areas 5 and 6 of the NTS: CAS 05-17-02 Construction Materials/Lead Bricks; CAS 06-17-03 Cement Mud Pit; CAS 06-1 9-01 Cable Pile; Powder Piles (3); CAS 06-44-02 Paint Spill; CAS 06-44-03 Plaster Spill; CAS 06-44-04 Cutting Fluid Discharge Ditch. Closure activities were performed in two phases. Phase 1 activities consisted of collecting waste characterization samples of soil and material present on-site, and where appropriate, performing radiological screening of debris at the six CASs. Results were used to determine how waste generated during closure activities would be handled and disposed of, i.e., as nonhazardous sanitary or hazardous waste, etc. Phase 2 activities consisted of closing each CAS by removing debris and/or soil, disposing of the generated waste, and verifying that each CAS was clean closed by visual inspection and/or by the collecting soil verification samples for laboratory analysis. Copies of the analytical results for the site verification samples are included in Appendix A. Copies of the Sectored Housekeeping Site Closure Verification Form for each of the six CASs are included in Appendix 8. Appendix C contains a copy of the Bechtel Nevada (BN) On-site Waste Transport Manifest for the hazardous waste generated during closure of CAS 06-44-02.

  4. Cleaning and materials compatibility test results for elimination of flammable solvents in wipe applications.

    SciTech Connect (OSTI)

    Lopez, Edwin Paul

    2005-06-01T23:59:59.000Z

    In recent years, efforts have been made within the nuclear weapons complex (National Nuclear Security Administration) of the Department of Energy (DOE) to replace Resource Conservation and Recovery Act (RCRA) regulated solvents (i.e., flammable, toxic, corrosive, and reactive) and ozone-depleting chemicals (ODC) with more benign alternatives. Within the National Nuclear Security Administration (NNSA) and the Department of Defense (DoD) sectors, these solvents are used for cleaning hardware during routine maintenance operations. A primary goal of this study is to replace flammable solvents used in wiping applications. Two cleaners, including a hydrofluoroether (HFE) and an azeotrope of the HFE and isopropyl alcohol (IPA), have been studied as potential replacements for flammable solvents. Cleaning efficacy, short-term and long-term materials compatibility, corrosion, drying times, flammability, environment, safety and health (ES&H) and accelerated aging issues were among the experiments used to screen candidate solvents by the interagency team performing this work. This report presents cleaning efficacy results as determined by the contact angle Goniometer as well as materials compatibility results of various metal alloys and polymers. The results indicate that IPA (baseline cleaner) and the HFE/IPA azeotrope are roughly equivalent in their ability to remove fluorinated grease, silicone grease, and a simulated finger print contaminant from various metal alloys. All of the ASTM sandwich and immersion corrosion tests with IPA, HFE or the HFE/IPA azeotrope on metal alloys showed no signs of corrosion. Furthermore, no deleterious effects were noted for polymeric materials immersed in IPA, HFE, or the HFE/IPA azeotrope.

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

    SciTech Connect (OSTI)

    Benjamin Langhorst; Thomas M Lillo; Henry S Chu

    2014-05-01T23:59:59.000Z

    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.

  6. CALMOS: Innovative device for the measurement of nuclear heating in material testing reactors

    SciTech Connect (OSTI)

    Carcreff, H. [Alternative Energies and Atomic Energy Commission CEA, Saclay Center, DEN/DANS/DRSN/SIREN, Gif Sur Yvette, 91191 (France)

    2011-07-01T23:59:59.000Z

    An R and D program has been carried out since 2002 in order to improve gamma heating measurements in the 70 MWth OSIRIS Material Testing Reactor operated by CEA's Nuclear Energy Div. at the Saclay research center. Throughout this program an innovative calorimetric probe associated to a specific handling system has been designed in order to make measurements both along the fissile height and on the upper part of the core, where nuclear heating rates still remain high. Two mock-ups of the probe were manufactured and tested in 2005 and 2009 in ex-core area of OSIRIS reactor for the process validation, while a displacement system has been especially designed to move the probe axially. A final probe has been designed thanks to modeling results and to preliminary measurements obtained with mock-ups irradiated to a heating level of 2W/g, This paper gives an overview of the development, describes the calorimetric probe, and expected advantages such as the possibility to use complementary methods to get the nuclear heating measurement. Results obtained with mock-ups irradiated in ex-core area of the reactor are presented and discussed. (authors)

  7. Simulated Irradiation of Samples in HFIR for use as Possible Test Materials in the MPEX (Material Plasma Exposure Experiment) Facility

    SciTech Connect (OSTI)

    Ellis, Ronald James [ORNL; Rapp, Juergen [ORNL

    2014-01-01T23:59:59.000Z

    The importance of Plasma Material Interaction (PMI) is a major concern in fusion reactor design and analysis. The Material-Plasma Exposure eXperiment (MPEX) facility will explore PMI under fusion reactor plasma conditions. Samples with accumulated displacements per atom (DPA) damage produced by irradiations in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL) will be studied in the MPEX facility. The project presented in this paper involved performing assessments of the induced radioactivity and resulting radiation fields of a variety of potential fusion reactor materials. The scientific code packages MCNP and SCALE were used to simulate irradiation of the samples in HFIR; generation and depletion of nuclides in the material and the subsequent composition, activity levels, gamma radiation fields, and resultant dose rates as a function of cooling time. These state-of-the-art simulation methods were used in addressing the challenge of the MPEX project to minimize the radioactive inventory in the preparation of the samples for inclusion in the MPEX facility.

  8. JASPERSE CHEM 210 PRACTICE TEST 1 VERSION 3 Ch. 11 Liquids, Solids, and Materials

    E-Print Network [OSTI]

    Jasperse, Craig P.

    . 15 The Chemistry of Solutes and Solutions Ch. 13 Chemical Kinetics Constants and/or Formulas Formulas. Which of the following is an exothermic process: a. sublimation b. melting c. condensation d

  9. 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.

  10. WAFER TEST CAVITY -Linking Surface Microstructure to RF Performance: a ‘Short-­?Sample Test Facility’ for characterizing superconducting materials for SRF cavities.

    SciTech Connect (OSTI)

    Pogue, Nathaniel; Comeaux, Justin; McIntyre, Peter

    2014-05-30T23:59:59.000Z

    The Wafer Test cavity was designed to create a short sample test system to determine the properties of the superconducting materials and S?I?S hetero?structures. The project, funded by ARRA, was successful in accomplishing several goals to achieving a high gradient test system for SRF research and development. The project led to the design and construction of the two unique cavities that each severed unique purposes: the Wafer test Cavity and the Sapphire Test cavity. The Sapphire Cavity was constructed first to determine the properties of large single crystal sapphires in an SRF environment. The data obtained from the cavity greatly altered the design of the Wafer Cavity and provided the necessary information to ascertain the Wafer Test cavity’s performance.

  11. Testing of Dark Energy and a Solution of the Cosmological Constant Problem

    E-Print Network [OSTI]

    Vladimir Burdyuzha

    2014-01-19T23:59:59.000Z

    A probable solution of the cosmological constant problem was recently found. We propose that dark energy of the Universe is vacuum energy. Our Universe during its expansion is spending its vacuum energy for creation of new quantum states, but in the quantum regime phase transitions were more effective in reducing the vacuum energy than creation of new quantum states. Here we show how the 123 crisis orders of the vacuum energy are reduced by conventional physical processes in both the quantum and classical regimes of the Universe evolution. Numeral estimates of dark energy evolution are also presented.

  12. NREL Delivers In-Home HVAC Efficiency Testing Solutions (Fact Sheet)

    SciTech Connect (OSTI)

    Not Available

    2012-01-01T23:59:59.000Z

    Researchers at the National Renewable Energy Laboratory (NREL) have recently developed two simple in-home efficiency test methods that can be used by technicians, researchers, or interested homeowners to verify the correct operation and energy efficiency of a home's air conditioning equipment. An efficiency validation method for mini-split heat pumps (MSHPs) - highly efficient refrigerant-based air conditioning and heating systems that permit room-by-room conditioning and control - will enable building researchers to easily explore the installed performance of this class of equipment. MSHPs are very popular overseas and are gaining market share in energy efficient home upgrades throughout the United States. Yet, because MSHPs have multiple variable-speed components that work in tandem, their performance is challenging to measure in a real home. NREL researchers developed a field evaluation method including test equipment, methods, and data analysis to determine the installed performance of this equipment in occupied homes. A field test was conducted to validate the method. When testing a home's operation, it is often important to simulate occupancy within an unoccupied home. That way, the researcher will know the actual usage profiles for heat and moisture generation; this removes the uncertainty associated with real occupants. The second test method details a standardized protocol for generating heat and moisture loads, to mimic occupants and their activities by using heaters and humidifiers. Realistic heat and moisture loads can be used to drive air conditioning systems, evaluate air distribution systems, and examine building enclosure technologies. These loads are drawn from the Building America House Simulation Protocols. Proper application of the method will result in better comparison between performance of the test home and its simulated analogue. This method is also validated by field testing. These test methods are now available in two technical reports. The methods can be used widely by the building research community to confirm proper operation of space conditioning equipment in homes, thereby improving thermal comfort, building health, and durability. National objectives for cost-effective energy savings in the residential sector can be met more quickly and with greater consistency.

  13. Materials

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsrucLas Conchas recovery challenge fund LasDubey selectedContract Research Material

  14. Investigation of InP{sub x}As{sub 1?x} solid solutions and creation of the radiation-resistant materials on their basis

    SciTech Connect (OSTI)

    Kekelidze, Nodar [F.Tavadze Institute of Metallurgy and Materials Science,15 Kazbegistr, 0160 Tbilisi (Georgia); Iv.Javakhishvili Tbilisi State University, 1 Chavchavadze Ave., 0179 Tbilisi (Georgia); Kekelidze, Gizo; Aliyev, Vugar [Institute of Physics of National Academy of Sciences.33 H. Cavid Ave., AZ-1143 Baku (Azerbaijan); Kekelidze, David [Iv.Javakhishvili Tbilisi State University, 1 Chavchavadze Ave., 0179 Tbilisi (Georgia)

    2013-12-04T23:59:59.000Z

    The solid solutions InP{sub x}As{sub 1?x} were investigated before and after irradiation with fast neutrons and electrons. By use of the technology developed by us, we created the radiation-resistant materials enduring the high dose of hard radiation.

  15. Testing and Analysis of Low Cost Composite Materials Under Spectrum Loading and High Cycle Fatigue Conditions

    E-Print Network [OSTI]

    architecture, environment, flaws, and manufacturing method. Second, for a single E-glass/polyester material blades [1]. As wind turbines expand in both size and importance, improvements in materials and lifetime

  16. Test and evaluation of computerized nuclear material accounting methods. Final report

    SciTech Connect (OSTI)

    NONE

    1995-12-31T23:59:59.000Z

    In accordance with the definition of a Material Balance Area (MBA) as a well-defined geographical area involving an Integral operation, the building housing the BFS-1 and BFS-1 critical facilities is considered to consist of one MBA. The BFS materials are in the form of small disks clad in stainless steel and each disk with nuclear material has its own serial number. Fissile material disks in the BFS MBA can be located at three key monitoring points: BFS-1 facility, BFS-2 facility and main storage of BFS fissile materials (storage 1). When used in the BFS-1 or BFS-2 critical facilities, the fissile material disks are loaded in tubes (fuel rods) forming critical assembly cores. The following specific features of the BFS MBA should be taken into account for the purpose of computerized accounting of nuclear material: (1) very large number of nuclear material items (about 70,000 fissile material items); and (2) periodically very intensive shuffling of nuclear material items. Requirements for the computerized system are determined by basic objectives of nuclear material accounting: (1) providing accurate information on the identity and location of all items in the BFS material balance area; (2) providing accurate information on location and identity of tamper-indicating devices; (3) tracking nuclear material inventories; (4) issuing periodic reports; (5) assisting with the detection of material gains or losses; (6) providing a history of nuclear material transactions; (7) preventing unauthorized access to the system and data falsification. In August 1995, the prototype computerized accounting system was installed on the BFS facility for trial operation. Information on two nuclear material types was entered into the data base: weapon-grade plutonium metal and 36% enriched uranium dioxide. The total number of the weapon-grade plutonium disks is 12,690 and the total number of the uranium dioxide disks is 1,700.

  17. REVIEW OF SCIENTIFIC INSTRUMENTS 85, 083702 (2014) Tensile testing of materials at high temperatures above 1700

    E-Print Network [OSTI]

    Ritchie, Robert

    , the range of materials that meet both of these objectives is limited, with ceramic-matrix composites (CMCs the evolution of 3D damage mecha- nisms in ceramic composite materials under tensile loading at 1750 C. © 2014 Of the available CMC materials, textile composite struc- tures with 3D woven carbon or SiC fibers embedded within

  18. Synthesis, Characterization and Testing of Novel Anode and Cathode Materials for Li-Ion Batteries

    SciTech Connect (OSTI)

    White, Ralph E.; Popov, Branko N.

    2002-10-31T23:59:59.000Z

    During this program we have synthesized and characterized several novel cathode and anode materials for application in Li-ion batteries. Novel synthesis routes like chemical doping, electroless deposition and sol-gel method have been used and techniques like impedance, cyclic voltammetry and charge-discharge cycling have been used to characterize these materials. Mathematical models have also been developed to fit the experimental result, thus helping in understanding the mechanisms of these materials.

  19. Performance evaluation of booster materials in the plastic bonded explosive PBX 9502 in a hemispherical wave breakout test

    SciTech Connect (OSTI)

    Hooks, Daniel E [Los Alamos National Laboratory; Morris, John S [Los Alamos National Laboratory; Hill, Larry G [Los Alamos National Laboratory; Francois, Elizabeth [Los Alamos National Laboratory

    2008-01-01T23:59:59.000Z

    An explosive booster is normally required to initiate detonation in an insensitive high explosive (lHE). Booster materials must be ignitable by a conventional detonator and deliver sufficient energy and favorable pulse shape to initiate the IHE charge. The explosive booster should be as insensitive as reasonably possible to maintain the overall safety margin of the explosive assembly. A hemispherical wave breakout test termed the on ionskin test is one of the methods of testing the performance of booster materials in an initiation train assembly. There are several variations of this basic test which are known by other names. In this test, the wave breakout time-position history at the surface of a hemispherical IHE acceptor charge is recorded, and the relative uniformity of breakout allows qualitative comparison between booster candidates and quantitative comparison of several metrics. The results of a series of onionskin experiments evaluating the performance of some new booster formulations in the triaminotrinitrobenzene (TA TB) -based plastic bonded explosive PBX 9502 will be presented. The boosters were tested in an onionskin arrangement in which the booster pellet was cylindrical, and the tests were performed at a temperature of-55{sup o}C to emphasize variations in spreading performance. The modification from the traditional hemispherical geometry facilitated efficient explosive fabrication and charge assembly, but the results indicate that this geometry was not ideal for several reasons. Despite the complications arising from geometry, promising performance was observed from booster formulations including 3,3' -diamino-4,4'azoxyfurazan.

  20. Performance evaluation of diaminoazoxyfurazan (DAAF) as a booster material for insensitive high explosives using the onionskin test

    SciTech Connect (OSTI)

    Morris, John S [Los Alamos National Laboratory; Francois, Elizabeth G [Los Alamos National Laboratory; Hooks, Daniel E [Los Alamos National Laboratory; Hill, Larry G [Los Alamos National Laboratory; Harry, Herbert H [Los Alamos National Laboratory

    2010-11-09T23:59:59.000Z

    Initiation of insensitive high explosive (IHE) formulations requires the use of a booster explosive in the initiation train. Booster material selection is crucial, as the initiation must reliably function across some spectrum of physical parameters. The interest in DAAF for this application stems from the fact that it possesses many traits of an IHE but is shock sensitive enough to serve as an explosive booster. A hemispherical wave breakout test, termed the onionskin test, is one of the methods used to evaluate the performance of a booster material. The wave breakout time-position history at the surface of a hemisphericallHE charge is recorded and the relative uniformity of the breakout can be quantitatively compared between booster materials. A series of onionskin tests were performed to investigate breakout and propagation diaminoazoxyfurazan (DAAF) at low temperatures to evaluate ignition and detonation spreading in comparison to other explosives commonly used in booster applications. Some wave perturbation was observed with the DAAF booster in the onionskin tests presented. The results of these tests will be presented and discussed.

  1. Pries M161: Rock the test! Review sheet for Chapter 11 Chapter 11 is the most important material in the calculus curriculum. Try making flashcards!

    E-Print Network [OSTI]

    Pries, Rachel

    Pries M161: Rock the test! Review sheet for Chapter 11 Chapter 11 is the most important material for Taylor polynomials Tests for convergence For each test write down: i) what the test says; ii) a short explanation of why it is true; iii) an example of a series which converges by this test; iv) an example

  2. Dielectric-Loaded Microwave Cavity for High-Gradient Testing of Superconducting Materials

    E-Print Network [OSTI]

    Pogue, Nathaniel Johnston

    2011-08-08T23:59:59.000Z

    cavity to function appropriately, the large sapphire at the heart of the cavity must have specific inherent qualities. A second cavity was constructed to test these parameters: dielectric constant, loss tangent, and heat capacity. Several tests were...

  3. Line formation in the inner winds of classical T Tauri stars: testing the conical wind solution

    E-Print Network [OSTI]

    Kurosawa, Ryuichi

    2012-01-01T23:59:59.000Z

    We present the emission line profile models of hydrogen and helium based on the results from axisymmetric magnetohydrodynamics (MHD) simulations of the wind formed near the disk-magnetosphere boundary of classical T Tauri stars (CTTSs). We extend the previous outflow models of `the conical wind' by Romanova et al. to include a well defined magnetospheric accretion funnel flow which is essential for modelling the optical and near-infrared hydrogen and helium lines of CTTSs. Our MHD model shows outflows in conical shape with a half opening angle about 35 degrees. The flow properties such as the maximum outflow speed in the conical wind, maximum inflow speed in the accretion funnel, mass-accretion and mass-loss rates are comparable to those found in a typical CTTS. The density, velocity and temperature from the MHD simulations are used in a separate radiative transfer model to predict the line profiles and test the consistency of the MHD models with observations. The line profiles are computed with various combi...

  4. Calcium Film Based Testing of Edge-Seal Materials for Photovoltaic Applications (Presentation)

    SciTech Connect (OSTI)

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

    2011-04-01T23:59:59.000Z

    Because of the sensitivity of some photovoltaic devices to moisture-induced corrosion, they are packaged using impermeable front- and back-sheets with an edge seal to prevent moisture ingress. Evaluation of edge seal materials can be difficult because of the low permeation rates involved and/or non-Fickian behavior. Here, using a Ca film deposited on a glass substrate, we demonstrate the evaluation of edge seal materials in a manner that effectively duplicates their use in a photovoltaic application and compare the results with standard methods for measuring water vapor transport. We demonstrate how moisture permeation data from polymer films can be used to estimate moisture ingress rates and compare the results of these two methods. Encapsulant materials were also evaluated for comparison and to highlight the need for edge seals. Of the materials studied, dessicant-filled polyisobutene materials demonstrate by far the best potential to keep moisture out for a 20 to 30 year lifetime.

  5. Calcium Based Test Method for Evaluation of Photovoltaic Edge-Seal Materials (Presentation)

    SciTech Connect (OSTI)

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

    2011-02-01T23:59:59.000Z

    Because of the sensitivity of some photovoltaic devices to moisture-induced corrosion, they are packaged using impermeable front- and back-sheets with an edge seal to prevent moisture ingress. Evaluation of edge seal materials can be difficult because of the low permeation rates involved and/or non-Fickian behavior. Here, using a Ca film deposited on a glass substrate, we demonstrate the evaluation of edge seal materials in a manner that effectively duplicates their use in a photovoltaic application and compare the results with standard methods for measuring water vapor transport. We demonstrate how moisture permeation data from polymer films can be used to estimate moisture ingress rates and compare the results of these two methods. Encapsulant materials were also evaluated for comparison and to highlight the need for edge seals. Of the materials studied, dessicant-filled polyisobutene materials demonstrate by far the best potential to keep moisture out for a 20 to 30 year lifetime.

  6. Closure Report for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2009-08-01T23:59:59.000Z

    Corrective Action Unit (CAU) 166 is identified in the Federal Facility Agreement and Consent Order (FFACO) as 'Storage Yards and Contaminated Materials' and consists of the following seven Corrective Action Sites (CASs), located in Areas 2, 3, 5, and 18 of the Nevada Test Site: CAS 02-42-01, Condo Release Storage Yd - North; CAS 02-42-02, Condo Release Storage Yd - South; CAS 02-99-10, D-38 Storage Area; CAS 03-42-01, Conditional Release Storage Yard; CAS 05-19-02, Contaminated Soil and Drum; CAS 18-01-01, Aboveground Storage Tank; and CAS 18-99-03, Wax Piles/Oil Stain. Closure activities were conducted from March to July 2009 according to the FF ACO (1996, as amended February 2008) and the Corrective Action Plan for CAU 166 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office, 2007b). The corrective action alternatives included No Further Action and Clean Closure. Closure activities are summarized. CAU 166, Storage Yards and Contaminated Materials, consists of seven CASs in Areas 2, 3, 5, and 18 of the NTS. The closure alternatives included No Further Action and Clean Closure. This CR provides a summary of completed closure activities, documentation of waste disposal, and confirmation that remediation goals were met. The following site closure activities were performed at CAU 166 as documented in this CR: (1) At CAS 02-99-10, D-38 Storage Area, approximately 40 gal of lead shot were removed and are currently pending treatment and disposal as MW, and approximately 50 small pieces of DU were removed and disposed as LLW. (2) At CAS 03-42-01, Conditional Release Storage Yard, approximately 7.5 yd{sup 3} of soil impacted with lead and Am-241 were removed and disposed as LLW. As a BMP, approximately 22 ft{sup 3} of asbestos tile were removed from a portable building and disposed as ALLW, approximately 55 gal of oil were drained from accumulators and are currently pending disposal as HW, the portable building was removed and disposed as LLW, and accumulators, gas cylinders, and associated debris were removed and are currently pending treatment and disposal as MW. (3) At CAS 05-19-02, Contaminated Soil and Drum, as a BMP, an empty drum was removed and disposed as sanitary waste. (4) At CAS 18-01-01, Aboveground Storage Tank, approximately 165 gal of lead-impacted liquid were removed and are currently pending disposal as HW, and approximately 10 gal of lead shot and 6 yd{sup 3} of wax embedded with lead shot were removed and are currently pending treatment and disposal as MW. As a BMP, approximately 0.5 yd{sup 3} of wax were removed and disposed as hydrocarbon waste, approximately 55 gal of liquid were removed and disposed as sanitary waste, and two metal containers were grouted in place. (5) At CAS 18-99-03, Wax Piles/Oil Stain, no further action was required; however, as a BMP, approximately l.5 yd{sup 3} of wax were removed and disposed as hydrocarbon waste, and one metal container was grouted in place.

  7. Development of Dodecaniobate Keggin Chain Materials as Alternative Sorbents for SR and Actinide Removal from High-Level Nuclear Waste Solutions

    SciTech Connect (OSTI)

    Nyman, May; Bonhomme, Francois

    2004-03-28T23:59:59.000Z

    The current baseline sorbent (monosodium titanate) for Sr and actinide removal from Savannah River Site's high level wastes has excellent adsorption capabilities for Sr but poor performance for the actinides. We are currently investigating the development of alternative materials that sorb radionuclides based on chemical affinity and/or size selectivity. The polyoxometalates, negatively-charged metal oxo clusters, have known metal binding properties and are of interest for radionuclide sequestration. We have developed a class of Keggin-ion based materials, where the Keggin ions are linked in 1- dimensional chains separated by hydrated, charge-balancing cations. These Nb-based materials are stable in the highly basic nuclear waste solutions and show good selectivity for Sr and Pu. Synthesis, characterization and structure of these materials in their native forms and Sr-exchanged forms will be presented.

  8. Standard test methods for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade uranyl nitrate solutions

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    1999-01-01T23:59:59.000Z

    1.1 These test methods cover procedures for the chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of nuclear-grade uranyl nitrate solution to determine compliance with specifications. 1.2 The analytical procedures appear in the following order: Sections Determination of Uranium 7 Specific Gravity by Pycnometry 15-20 Free Acid by Oxalate Complexation 21-27 Determination of Thorium 28 Determination of Chromium 29 Determination of Molybdenum 30 Halogens Separation by Steam Distillation 31-35 Fluoride by Specific Ion Electrode 36-42 Halogen Distillate Analysis: Chloride, Bromide, and Iodide by Amperometric Microtitrimetry 43 Determination of Chloride and Bromide 44 Determination of Sulfur by X-Ray Fluorescence 45 Sulfate Sulfur by (Photometric) Turbidimetry 46 Phosphorus by the Molybdenum Blue (Photometric) Method 54-61 Silicon by the Molybdenum Blue (Photometric) Method 62-69 Carbon by Persulfate Oxidation-Acid Titrimetry 70 Conversion to U3O8 71-74 Boron by ...

  9. Standard test method for gamma energy emission from fission products in uranium hexafluoride and uranyl nitrate solution

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2005-01-01T23:59:59.000Z

    1.1 This test method covers the measurement of gamma energy emitted from fission products in uranium hexafluoride (UF6) and uranyl nitrate solution. It is intended to provide a method for demonstrating compliance with UF6 specifications C 787 and C 996 and uranyl nitrate specification C 788. 1.2 The lower limit of detection is 5000 MeV Bq/kg (MeV/kg per second) of uranium and is the square root of the sum of the squares of the individual reporting limits of the nuclides to be measured. The limit of detection was determined on a pure, aged natural uranium (ANU) solution. The value is dependent upon detector efficiency and background. 1.3 The nuclides to be measured are106Ru/ 106Rh, 103Ru,137Cs, 144Ce, 144Pr, 141Ce, 95Zr, 95Nb, and 125Sb. Other gamma energy-emitting fission nuclides present in the spectrum at detectable levels should be identified and quantified as required by the data quality objectives. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its us...

  10. Materials testing at the Hanna-IV and Hoe Creek-III in situ coal-gasification sites

    SciTech Connect (OSTI)

    Loop, R.B.; LaRue, D.M.

    1981-03-01T23:59:59.000Z

    Candidate structural alloys were exposed to the direct product gas stream during three different in situ coal gasification experiments at two sites. Physical appearance and chemical analysis indicate that the coating on the specimens following exposure is typical of condensed hydrocarbons, coal char, coal ash, and mineral particles from the overburden. Deposits on specimens from one test had a fairly high concentration of sulfur (about 8 w/o) while the others had very low sulfur concentrations (0.313 w/o and 0.014 w/o, respectively). Energy-dispersive x-ray spectra indicate that corrosion occurred principally by oxidation, with some sulfidation. Mean penetration rates expressed in millimetres/year were calculated from weight loss data. No material evaluated showed a truly unacceptable degradation. There was no consistent difference in the amount of material removed from specimens with or without welds. Specimens from one test experienced no consistent difference in material removal between different exposure angles; a consistent difference in material loss and dents from particle impact indicated that erosion may have occurred in the other two tests. There was no indication of carburization, decarburization, or severe localized attack in the form of pitting or intergranular corrosion on any of the specimens examined. Results obtained for the flame-sprayed 316 SS specimens and one of the Alonized specimens indicated that use of these processes may be questionable in this environment.

  11. Analysis of material disposition for Illinois {number_sign}6 coal POC testing at the CFFF

    SciTech Connect (OSTI)

    Jackson, D.M.

    1993-06-01T23:59:59.000Z

    The Illinois No.6 coal Proof-of-Concept (POC) bottoming cycle testing began in August of 1987 with test LMF4K. POC testing of this coal was completed in November of 1990 with test LMF4V, and included a total of over 2003 hours of coal-fired operation. This testing was conducted to permit the evaluation of effects of long duration operation on a number of critical design issues. During all of the POC testing, all Heat-Recovery/Seed Recovery (HRSR) components, with the exception of the wet electrostatic precipitator (ESP), were installed and operational. Throughout this time, measurements were made of all major solid feed and product streams entering and leaving the CFFF flow train. In addition, key process variables, including mass flowrates and gas compositions, were measured continuously during testing. Particulate samples were obtained and chemically analyzed, and dust loading measurements, at several locations in the flow train, were made during many of the tests. After testing, major waste and product streams were analyzed for chemical composition. Combined, this information was sufficient to enable an overall mass balance as well as a number of elemental balances to be performed around the flow train for each test.

  12. Fracture characterization of clays and clay-like materials using flattened Brazilian Test

    E-Print Network [OSTI]

    Agaiby, Shehab Sherif Wissa

    2013-01-01T23:59:59.000Z

    Fracture mechanics has been used for many years to study the mechanical behavior of brittle and quasi-brittle materials like concrete, rock, wood, and ceramics. To date, the application of fracture mechanics to soils has ...

  13. On the modeling of the Taylor cylinder impact test for orthotropic textured materials: Calculations and experiments

    SciTech Connect (OSTI)

    Maudlin, P.J.; Bingert, J.F.; House, J.W.

    1997-04-01T23:59:59.000Z

    Taylor impact tests using specimens cut from a rolled plate of Ta were conducted. The Ta was well-characterized in terms of flow stress and crystallographic texture. A piece-wise yield surface was interrogated from this orthotropic texture, and used in EPIC-95 3D simulations of the Taylor test. Good agreement was realized between the calculations and the post-test geometries in terms of major and minor side profiles and impact-interface footprints.

  14. An evaluation of membrane materials for the treatment of highly concentrated suspended salt solutions in reverse osmosis and nanofiltration processes for desalination

    E-Print Network [OSTI]

    Hughes, Trenton Whiting

    2009-05-15T23:59:59.000Z

    of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE December 2006 Major Subject: Civil Engineering AN EVALUATION OF MEMBRANE MATERIALS FOR THE TREATMENT OF HIGHLY... CONCENTRATED SUSPENDED SALT SOLUTIONS IN REVERSE OSMOSIS AND NANOFILTRATION PROCESSES FOR DESALINATION A Thesis by TRENTON WHITING HUGHES Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment...

  15. Materials and Manufacturing

    E-Print Network [OSTI]

    Environmental Assurance Anne Meinhold Unprecedented Accomplishments in the Use of Aluminum-Lithium Alloy Preston is the solution. Other times, the design must accommodate the limitations of materials properties. The design requirements, and written procedures. Nondestructive testing depends on incident or input energy that interacts

  16. PERFORMANCE TESTING OF SPRING ENERGIZED C-RINGS FOR USE IN RADIOACTIVE MATERIAL PACKAGINGS CONTAINING TRITIUM

    SciTech Connect (OSTI)

    Blanton, P; Kurt Eberl, K

    2007-10-23T23:59:59.000Z

    This paper describes the sealing performance testing and results of silver-plated inconel Spring Energized C-Rings used for tritium containment in radioactive shipping packagings. The test methodology used follows requirements of the American Society of Mechanical Engineers (ASME) summarized in ASME Pressure Vessel Code (B&PVC), Section V, Article 10, Appendix IX (Helium Mass Spectrometer Test - Hood Technique) and recommendations by the American National Standards Institute (ANSI) described in ANSI N14.5-1997. The tests parameters bound the predicted structural and thermal responses from conditions defined in the Code of Federal Regulations 10 CFR 71. The testing includes an evaluation of the effects of pressure, temperature, flange deflection, surface roughness, permeation, closure torque, torque sequencing and re-use on performance of metal C-Ring seals.

  17. Milestone Report - Complete New Adsorbent Materials for Marine Testing to Demonstrate 4.5 g-U/kg Adsorbent

    SciTech Connect (OSTI)

    Janke, Christopher James [ORNL; Das, Sadananda [ORNL; Oyola, Yatsandra [ORNL; Mayes, Richard T. [ORNL; Saito, Tomonori [ORNL; Brown, Suree [ORNL; Gill, Gary [PNNL; Kuo, Li-Jung [PNNL; Wood, Jordana [PNNL

    2014-08-01T23:59:59.000Z

    This report describes work on the successful completion of Milestone M2FT-14OR03100115 (8/20/2014) entitled, “Complete new adsorbent materials for marine testing to demonstrate 4.5 g-U/kg adsorbent”. This effort is part of the Seawater Uranium Recovery Program, sponsored by the U.S. Department of Energy, Office of Nuclear Energy, and involved the development of new adsorbent materials at the Oak Ridge National Laboratory (ORNL) and marine testing at the Pacific Northwest National Laboratory (PNNL). ORNL has recently developed two new families of fiber adsorbents that have demonstrated uranium adsorption capacities greater than 4.5 g-U/kg adsorbent after marine testing at PNNL. One adsorbent was synthesized by radiation-induced graft polymerization of itaconic acid and acrylonitrile onto high surface area polyethylene fibers followed by amidoximation and base conditioning. This fiber showed a capacity of 4.6 g-U/kg adsorbent in marine testing at PNNL. The second adsorbent was prepared by atom-transfer radical polymerization of t-butyl acrylate and acrylonitrile onto halide-functionalized round fibers followed by amidoximation and base hydrolysis. This fiber demonstrated uranium adsorption capacity of 5.4 g-U/kg adsorbent in marine testing at PNNL.

  18. Standard test method for evaluating stress-corrosion cracking of stainless alloys with different nickel content in boiling acidified sodium chloride solution

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2000-01-01T23:59:59.000Z

    1.1 This test method describes a procedure for conducting stress-corrosion cracking tests in an acidified boiling sodium chloride solution. This test method is performed in 25% (by mass ) sodium chloride acidified to pH 1.5 with phosphoric acid. This test method is concerned primarily with the test solution and glassware, although a specific style of U-bend test specimen is suggested. 1.2 This test method is designed to provide better correlation with chemical process industry experience for stainless steels than the more severe boiling magnesium chloride test of Practice G36. Some stainless steels which have provided satisfactory service in many environments readily crack in Practice G36, but have not cracked during interlaboratory testing using this sodium chloride test method. 1.3 This boiling sodium chloride test method was used in an interlaboratory test program to evaluate wrought stainless steels, including duplex (ferrite-austenite) stainless and an alloy with up to about 33% nickel. It may also b...

  19. Materials Science and Engineering A 423 (2006) 2427 Experimental and computational study on the load-jump tests of AlMg

    E-Print Network [OSTI]

    Dao, Ming

    2006-01-01T23:59:59.000Z

    ) comparison of indentation creep curve (ICC) right after load jumping and that for the corresponding constant-load on the load-jump tests of Al­Mg solid­solution alloy using instrumented indentation technique H. Takagia,, M January 2006 Abstract Constant-load tests and load-jump tests were carried out using a microindenter in Al

  20. EIS-0017: Fusion Materials Irradiation Testing Facility, Hanford Reservation, Richland, Washington

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy developed this statement to evaluate the environmental impacts associated with proposed construction and operation of an irradiation test facility, the Deuterium-Lithium High Flux Neutron Source Facility, at the Hanford Reservation.

  1. Investigation of test methods, material properties, and processes for solar cell encapsulants. Annual report

    SciTech Connect (OSTI)

    Willis, P. B.; Baum, B.; Schnitzer, H. S.

    1980-07-01T23:59:59.000Z

    The goal of this program is to identify, evaluate, and recommend encapsulant materials and processes for the production of cost-effective, long-life solar cell modules. Technical activities during the past year have covered a number of topics and have emphasized the development of solar module encapsulation technology that employs ethylene/vinyl acetate, copolymer (EVA) as the pottant. These activities have included: (1) continued production of encapsulation grade EVA in sheet form to meet the needs of the photovoltaic industry; (2) investigations of three non-blocking techniques for EVA sheet; (3) performed an economic analysis of the high volume production of each pottant in order to estimate the large volume selling price (EVA, EPDM, aliphatic urethane, PVC plastisol, and butyl acrylate); (4) initiated an experimental corrosion protection program to determine if metal components could be successfully protected by encapsulation; (5) began an investigation to determine the maximum temperature which can be tolerated by the candidate pottant material in the event of hot spot heating or other temperature override; (6) continuation of surveys of potentially useful outer cover materials; and (7) continued with the accelerated artificial weathering of candidate encapsulation materials. Study results are presented. (WHK)

  2. SIMULATION OF A TYPICAL HOUSE IN THE REGION OF ANTANANARIVO, MADAGASCAR DETERMINATION OF PASSIVE SOLUTIONS USING LOCAL MATERIALS

    E-Print Network [OSTI]

    Boyer, Edmond

    SIMULATION OF A TYPICAL HOUSE IN THE REGION OF ANTANANARIVO, MADAGASCAR DETERMINATION OF PASSIVE union ABSTRACT This paper deals with new proposals for the design of passive solutions adapted use raw wood to warm the poorly designed houses. This leads to a large scale deforestation

  3. High Temperature Expansion Due to Compression Test for the Determination of a Cladding Material Failure Criterion under RIA Loading Conditions

    SciTech Connect (OSTI)

    Le Saux, M.; Poussard, C.; Averty, X.; Sainte Catherine, C.; Carassou, S. [CEA-Saclay, DEN/DMN/SEMI, 91191 Gif-Sur-Yvette (France); Besson, J. [Centre des Materiaux, Mines Paris, CNRS UMR 7633, BP 87, 91003 Evry (France)

    2007-07-01T23:59:59.000Z

    This paper is mainly dedicated to the development of an out-of-pile test reproducing the thermo-mechanical loading conditions encountered during the first stage of a Reactivity Initiated Accidents (RIA) transient, dominated by Pellet Clad Mechanical Interaction (PCMI). In particular, the strain-controlled clad loading under high strain rate associated with temperatures up to 600 deg. C expected during the PCMI phase is simulated by an Expansion Due to Compression (EDC) test achievable at high temperature. The use of appropriate materials for the inner pellet made it possible to achieve the tests from 20 deg. C up to 900 deg. C. The interpretation of the test data is supported by Finite Element Analysis (FEA) including parameters tuned using an inverse method coupling FEA and tests results. A deformation model, identified upon the PROMETRA (Transient Mechanical Properties) experimental database and describing the anisotropic viscoplastic behavior of Cold-Worked Stress Relieved Zircaloy-4 cladding alloys under typical RIA loading conditions, is exploited. The combined analysis of experimental results and finite element simulations provides a deeper understanding of the deformation mode (near pure hoop tension) that arises during the tests. The failure mode appears to be representative of that obtained on tubes during the PCMI stage of RIA experiments. An appropriate device is currently developed in order to reach a bi-axiality of the loading path closer to that expected during the PCMI stage (between plane-strain and equal-biaxial tension). (authors)

  4. Testing of candidate materials for their resistance to alkali-vapor adsorption in PFBC and gasification environments. Final report

    SciTech Connect (OSTI)

    Lee, S.H.D.; Natesan, K.; Swift, W.M.

    1995-08-01T23:59:59.000Z

    Laboratory-scale studies were performed to identify metallic material(s) having no, or limited, affinity for alkali vapors in an environment of either the off-gas from pressurized fluidized-bed combustion (PFBC) or the fuel gas from coal gasification. Such materials would be potential candidates for use as components in advanced coal-utilization systems. The following materials were tested for adsorption of NaCl vapor at 870--875 C and atmospheric pressure in a simulated PFBC off-gas (oxidizing) doped with 80 ppmW NaCl vapor: iron-based Type 304 stainless steel (304 SS), nickel-based Hastelloy C-276 and Hastelloy X alloys, cobalt-based Haynes No. 188 alloy, noble-metal-coated 304 SS, aluminized 304 SS, and ZrO{sub 2}-coated 304 SS. The Haynes No. 188 alloy and the aluminized 304 SS were also tested for their NaCl-vapor adsorption in a simulated gasification fuel gas (reducing) under the same test conditions as in the PFBC off-gas test. After 100 h of testing, the specimens were analyzed with a SEM equipped with an energy dispersive X-ray analyzer, and by an AES. The aluminized 304 SS had the least tendency to adsorb NaCl vapor, as well as an excellent resistance to corrosion as a result of the formation of a protective layer of Al{sub 2}O{sub 3} on its surface. In the reducing environment, however, the aluminized 304 SS was badly corroded by H{sub 2}S attack. The Haynes No. 188 showed virtually no NaCl-vapor adsorption and only limited H{sub 2}S attack. The authors recommend further long-term parametric studies to quantitate alkali-vapor adsorption as a function of operating variables for (1) the aluminized 304 SS in the PFBC off-gas environment and (2) the Haynes No. 188 in the gasification fuel gas environment.

  5. 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.

  6. Near-real-time materials accountancy: Use of SITMUF and page's test to detect losses occurring in a complex pattern

    SciTech Connect (OSTI)

    Jones, B.J.

    1987-01-01T23:59:59.000Z

    It is probably accepted that near-real-time materials accountancy (NRTMA) can lead to a more timely detection of losses. However, there may be some concern that this timeliness can be gained only at the expense of a power reduction to ultimately detect a loss of a given size. It has been demonstrated the NRTMA, using the standardized independent transformed material unaccounted for (MUF) SITMUF values and Page's test, is superior to conventional accountancy in three ways. Further aspects of the performance of NRTMA using Page's test are investigated. Reference 1 did not consider the case of protracted losses occurring at a variable rate or in an intermittent fashion. Both of these aspects are considered. Another factor that might be expected to affect the behavior of Page's test, namely, the frequency with which balances are taken, is studied. These investigations were all carried out using data from a model with characteristics similar to those expected at the new British Nuclear Fuels Thermal Oxide Reprocessing Plant.

  7. DEVELOPMENT OF A SENSOR NETWORK TEST BED FOR ISD MATERIALS AND STRUCUTRAL CONDITION MONITORING

    SciTech Connect (OSTI)

    Zeigler, K.; Ferguson, B.; Karapatakis, D.; Herbst, C.; Stripling, C.

    2011-07-06T23:59:59.000Z

    The P Reactor at the Savannah River Site is one of the first reactor facilities in the US DOE complex that has been placed in its end state through in situ decommissioning (ISD). The ISD end state consists of a grout-filled concrete civil structure within the concrete frame of the original building. To evaluate the feasibility and utility of remote sensors to provide verification of ISD system conditions and performance characteristics, an ISD Sensor Network Test Bed has been designed and deployed at the Savannah River National Laboratory. The test bed addresses the DOE-EM Technology Need to develop a remote monitoring system to determine and verify ISD system performance. Commercial off-the-shelf sensors have been installed on concrete blocks taken from walls of the P Reactor Building. Deployment of this low-cost structural monitoring system provides hands-on experience with sensor networks. The initial sensor system consists of: (1) Groutable thermistors for temperature and moisture monitoring; (2) Strain gauges for crack growth monitoring; (3) Tiltmeters for settlement monitoring; and (4) A communication system for data collection. Preliminary baseline data and lessons learned from system design and installation and initial field testing will be utilized for future ISD sensor network development and deployment.

  8. Waste Isolation Pilot Plant Materials Interface Interactions Test: Papers presented at the Commission of European Communities workshop on in situ testing of radioactive waste forms and engineered barriers

    SciTech Connect (OSTI)

    Molecke, M.A.; Sorensen, N.R. [eds.] [Sandia National Labs., Albuquerque, NM (US); Wicks, G.G. [ed.] [Westinghouse Savannah River Technology Center, Aiken, SC (US)

    1993-08-01T23:59:59.000Z

    The three papers in this report were presented at the second international workshop to feature the Waste Isolation Pilot Plant (WIPP) Materials Interface Interactions Test (MIIT). This Workshop on In Situ Tests on Radioactive Waste Forms and Engineered Barriers was held in Corsendonk, Belgium, on October 13--16, 1992, and was sponsored by the Commission of the European Communities (CEC). The Studiecentrum voor Kernenergie/Centre D`Energie Nucleaire (SCK/CEN, Belgium), and the US Department of Energy (via Savannah River) also cosponsored this workshop. Workshop participants from Belgium, France, Germany, Sweden, and the United States gathered to discuss the status, results and overviews of the MIIT program. Nine of the twenty-five total workshop papers were presented on the status and results from the WIPP MIIT program after the five-year in situ conclusion of the program. The total number of published MIIT papers is now up to almost forty. Posttest laboratory analyses are still in progress at multiple participating laboratories. The first MIIT paper in this document, by Wicks and Molecke, provides an overview of the entire test program and focuses on the waste form samples. The second paper, by Molecke and Wicks, concentrates on technical details and repository relevant observations on the in situ conduct, sampling, and termination operations of the MIIT. The third paper, by Sorensen and Molecke, presents and summarizes the available laboratory, posttest corrosion data and results for all of the candidate waste container or overpack metal specimens included in the MIIT program.

  9. The Impact of the Item Types and Number of Solution Steps of Multiple-Choice Items on Item Difficulty and Discrimination and Test Reliability

    E-Print Network [OSTI]

    Atalmis, Erkan Hasan

    2014-08-31T23:59:59.000Z

    The Impact of the Item Types and Number of Solution Steps of Multiple-Choice Items on Item Difficulty and Discrimination and Test Reliability By Erkan Hasan Atalmis Submitted to the graduate degree program in the Department of Psychology... ________________________________ Bruce Frey ________________________________ Marianne Perie ________________________________ Argun Saatcioglu ________________________________ William Skorupski Date Defended: 5/5/14 The Dissertation Committee for Erkan Hasan...

  10. Solutions to Test 1 Review Problems 1. Here are two sound waves. Identify which is periodic. For the periodic wave, sketch a

    E-Print Network [OSTI]

    Hall, Rachel W.

    Solutions to Test 1 Review Problems 1. Here are two sound waves. Identify which is periodic. Sound wave = You hear a sound that fades in, then gets quiet, then gets louder, and inally fades out. The width of the sound wave corresponds to intensity. (b) Suppose a 1000 Hz tone and a 1008 Hz tone

  11. 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.

  12. Tensile testing of materials at high temperatures above 1700?°C with in situ synchrotron X-ray micro-tomography

    SciTech Connect (OSTI)

    Haboub, Abdel; Nasiatka, James R.; MacDowell, Alastair A. [Lawrence Berkeley National Laboratory, Berkeley, California 94720 (United States); Bale, Hrishikesh A. [Department of Materials Science and Engineering, University of California, Berkeley, California 94720 (United States); Cox, Brian N.; Marshall, David B. [Teledyne Scientific Company, Thousand Oaks, California 91360 (United States); Ritchie, Robert O., E-mail: roritchie@lbl.gov [Lawrence Berkeley National Laboratory, Berkeley, California 94720 (United States); Department of Materials Science and Engineering, University of California, Berkeley, California 94720 (United States)

    2014-08-15T23:59:59.000Z

    A compact ultrahigh temperature tensile testing instrument has been designed and fabricated for in situ x-ray micro-tomography using synchrotron radiation at the Advanced Light Source, Lawrence Berkeley National Laboratory. It allows for real time x-ray micro-tomographic imaging of test materials under mechanical load at temperatures up to 2300?°C in controlled environments (vacuum or controlled gas flow). Sample heating is by six infrared halogen lamps with ellipsoidal reflectors arranged in a confocal configuration, which generates an approximately spherical zone of high heat flux approximately 5 mm in diameter. Samples are held between grips connected to a motorized stage that loads the samples in tension or compression with forces up to 2.2 kN. The heating chamber and loading system are water-cooled for thermal stability. The entire instrument is mounted on a rotation stage that allows stepwise recording of radiographs over an angular range of 180°. A thin circumferential (360°) aluminum window in the wall of the heating chamber allows the x-rays to pass through the chamber and the sample over the full angular range. The performance of the instrument has been demonstrated by characterizing the evolution of 3D damage mechanisms in ceramic composite materials under tensile loading at 1750?°C.

  13. Apparatus and method for fatigue testing of a material specimen in a high-pressure fluid environment

    DOE Patents [OSTI]

    Wang, Jy-An; Feng, Zhili; Anovitz, Lawrence M; Liu, Kenneth C

    2013-06-04T23:59:59.000Z

    The invention provides fatigue testing of a material specimen while the specimen is disposed in a high pressure fluid environment. A specimen is placed between receivers in an end cap of a vessel and a piston that is moveable within the vessel. Pressurized fluid is provided to compression and tension chambers defined between the piston and the vessel. When the pressure in the compression chamber is greater than the pressure in the tension chamber, the specimen is subjected to a compression force. When the pressure in the tension chamber is greater than the pressure in the compression chamber, the specimen is subjected to a tension force. While the specimen is subjected to either force, it is also surrounded by the pressurized fluid in the tension chamber. In some examples, the specimen is surrounded by hydrogen.

  14. Film Deposition, Cryogenic RF Testing and Materials Analysis of a Nb/Cu Single Cell SRF Cavity

    SciTech Connect (OSTI)

    Zhao, Xin [JLAB; Geng, Rongli [JLAB; Palczerski, Ari [JLAB; Li, Yongming [Peking

    2013-09-01T23:59:59.000Z

    In this study, we present preliminary results on using a cathodic-arc-discharge Nb plasma ion source to establish a Nb film-coated single-cell Cu cavity for SRF research. The polycrystalline Cu cavity was fabricated and mirror-surface-finished by a centrifugal barrel polishing (CBP) process at Jefferson Lab. Special pre-coating processes were conducted, in order to create a template-layer for follow-on Nb grain thickening. A sequence of cryogenic RF testing demonstrated that the Nb film does show superconductivity. But the quality factor of this Nb/Cu cavity is low as a result of high residual surface resistance. We are conducting a thorough materials characterization to explore if some microstructural defects or hydrogen impurities, led to such a low quality factor.

  15. Cultural Resource Investigations for the Resumption of Transient Testing of Nuclear Fuels and Material at the Idaho National Laboratory

    SciTech Connect (OSTI)

    Brenda R. Pace; Julie B. Williams

    2013-11-01T23:59:59.000Z

    The U. S. Department of Energy (DOE) has a need to test nuclear fuels under conditions that subject them to short bursts of intense, high-power radiation called ‘transient testing’ in order to gain important information necessary for licensing new nuclear fuels for use in U.S. nuclear power plants, for developing information to help improve current nuclear power plant performance and sustainability, for improving the affordability of new generation reactors, for developing recyclable nuclear fuels, and for developing fuels that inhibit any repurposing into nuclear weapons. To meet this mission need, DOE is considering alternatives for re-use and modification of existing nuclear reactor facilities to support a renewed transient testing program. One alternative under consideration involves restarting the Transient Reactor Test (TREAT) reactor located at the Materials and Fuels Complex (MFC) on the Idaho National Laboratory (INL) site in southeastern Idaho. This report summarizes cultural resource investigations conducted by the INL Cultural Resource Management Office in 2013 to support environmental review of activities associated with restarting the TREAT reactor at the INL. These investigations were completed in order to identify and assess the significance of cultural resources within areas of potential effect associated with the proposed action and determine if the TREAT alternative would affect significant cultural resources or historic properties that are eligible for nomination to the National Register of Historic Places. No archaeological resources were identified in the direct area of potential effects for the project, but four of the buildings proposed for modifications are evaluated as historic properties, potentially eligible for nomination to the National Register of Historic Places. This includes the TREAT reactor (building #), control building (building #), guardhouse (building #), and warehouse (building #). The proposed re-use of these historic properties is consistent with original missions related to nuclear reactor testing and is expected to result in no adverse effects to their historic significance. Cultural resource investigations also involved communication with representatives from the Shoshone-Bannock Tribes to characterize cultural resources of potential tribal concern. This report provides a summary of the cultural resources inventoried and assessed within the defined areas of potential effect for the resumption of transient testing at the INL. Based on these analyses, proposed activities would have no adverse effects on historic properties within the APEs that have been defined. Other archaeological resources and cultural resources of potential concern to the Shoshone-Bannock Tribes and others that are located near the APEs are also discussed with regard to potential indirect impacts. The report concludes with general recommendations for measures to reduce impacts to all identified resources.

  16. Development of a Supercritical Carbon Dioxide Brayton Cycle: Improving VHTR Efficiency and Testing Material Compatibility - Final Report

    SciTech Connect (OSTI)

    Chang H. Oh

    2006-06-01T23:59:59.000Z

    Generation IV reactors will need to be intrinsically safe, having a proliferation-resistant fuel cycle and several advantages relative to existing light water reactor (LWR). They, however, must still overcome certain technical issues and the cost barrier before it can be built in the U.S. The establishment of a nuclear power cost goal of 3.3 cents/kWh is desirable in order to compete with fossil combined-cycle, gas turbine power generation. This goal requires approximately a 30 percent reduction in power cost for stateof-the-art nuclear plants. It has been demonstrated that this large cost differential can be overcome only by technology improvements that lead to a combination of better efficiency and more compatible reactor materials. The objectives of this research are (1) to develop a supercritical carbon dioxide Brayton cycle in the secondary power conversion side that can be applied to the Very-High-Temperature Gas-Cooled Reactor (VHTR), (2) to improve the plant net efficiency by using the carbon dioxide Brayton cycle, and (3) to test material compatibility at high temperatures and pressures. The reduced volumetric flow rate of carbon dioxide due to higher density compared to helium will reduce compression work, which eventually increase plant net efficiency.

  17. 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.

  18. 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.

  19. LANSCE | Materials Test Station

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr May JunDatastreamsmmcrcalgovInstrumentsruc DocumentationP-SeriesFlickrinformationPostdocs &JeffIntensitySurface Los Alamos Neutron

  20. Gas storage materials, including hydrogen storage materials

    DOE Patents [OSTI]

    Mohtadi, Rana F; Wicks, George G; Heung, Leung K; Nakamura, Kenji

    2014-11-25T23:59:59.000Z

    A material for the storage and release of gases comprises a plurality of hollow elements, each hollow element comprising a porous wall enclosing an interior cavity, the interior cavity including structures of a solid-state storage material. In particular examples, the storage material is a hydrogen storage material, such as a solid state hydride. An improved method for forming such materials includes the solution diffusion of a storage material solution through a porous wall of a hollow element into an interior cavity.

  1. Gas storage materials, including hydrogen storage materials

    DOE Patents [OSTI]

    Mohtadi, Rana F; Wicks, George G; Heung, Leung K; Nakamura, Kenji

    2013-02-19T23:59:59.000Z

    A material for the storage and release of gases comprises a plurality of hollow elements, each hollow element comprising a porous wall enclosing an interior cavity, the interior cavity including structures of a solid-state storage material. In particular examples, the storage material is a hydrogen storage material such as a solid state hydride. An improved method for forming such materials includes the solution diffusion of a storage material solution through a porous wall of a hollow element into an interior cavity.

  2. Corrective Action Plan for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2007-10-01T23:59:59.000Z

    Corrective Action Unit (CAU) 166, Storage Yards and Contaminated Materials, is listed in the Federal Facility Agreement and Consent Order (FFACO) of 1996 (FFACO, 1996). CAU 166 consists of seven Corrective Action Sites (CASs) located in Areas 2, 3, 5, and 18 of the Nevada Test Site (NTS), which is located approximately 65 miles northwest of Las Vegas, Nevada (Figure 1). CAU 166 consists of the following CASs: (1) CAS 02-42-01, Cond. Release Storage Yd - North; (2) CAS 02-42-02, Cond. Release Storage Yd - South; (3) CAS 02-99-10, D-38 Storage Area; (4) CAS 03-42-01, Conditional Release Storage Yard; (5) CAS 05-19-02, Contaminated Soil and Drum; (6) CAS 18-01-01, Aboveground Storage Tank; and (7) CAS 18-99-03, Wax Piles/Oil Stain. Details of the site history and site characterization results for CAU 166 are provided in the approved Corrective Action Investigation Plan (CAIP) (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2006) and in the approved Corrective Action Decision Document (CADD) (NNSA/NSO, 2007).

  3. Testing thermocline filler materials and molten-salt heat transfer fluids for thermal energy storage systems used in parabolic trough solar power plants.

    SciTech Connect (OSTI)

    Kelly, Michael James; Hlava, Paul Frank; Brosseau, Douglas A.

    2004-07-01T23:59:59.000Z

    Parabolic trough power systems that utilize concentrated solar energy to generate electricity are a proven technology. Industry and laboratory research efforts are now focusing on integration of thermal energy storage as a viable means to enhance dispatchability of concentrated solar energy. One option to significantly reduce costs is to use thermocline storage systems, low-cost filler materials as the primary thermal storage medium, and molten nitrate salts as the direct heat transfer fluid. Prior thermocline evaluations and thermal cycling tests at the Sandia National Laboratories' National Solar Thermal Test Facility identified quartzite rock and silica sand as potential filler materials. An expanded series of isothermal and thermal cycling experiments were planned and implemented to extend those studies in order to demonstrate the durability of these filler materials in molten nitrate salts over a range of operating temperatures for extended timeframes. Upon test completion, careful analyses of filler material samples, as well as the molten salt, were conducted to assess long-term durability and degradation mechanisms in these test conditions. Analysis results demonstrate that the quartzite rock and silica sand appear able to withstand the molten salt environment quite well. No significant deterioration that would impact the performance or operability of a thermocline thermal energy storage system was evident. Therefore, additional studies of the thermocline concept can continue armed with confidence that appropriate filler materials have been identified for the intended application.

  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. 1981). Their basic solution is to find a suitable backfilling material to minimize the contact resistance and to maintain high ground thermal conductivity around the cable even under very

    E-Print Network [OSTI]

    Oak Ridge National Laboratory

    resistance and to maintain high ground thermal conductivity around the cable even under very dry ground#12;1981). Their basic solution is to find a suitable backfilling material to minimize the contact thermal conductivity for clay backfilling, measured 1/2 inch and 6 inches (1.3 and 15 cm) away from

  6. materialsELSEVIER Journal of Nuclear Materials 233-237 (1996) 1547-1551 Deuteron beam interaction with lithium jet in a neutron source test

    E-Print Network [OSTI]

    Harilal, S. S.

    -speed flowing jet of liquid Li, as shown in Fig. 1. This system must also be capable of operating under the high tank where complete mixing occurs with the large volume of Li in the tank. Some of the concerns beam interaction with lithium jet in a neutron source test facility I A. Hassanein Argonne National

  7. US/French joint research program regarding the behavior of polymer base materials subjected to beta radiation: Volume 2, Phase-2a screening tests: (Final report)

    SciTech Connect (OSTI)

    Buckalew, W.H.; Wyant, F.J.; Chenion, J.; Carlin, F.; Gaussens, G.; Le Tutour, P.; Le Meur, M.

    1987-09-01T23:59:59.000Z

    As part of the ongoing joint NRC/CEA cooperative test program to investigate the relative effectiveness of beta and gamma irradiation to produce damage in polymer base materials, ethylene propylene rubber (EPR) specimens, in slab geometry, were exposed to Cobalt-60 gamma rays and accelerator produced electron beams. Specimens were irradiated and evaluated at research facilities in the US (Sandia National Laboratories) and France (Compagnie ORIS Industrie). These tests included several electron beam energies, sample thicknesses, exposure doses, and dose rates. Based on changes in the tensile properties, of the test specimens, results of these studies suggest that material damage resulting from electron and gamma irradiations can be correlated on the basis of absorbed radiation dose.

  8. An Assessment of the Current Day Impact of Various Materials Associated with the U.S. Nuclear Test Program in the Marshall Island

    SciTech Connect (OSTI)

    Robison, W L; Noshkin, V E; Hamilton, T F; Conrado, C L; Bogen, K T

    2001-05-01T23:59:59.000Z

    Different stable elements, and some natural and man-made radionuclides, were used as tracers or associated in other ways with nuclear devices that were detonated at Bikini and Enewetak Atolls as part of the U.S. nuclear testing program from 1946 through 1958. The question has been raised whether any of these materials dispersed by the explosions could be of sufficient concentration in either the marine environment or on the coral islands to be of a health concern to people living, or planning to live, on the atolls. This report addresses that concern. An inventory of the materials involved during the test period was prepared and provided to us by the Office of Defense Programs (DP) of the United States Department of Energy (DOE). The materials that the DOE and the Republic of the Marshall Islands (RMI) ask to be evaluated are--sulfur, arsenic, yttrium, tantalum, gold, rhodium, indium, tungsten, thallium, thorium-230,232 ({sup 230,232}Th), uranium-233,238 ({sup 233,238}U), polonium-210 ({sup 210}Po), curium-232 ({sup 232}Cu), and americium-241 ({sup 241}Am). The stable elements were used primarily as tracers for determining neutron energy and flux, and for other diagnostic purposes in the larger yield, multistage devices. It is reasonable to assume that these materials would be distributed in a similar manner as the fission products subsequent to detonation. A large inventory of fission product and uranium data was available for assessment. Detailed calculations show only a very small fraction of the fission products produced during the entire test series remain at the test site atolls. Consequently, based on the information provided, we conclude that the concentration of these materials in the atoll environment pose no adverse health effects to humans.

  9. Summary of Blast Shield and Material Testing for Development of Solid Debris Collection at the National Ignition Facility (NIF)

    SciTech Connect (OSTI)

    Shaughnessy, D A; Gostic, J M; Moody, K J; Grant, P M; Lewis, L A; Hutcheon, I D

    2011-11-21T23:59:59.000Z

    The ability to collect solid debris from the target chamber following a NIF shot has application for both capsule diagnostics, particularly for fuel-ablator mix, and measuring cross sections relevant to the Stockpile Stewardship program and nuclear astrophysics. Simulations have shown that doping the capsule with up to 10{sup 15} atoms of an impurity not otherwise found in the capsule does not affect its performance. The dopant is an element that will undergo nuclear activations during the NIF implosion, forming radioactive species that can be collected and measured after extraction from the target chamber. For diagnostics, deuteron or alpha induced reactions can be used to probe the fuel-ablator mix. For measuring neutron cross sections, the dopant should be something that is sensitive to the 14 MeV neutrons produced through the fusion of deuterium and tritium. Developing the collector is a challenge due to the extreme environment of the NIF chamber. The collector surface is exposed to a large photon flux from x-rays and unconverted laser light before it is exposed to a debris wind that is formed from vaporized material from the target chamber center. The photons will ablate the collector surface to some extent, possibly impeding the debris from reaching the collector and sticking. In addition, the collector itself must be mechanically strong enough to withstand the large amount of energy it will be exposed to, and it should be something that will be easy to count and chemically process. In order to select the best material for the collector, a variety of different metals have been tested in the NIF chamber. They were exposed to high-energy laser shots in order to evaluate their postshot surface characterization, morphology, degree of melt, and their ability to retain debris from the chamber center. The first set of samples consisted of 1 mm thick pieces of aluminum that had been fielded in the chamber as blast shields protecting the neutron activation diagnostic. Ten of these pieces were fielded at the equator and one was fielded on the pole. The shields were analyzed using a combination of scanning electron microscopy (SEM), energy dispersive spectroscopy (EDS), x-ray fluorescence (XRF), neutron activation analysis (NAA) and chemical leaching followed by mass spectrometry. On each shield, gold debris originating from the gold hohlraum was observed, as well as large quantities of debris that were present in the center of the target chamber at the time of the shot (i.e., stainless steel, indium, copper, etc.) Debris was visible in the SEM as large blobs or splats of material that had encountered the surface of the aluminum and stuck. The aluminum itself had obviously melted and condensed, and some of the large debris splats arrived after the surface had already hardened. Melt depth was determined by cross sectioning the pieces and measuring the melted surface layers via SEM. After the SEM analysis was completed, the pieces were sent for NAA at the USGS reactor and were analyzed by U. Greife at the Colorado School of Mines. The NAA showed that the majority of gold mass present on the shields was not in the form of large blobs and splats, but was present as small particulates that had most likely formed as condensed vapor. Further analysis showed that the gold was entrained in the melted aluminum surface layers and did not extend down into the bulk of the aluminum. Once the gold mass was accounted for from the NAA, it was determined that the aluminum fielded at the equator was collecting a fraction of the total gold hohlraum mass equivalent to 120% {+-} 10% of the solid angle subtended by the shield. The attached presentation has more information on the results of the aluminum blast shield analysis. In addition to the information given in the presentation, the surfaces of the shields have been chemically leached and submitted for mass spectrometric analysis. The results from that analysis are expected to arrive after the due date of this report and will be written up at a later time. Based on the results of the aluminum b

  10. High yield production of inorganic graphene-like materials (MoS?, WS?, BN) through liquid exfoliation testing key parameters

    E-Print Network [OSTI]

    Pu, Fei, S.B. Massachusetts Institute of Technology

    2012-01-01T23:59:59.000Z

    Inorganic graphene-like materials such as molybdenum disulfide (MoS?), tungsten sulfide (WS?), and boron nitride (BN) are known to have electronic properties. When exfoliated into layers and casted onto carbon nanofilms, ...

  11. FEASIBILITY STUDY FOR THE DEVELOPMENT OF A TEST BED PROGRAM FOR NOVEL DETECTORS AND DETECTOR MATERIALS AT SRS H-CANYON SEPARATIONS FACILITY

    SciTech Connect (OSTI)

    Sexton, L.; Mendez-Torres, A.; Hanks, D.

    2011-06-07T23:59:59.000Z

    Researchers at the Savannah River National Laboratory (SRNL) have proposed that a test bed for advanced detectors be established at the H-Canyon separations facility located on the DOE Savannah River Site. The purpose of the proposed test bed will be to demonstrate the capabilities of emerging technologies for national and international safeguards applications in an operational environment, and to assess the ability of proven technologies to fill any existing gaps. The need for such a test bed has been expressed in the National Nuclear Security Administration's (NNSA) Next Generation Safeguards Initiative (NGSI) program plan and would serve as a means to facilitate transfer of safeguards technologies from the laboratory to an operational environment. New detectors and detector materials open the possibility of operating in a more efficient and cost effective manner, thereby strengthening national and international safeguards objectives. In particular, such detectors could serve the DOE and IAEA in improving timeliness of detection, minimizing uncertainty and improving confidence in results. SRNL's concept for the H Canyon test bed program would eventually open the facility to other DOE National Laboratories and establish a program for testing national and international safeguards related equipment. The initial phase of the test bed program is to conduct a comprehensive feasibility study to determine the benefits and challenges associated with establishing such a test bed. The feasibility study will address issues related to the planning, execution, and operation of the test bed program. Results from the feasibility study will be summarized and discussed in this paper.

  12. 100-NR-2 Apatite Treatability Test: High-Concentration Calcium-Citrate-Phosphate Solution Injection for In Situ Strontium-90 Immobilization

    SciTech Connect (OSTI)

    Vermeul, Vincent R.; Fritz, Brad G.; Fruchter, Jonathan S.; Szecsody, James E.; Williams, Mark D.

    2010-09-01T23:59:59.000Z

    Following an evaluation of potential strontium-90 (90Sr) treatment technologies and their applicability under 100-NR-2 hydrogeologic conditions, the U.S. Department of Energy (DOE), Fluor Hanford, Inc. (now CH2M Hill Plateau Remediation Company [CHPRC]), Pacific Northwest National Laboratory, and the Washington State Department of Ecology agreed that the long-term strategy for groundwater remediation at the 100-N Area should include apatite as the primary treatment technology. This agreement was based on results from an evaluation of remedial alternatives that identified the apatite permeable reactive barrier (PRB) technology as the approach showing the greatest promise for reducing 90Sr flux to the Columbia River at a reasonable cost. This letter report documents work completed to date on development of a high-concentration amendment formulation and initial field-scale testing of this amendment solution.

  13. Interim Report: 100-NR-2 Apatite Treatability Test: Low Concentration Calcium Citrate-Phosphate Solution Injection for In Situ Strontium-90 Immobilization

    SciTech Connect (OSTI)

    Williams, Mark D.; Fritz, Brad G.; Mendoza, Donaldo P.; Rockhold, Mark L.; Thorne, Paul D.; Xie, YuLong; Bjornstad, Bruce N.; Mackley, Rob D.; Newcomer, Darrell R.; Szecsody, James E.; Vermeul, Vincent R.

    2008-07-11T23:59:59.000Z

    Following an evaluation of potential Sr-90 treatment technologies and their applicability under 100-NR-2 hydrogeologic conditions, U.S. Department of Energy, Fluor Hanford, Inc., Pacific Northwest National Laboratory, and the Washington Department of Ecology agreed that the long-term strategy for groundwater remediation at 100-N Area will include apatite sequestration as the primary treatment, followed by a secondary treatment if necessary (most likely phytoremediation). Since then, the agencies have worked together to agree on which apatite sequestration technology has the greatest chance of reducing Sr-90 flux to the river at a reasonable cost. In July 2005, aqueous injection, (i.e., the introduction of apatite-forming chemicals into the subsurface) was endorsed as the interim remedy and selected for field testing. Studies are in progress to assess the efficacy of in situ apatite formation by aqueous solution injection to address both the vadose zone and the shallow aquifer along the 300 ft of shoreline where Sr-90 concentrations are highest. This report describes the field testing of the shallow aquifer treatment.

  14. Vehicle Technologies Office Merit Review 2014: Post-Test Analysis of Lithium-Ion Battery Materials at Argonne National Laboratory

    Broader source: Energy.gov [DOE]

    Presentation given by Argonne National Laboratory at 2014 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Office Annual Merit Review and Peer Evaluation Meeting about post-test...

  15. The evaluation of micro-surfacing mixture design procedures and the effects of material variation on the test responses

    E-Print Network [OSTI]

    Andrews, Edward Mensah

    1994-01-01T23:59:59.000Z

    sand paper. c. 100 grit silicon carbide 'Carborundum' brand sand paper. d. Load cell to periodically check the cohesion meter pressure. 12 Sample Preparation and Testing Procedure Aggregate falling within the Texas Department of Transportation (Tx...

  16. Department of Mechanical Engineering/Material Science and Engineering Spring 2013 Project Name Development of Test Rig to

    E-Print Network [OSTI]

    Demirel, Melik C.

    PENNSTATE Department of Mechanical Engineering/Material Science and Engineering Spring 2013 Project up. The hardest part of this project was learning SolidWorks, how to incorporate mechanical design into an actual project, general machining (boring, reaming, broaching), advanced machining (CNC), and data

  17. CHARACTERIZATION OF SIALON-TYPE MATERIALS

    E-Print Network [OSTI]

    Spencer, P.N.

    2010-01-01T23:59:59.000Z

    testing of ceramic materials. crucihle Thermal Shock Tests.and thermal shock. Among the various ceramic materials being

  18. Predictability of estimated maximal aerobic capacities for manual material handlers using submaximal box lifting and bench stepping tests

    E-Print Network [OSTI]

    Cortner, James D.

    1996-01-01T23:59:59.000Z

    and not supporting an Oxylog unit that weighs 2.6 kg (5.8 lb). The mean S.D. manual material handling V 02 max of 2.94 ?0.3 8 L02 /min was not significantly greater (p = 0.0798) than the bench stepping while supporting the Oxylog unit V 02 m. (2.94 ?0.44 L02/min...

  19. Standard test method for static leaching of monolithic waste forms for disposal of radioactive waste

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2010-01-01T23:59:59.000Z

    1.1 This test method provides a measure of the chemical durability of a simulated or radioactive monolithic waste form, such as a glass, ceramic, cement (grout), or cermet, in a test solution at temperatures radioactive waste forms in various leachants under the specific conditions of the test based on analysis of the test solution. Data from this test are used to calculate normalized elemental mass loss values from specimens exposed to aqueous solutions at temperatures <100°C. 1.3 The test is conducted under static conditions in a constant solution volume and at a constant temperature. The reactivity of the test specimen is determined from the amounts of components released and accumulated in the solution over the test duration. A wide range of test conditions can be used to study material behavior, includin...

  20. Preliminary evaluation of the use of the greater confinement disposal concept for the disposal of Fernald 11e(2) byproduct material at the Nevada Test Site

    SciTech Connect (OSTI)

    Cochran, J.R.; Brown, T.J.; Stockman, H.W.; Gallegos, D.P.; Conrad, S.H. [Sandia National Labs., Albuquerque, NM (United States)] [Sandia National Labs., Albuquerque, NM (United States); Price, L.L. [Sandia National Labs., Albuquerque, NM (United States)] [Sandia National Labs., Albuquerque, NM (United States); [Beta Inc. (United States)

    1997-09-01T23:59:59.000Z

    This report documents a preliminary evaluation of the ability of the greater confinement disposal boreholes at the Nevada Test Site to provide long-term isolation of radionuclides from the disposal of vitrified byproduct material. The byproduct material is essentially concentrated residue from processing uranium ore that contains a complex mixture of radionuclides, many of which are long-lived and present in concentrations greater than 100,000 picoCuries per gram. This material has been stored in three silos at the fernald Environmental Management Project since the early 1950s and will be vitrified into 6,000 yd{sup 3} (4,580 m{sup 3}) of glass gems prior to disposal. This report documents Sandia National Laboratories` preliminary evaluation for disposal of the byproduct material and includes: the selection of quantitative performance objectives; a conceptual model of the disposal system and the waste; results of the modeling; identified issues, and activities necessary to complete a full performance assessment.

  1. Development and experimental validation of a calculation scheme for nuclear heating evaluation in the core of the OSIRIS material testing reactor

    SciTech Connect (OSTI)

    Malouch, F. [Saclay Center CEA, DEN/DANS/DM2S/SERMA, F-91191 Gif-sur-Yvette Cedex (France)

    2011-07-01T23:59:59.000Z

    The control of the temperature in material samples irradiated in a material testing reactor requires the knowledge of the nuclear heating caused by the energy deposition by neutrons and photons interacting in the irradiation device structures. Thus, a neutron-photonic three-dimensional calculation scheme has been developed to evaluate the nuclear heating in experimental devices irradiated in the core of the OSIRIS MTR reactor (CEA/Saclay Center). The aim is to obtain a predictive tool for the nuclear heating estimation in irradiation devices. This calculation scheme is mainly based on the TRIPOLI-4 three-dimensional continuous-energy Monte Carlo transport code, developed by CEA (Saclay Center). An experimental validation has been carried out on the basis of nuclear heating measurements performed in the OSIRIS core. After an overview of the experimental devices irradiated in the OSIRIS reactor, we present the calculation scheme and the first results of the experimental validation. (authors)

  2. Coaxial test fixture

    DOE Patents [OSTI]

    Praeg, W.F.

    1984-03-30T23:59:59.000Z

    This invention pertains to arrangements for performing electrical tests on contact material samples, and in particular for testing contact material test samples in an evacuated environment under high current loads. Frequently, it is desirable in developing high-current separable contact material, to have at least a preliminary analysis of selected candidate conductor materials. Testing of material samples will hopefully identify materials unsuitable for high current electrical contact without requiring incorporation of the materials into a completed and oftentimes complex structure.

  3. METC/3M Cooperative Agreement CRADA 94-024 high temperature high pressure filter materials exposure test program. Volume 1, Final report

    SciTech Connect (OSTI)

    NONE

    1995-06-01T23:59:59.000Z

    In conjunction with shakedown, operation, and desulfurization testing at the Morgantown Energy Technology Center (METC) 10 in. Fluid Bed Gasification and Cleanup facility, a series of tests was completed in cooperation with the Minnesota Mining and Manufacturing Company (3M). This cooperative research and development agreement (CRADA) between METC and 3M was to evaluate exposure of 3M SICONEX{trademark} fiber-reinforced ceramic and NEXTEL{trademark} 312 and 550 ceramic fabric materials to a gasifying environment at high temperatures (1000--1100{degree}F) and high pressure (300 psia). Minnesota Mining and Manufacturing Company (3M) provided two 60 mm I.D. {times} 0.5 m SICONEX{trademark} spools and one each of the NEXTEL{trademark} 312 and 550 ceramic fabrics for exposure to coal gas from the METC gasifier. METC installed the materials in a vessel existing in the METC Cleanup Facility and provided process data in exchange for ceramic filter and ash/char characterization. Details of the CRADA are found in CRADA 94-024. This report contains METC`s contribution to CRADA 94-024. Four gasifier runs were conducted over a five month period to accumulate 483 hours of operation. During this time, 2 LayCer{trademark} 70/3 filters were used for filtering the coal gas while the SICONEX{trademark} and NEXTEL{trademark} were exposed along side of the filters. During one 89 hour test, one Laycer{trademark} 70/3 candle was installed with a 3M ceramic composite filter. The face velocity through the candles was maintained nominally at 2.5 ft/min throughout the testing.

  4. Pilot-scale treatability testing -- Recycle, reuse, and disposal of materials from decontamination and decommissioning activities: Soda blasting demonstration

    SciTech Connect (OSTI)

    NONE

    1995-08-01T23:59:59.000Z

    The US Department of Energy (DOE) is in the process of defining the nature and magnitude of decontamination and decommissioning (D and D) obligations at its sites. With disposal costs rising and available storage facilities decreasing, DOE is exploring and implementing new waste minimizing D and D techniques. Technology demonstrations are being conducted by LMES at a DOE gaseous diffusion processing plant, the K-25 Site, in Oak Ridge, Tennessee. The gaseous diffusion process employed at Oak Ridge separated uranium-235 from uranium ore for use in atomic weapons and commercial reactors. These activities contaminated concrete and other surfaces within the plant with uranium, technetium, and other constituents. The objective of current K-25 D and D research is to make available cost-effective and energy-efficient techniques to advance remediation and waste management methods at the K-25 Site and other DOE sites. To support this objective, O`Brien and Gere tested a decontamination system on K-25 Site concrete and steel surfaces contaminated with radioactive and hazardous waste. A scouring system has been developed that removes fixed hazardous and radioactive surface contamination and minimizes residual waste. This system utilizes an abrasive sodium bicarbonate medium that is projected at contaminated surfaces. It mechanically removes surface contamination while leaving the surface intact. Blasting residuals are captured and dissolved in water and treated using physical/chemical processes. Pilot-scale testing of this soda blasting system and bench and pilot-scale treatment of the generated residuals were conducted from December 1993 to September 1994.

  5. Fissile solution measurement apparatus

    DOE Patents [OSTI]

    Crane, T.W.; Collinsworth, P.R.

    1984-06-11T23:59:59.000Z

    An apparatus for determining the content of a fissile material within a solution by detecting delayed fission neutrons emitted by the fissile material after it is temporarily irradiated by a neutron source. The apparatus comprises a container holding the solution and having a portion defining a neutron source cavity centrally disposed within the container. The neutron source cavity temporarily receives the neutron source. The container has portions defining a plurality of neutron detector ports that form an annular pattern and surround the neutron source cavity. A plurality of neutron detectors count delayed fission neutrons emitted by the fissile material. Each neutron detector is located in a separate one of the neutron detector ports.

  6. Mayne, P.W., Coop, M.R., Springman, S., Huang, A-B., and Zornberg, J. (2009). State-of-the-Art Paper (SOA-1): GeoMaterial Behavior and Testing. Proc. 17th Intl. Conf. Soil Mechanics & Geotechnical

    E-Print Network [OSTI]

    Mayne, Paul W.

    Mayne, P.W., Coop, M.R., Springman, S., Huang, A-B., and Zornberg, J. (2009). State-of-the-Art Paper (SOA-1): GeoMaterial Behavior and Testing. Proc. 17th Intl. Conf. Soil Mechanics & Geotechnical

  7. FY-05 First Quarter Report on Development of a Supercritical Carbon Dioxide Brayton Cycle: Improving PBR Efficiency and Testing Material Compatibility

    SciTech Connect (OSTI)

    Chang Oh

    2005-01-01T23:59:59.000Z

    The objective of this research is to improve a helium Brayton cycle and to develop a supercritical carbon dioxide Brayton cycle for the Pebble Bed Reactor (PBR) that can also be applied to the Fast Gas-Cooled Reactor (FGR) and the Very-High-Temperature Gas- Cooled Reactor (VHTR). The proposed supercritical carbon dioxide Brayton cycle will be used to improve the PBR, FGR, and VHTR net plant efficiency. Another objective of this research is to test materials to be used in the power conversion side at supercritical carbon dioxide conditions. Generally, the optimized Brayton cycle and balance of plant (BOP) to be developed from this study can be applied to Generation-IV reactor concepts. Particularly, we are interested in VHTR because it has a good chance of being built in the near future.

  8. Corrective Action Investigation Plan for Corrective Action Unit 529: Area 25 Contaminated Materials, Nevada Test Site, Nevada, Rev. 0, Including Record of Technical Change No. 1

    SciTech Connect (OSTI)

    U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2003-02-26T23:59:59.000Z

    This Corrective Action Investigation Plan contains the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 529, Area 25 Contaminated Materials, Nevada Test Site (NTS), Nevada, under the Federal Facility Agreement and Consent Order. CAU 529 consists of one Corrective Action Site (25-23-17). For the purpose of this investigation, the Corrective Action Site has been divided into nine parcels based on the separate and distinct releases. A conceptual site model was developed for each parcel to address the translocation of contaminants from each release. The results of this investigation will be used to support a defensible evaluation of corrective action alternatives in the corrective action decision document.

  9. The in-situ decontamination of sand and gravel aquifers by chemically enhanced solubilization of multiple-compound DNAPLs with surfactant solutions: Phase 1 -- Laboratory and pilot field-scale testing and Phase 2 -- Solubilization test and partitioning and interwell tracer tests. Final report

    SciTech Connect (OSTI)

    NONE

    1997-10-24T23:59:59.000Z

    Laboratory, numerical simulation, and field studies have been conducted to assess the potential use of micellar-surfactant solutions to solubilize chlorinated solvents contaminating sand and gravel aquifers. Ninety-nine surfactants were screened for their ability to solubilize trichloroethene (TCE), perchloroethylene (PCE), and carbon tetrachloride (CTET). The field test was conducted in the alluvial aquifer which is located 20 to 30 meters beneath a vapor degreasing operation at Paducah Gaseous Diffusion Plant. This aquifer has become contaminated with TCE due to leakage of perhaps 40,000 liters of TCE, which has generated a plume of dissolved TCE extending throughout an area of approximately 3 km{sup 2} in the aquifer. Most of the TCE is believed to be present in the overlying lacustrine deposits and in the aquifer itself as a dense, non-aqueous phase liquid, or DNAPL. The objective of the field test was to assess the efficacy of the surfactant for in situ TCE solubilization. Although the test demonstrated that sorbitan monooleate was unsuitable as a solubilizer in this aquifer, the single-well test was demonstrated to be a viable method for the in situ testing of surfactants or cosolvents prior to proceeding to full-scale remediation.

  10. Preparation of CaO as OLED getter material through control of crystal growth of CaCO{sub 3} by block copolymers in aqueous solution

    SciTech Connect (OSTI)

    Park, Jae-Hyung [Department of Chemical Engineering, Hanyang University, Seoul 133-791 (Korea, Republic of); Oh, Seong-Geun [Department of Chemical Engineering, Hanyang University, Seoul 133-791 (Korea, Republic of)], E-mail: seongoh@hanyang.ac.kr

    2009-01-08T23:59:59.000Z

    As the starting materials of organic light-emitting diode (OLED) getter, calcium carbonate (CaCO{sub 3}) particles with various shapes and crystal structures have been successfully prepared with additives (L64 or PEGPG), which contain blocks of poly(ethylene oxide) (PEO) and poly(propylene oxide) (PPO). These CaCO{sub 3} particles were calcinated into highly crystalline calcium oxide (CaO) nanoparticles with high capacity of water adsorption up to 14.23 wt.%. The CaCO{sub 3} and CaO particles prepared at various conditions were characterized using the field emission scanning electron microscopy (FE-SEM), Fourier transform infrared microscopy (FT-IR), X-ray powder diffraction (XRD), and dynamic vapor sorption (DVS) method.

  11. 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.

  12. Prototype to Test WHY prototype to test

    E-Print Network [OSTI]

    Prinz, Friedrich B.

    Prototype to Test METHOD WHY prototype to test HOW to prototype to test Prototyping to test or design space. The fundamental way you test your prototypes is by letting users experience them and react to them. In creating prototypes to test with users you have the opportunity to examine your solution

  13. Porous Materials Porous Materials

    E-Print Network [OSTI]

    Berlin,Technische Universität

    1 Porous Materials x Porous Materials · Physical properties * Characteristic impedance p = p 0 e -jk xa- = vej[ ] p x - j ; Zc= p ve = c ka 0k = c 1-j #12;2 Porous Materials · Specific acoustic impedance Porous Materials · Finite thickness ­ blocked p e + -jk (x-d)a p e - jk (x-d)a d x #12

  14. Geopolymer Sealing Materials

    Broader source: Energy.gov [DOE]

    DOE Geothermal Peer Review 2010 - Presentation. Project objectives: Develop and characterize field-applicable geopolymer temporary sealing materials in the laboratory and to transfer this developed material technology to geothermal drilling service companies as collaborators for field validation tests.

  15. SLUG TESTING IN WELLS WITH FINITE-THICKNESS SKIN

    SciTech Connect (OSTI)

    Moench, A.F.; Hsieh

    1985-01-22T23:59:59.000Z

    We present an analysis of the slug test in a well surrounded by an annulus of altered material, which is treated as a skin of finite thickness. By assuming the skin has a thickness, the storage capacity of the altered material is included in the analysis. The problem is solved in the Laplace domain. The solution is found in terms of well-bore storage and the thickness, hydraulic conductivity, and specific storage of the skin. Type curves are generated by numerical inversion of the Laplace transform solution. We find that standard methods of analysis, involving a skin of infinitesimal thickness, are adequate for open-well or drill-stem tests. However, for pressurized tests the response may differ markedly from standard slug-test solutions.

  16. Casting materials

    DOE Patents [OSTI]

    Chaudhry, Anil R. (Xenia, OH); Dzugan, Robert (Cincinnati, OH); Harrington, Richard M. (Cincinnati, OH); Neece, Faurice D. (Lyndurst, OH); Singh, Nipendra P. (Pepper Pike, OH)

    2011-06-14T23:59:59.000Z

    A foam material comprises a liquid polymer and a liquid isocyanate which is mixed to make a solution that is poured, injected or otherwise deposited into a corresponding mold. A reaction from the mixture of the liquid polymer and liquid isocyanate inside the mold forms a thermally collapsible foam structure having a shape that corresponds to the inside surface configuration of the mold and a skin that is continuous and unbroken. Once the reaction is complete, the foam pattern is removed from the mold and may be used as a pattern in any number of conventional casting processes.

  17. Materials Project: A Materials Genome Approach

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

    Ceder, Gerbrand (MIT); Persson, Kristin (LBNL)

    Technological innovation - faster computers, more efficient solar cells, more compact energy storage - is often enabled by materials advances. Yet, it takes an average of 18 years to move new materials discoveries from lab to market. This is largely because materials designers operate with very little information and must painstakingly tweak new materials in the lab. Computational materials science is now powerful enough that it can predict many properties of materials before those materials are ever synthesized in the lab. By scaling materials computations over supercomputing clusters, this project has computed some properties of over 80,000 materials and screened 25,000 of these for Li-ion batteries. The computations predicted several new battery materials which were made and tested in the lab and are now being patented. By computing properties of all known materials, the Materials Project aims to remove guesswork from materials design in a variety of applications. Experimental research can be targeted to the most promising compounds from computational data sets. Researchers will be able to data-mine scientific trends in materials properties. By providing materials researchers with the information they need to design better, the Materials Project aims to accelerate innovation in materials research.[copied from http://materialsproject.org/about] You will be asked to register to be granted free, full access.

  18. Addendum to the Corrective Action Decision Document/Closure Report for Corrective Action Unit 529: Area 25 Contaminated Materials, Nevada Test Site, Nevada, Revision 1

    SciTech Connect (OSTI)

    Krauss, Mark J

    2013-10-01T23:59:59.000Z

    This document constitutes an addendum to the Corrective Action Decision Document/Closure Report for Corrective Action Unit 529: Area 25 Contaminated Materials, Nevada Test Site, Nevada as described in the document Recommendations and Justifications To Remove Use Restrictions Established under the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office Federal Facility Agreement and Consent Order dated September 2013. The Use Restriction (UR) Removal document was approved by the Nevada Division of Environmental Protection on October 16, 2013. The approval of the UR Removal document constituted approval of each of the recommended UR removals. In conformance with the UR Removal document, this addendum consists of: This page that refers the reader to the UR Removal document for additional information The cover, title, and signature pages of the UR Removal document The NDEP approval letter The corresponding section of the UR Removal document This addendum provides the documentation justifying the cancellation of the UR for CAS 25-23-17, Contaminated Wash (Parcel H). This UR was established as part of FFACO corrective actions and was based on the presence of total petroleum hydrocarbon diesel-range organics contamination at concentrations greater than the NDEP action level at the time of the initial investigation.

  19. Corrective Action Investigation Plan for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Alfred Wickline

    2007-06-01T23:59:59.000Z

    Corrective Action Unit 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, consists of seven inactive sites located in the Yucca Flat area and one inactive site in the Pahute Mesa area. The eight CAU 545 sites consist of craters used for mud disposal, surface or buried waste disposed within craters or potential crater areas, and sites where surface or buried waste was disposed. The CAU 545 sites were used to support nuclear testing conducted in the Yucca Flat area during the 1950s through the early 1990s, and in Area 20 in the mid-1970s. This Corrective Action Investigation Plan has been developed in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the Federal Facility Agreement and Consent Order, this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection for approval. Fieldwork will be conducted following approval.

  20. 3.205 Thermodynamics and Kinetics of Materials, Fall 2003

    E-Print Network [OSTI]

    Allen, Samuel M.

    Laws of thermodynamics applied to materials and materials processes. Solution theory. Equilibrium diagrams. Overview of fluid transport processes. Kinetics of processes that occur in materials, including diffusion, phase ...

  1. Electrochemical Synthesis and Characterization of Nanostructured Chalcogenide Materials

    E-Print Network [OSTI]

    Chang, Chong Hyun

    2011-01-01T23:59:59.000Z

    Superlattice Thermoelectric Materials and Devices. ScienceCarbon Nanotube Composite Materials. Langmuir 2004, 20, (nanotubes composite materials in solution. Chem. Phys. Lett.

  2. Apparatus and method for simulating material damage from a fusion reactor

    DOE Patents [OSTI]

    Smith, D.L.; Greenwood, L.R.; Loomis, B.A.

    1988-05-20T23:59:59.000Z

    This paper discusses an apparatus and method for simulating a fusion environment on a first wall or blanket structure. A material test specimen is contained in a capsule made of a material having a low hydrogen solubility and permeability. The capsule is partially filled with a lithium solution, such that the test specimen is encapsulated by the lithium. The capsule is irradiated by a fast fission neutron source.

  3. Combinatorial synthesis of ceramic materials

    DOE Patents [OSTI]

    Lauf, Robert J.; Walls, Claudia A.; Boatner, Lynn A.

    2006-11-14T23:59:59.000Z

    A combinatorial library includes a gelcast substrate defining a plurality of cavities in at least one surface thereof; and a plurality of gelcast test materials in the cavities, at least two of the test materials differing from the substrate in at least one compositional characteristic, the two test materials differing from each other in at least one compositional characteristic.

  4. Combinatorial synthesis of ceramic materials

    DOE Patents [OSTI]

    Lauf, Robert J. (Oak Ridge, TN) [Oak Ridge, TN; Walls, Claudia A. (Oak Ridge, TN) [Oak Ridge, TN; Boatner, Lynn A. (Oak Ridge, TN) [Oak Ridge, TN

    2010-02-23T23:59:59.000Z

    A combinatorial library includes a gelcast substrate defining a plurality of cavities in at least one surface thereof; and a plurality of gelcast test materials in the cavities, at least two of the test materials differing from the substrate in at least one compositional characteristic, the two test materials differing from each other in at least one compositional characteristic.

  5. Corrective Action Decision Document/Closure Report for Corrective Action Unit 545: Dumps, Waste Disposal Sites, and Buried Radioactive Materials Nevada Test Site, Nevada, Revision 0

    SciTech Connect (OSTI)

    Alfred Wickline

    2008-04-01T23:59:59.000Z

    This Corrective Action Decision Document (CADD)/Closure Report (CR) has been prepared for Corrective Action Unit (CAU) 545, Dumps, Waste Disposal Sites, and Buried Radioactive Materials, in Areas 2, 3, 9, and 20 of the Nevada Test Site, Nevada, in accordance with the Federal Facility Agreement and Consent Order that was agreed to by the State of Nevada; U.S. Department of Energy (DOE), Environmental Management; U.S. Department of Defense; and DOE, Legacy Management (1996, as amended February 2008). Corrective Action Unit 545 is comprised of the following eight Corrective Action Sites (CASs): • 02-09-01, Mud Disposal Area • 03-08-03, Mud Disposal Site • 03-17-01, Waste Consolidation Site 3B • 03-23-02, Waste Disposal Site • 03-23-05, Europium Disposal Site • 03-99-14, Radioactive Material Disposal Area • 09-23-02, U-9y Drilling Mud Disposal Crater • 20-19-01, Waste Disposal Site While all eight CASs are addressed in this CADD/CR, sufficient information was available for the following three CASs; therefore, a field investigation was not conducted at these sites: • For CAS 03-08-03, though the potential for subsidence of the craters was judged to be extremely unlikely, the data quality objective (DQO) meeting participants agreed that sufficient information existed about disposal and releases at the site and that a corrective action of close in place with a use restriction is recommended. Sampling in the craters was not considered necessary. • For CAS 03-23-02, there were no potential releases of hazardous or radioactive contaminants identified. Therefore, the Corrective Action Investigation Plan for CAU 545 concluded that: “Sufficient information exists to conclude that this CAS does not exist as originally identified. Therefore, there is no environmental concern associated with CAS 03-23-02.” This CAS is closed with no further action. • For CAS 03-23-05, existing information about the two buried sources and lead pig was considered to be sufficient, and safety concerns existed about the stability of the crater component. Therefore, a corrective action of close in place with a use restriction is recommended, and sampling at the site was not considered necessary. The purpose of this CADD/CR is to provide justification and documentation to support the recommendation for closure of CAU 545 with no further corrective action. To achieve this, corrective action investigation (CAI) activities were performed from August 20 through November 02, 2007, as set forth in the CAU 545 Corrective Action Investigation Plan. The purpose of the CAI was to fulfill the following data needs as defined during the DQO process: • Determine whether contaminants of concern (COCs) are present. • If COCs are present, determine their nature and extent. • Provide sufficient information and data to complete appropriate corrective actions. The CAU 545 dataset from the investigation results was evaluated based on the data quality indicator parameters. This evaluation demonstrated the quality and acceptability of the dataset for use in fulfilling the DQO data needs. Analytes detected during the CAI were evaluated against final action levels established in this CADD/CR. The results of the CAI identified no COCs at the five CASs investigated in CAU 545. As a best management practice, repair of the fence enclosing CAS 03-08-03 has been completed. Therefore, the DOE, National Nuclear Security Administration Nevada Site Office provides the following recommendations: • Close in place COCs at CASs 03-08-03 and 03-23-05 with use restrictions. • No further corrective action for CAU 545. • No Corrective Action Plan. • Corrective Action Unit 545 should be moved from Appendix III to Appendix IV of the Federal Facility Agreement and Consent Order. • A Notice of Completion to the DOE, National Nuclear Security Administration Nevada Site Office is requested from the Nevada Division of Environmental Protection for closure of CAU 545.

  6. Corrective Action Investigation Plan for Corrective Action Unit 166: Storage Yards and Contaminated Materials, Nevada Test Site, Nevada, Rev. No.: 0

    SciTech Connect (OSTI)

    David Strand

    2006-06-01T23:59:59.000Z

    Corrective Action Unit 166 is located in Areas 2, 3, 5, and 18 of the Nevada Test Site, which is 65 miles northwest of Las Vegas, Nevada. Corrective Action Unit (CAU) 166 is comprised of the seven Corrective Action Sites (CASs) listed below: (1) 02-42-01, Cond. Release Storage Yd - North; (2) 02-42-02, Cond. Release Storage Yd - South; (3) 02-99-10, D-38 Storage Area; (4) 03-42-01, Conditional Release Storage Yard; (5) 05-19-02, Contaminated Soil and Drum; (6) 18-01-01, Aboveground Storage Tank; and (7) 18-99-03, Wax Piles/Oil Stain. These sites are being investigated because existing information on the nature and extent of potential contamination is insufficient to evaluate and recommend corrective action alternatives. Additional information will be obtained by conducting a corrective action investigation (CAI) before evaluating corrective action alternatives and selecting the appropriate corrective action for each CAS. The results of the field investigation will support a defensible evaluation of viable corrective action alternatives that will be presented in the Corrective Action Decision Document. The sites will be investigated based on the data quality objectives (DQOs) developed on February 28, 2006, by representatives of the Nevada Division of Environmental Protection; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office; Stoller-Navarro Joint Venture; and Bechtel Nevada. The DQO process was used to identify and define the type, amount, and quality of data needed to develop and evaluate appropriate corrective actions for CAU 166. Appendix A provides a detailed discussion of the DQO methodology and the DQOs specific to each CAS. The scope of the CAI for CAU 166 includes the following activities: (1) Move surface debris and/or materials, as needed, to facilitate sampling. (2) Conduct radiological surveys. (3) Perform field screening. (4) Collect and submit environmental samples for laboratory analysis to determine if contaminants of concern are present. (5) If contaminants of concern are present, collect additional step-out samples to define the extent of the contamination. (6) Collect samples of investigation-derived waste, as needed, for waste management and minimization purposes. This Corrective Action Investigation Plan has been developed in accordance with the ''Federal Facility Agreement and Consent Order'' that was agreed to by the State of Nevada, the U.S. Department of Energy, and the U.S. Department of Defense. Under the ''Federal Facility Agreement and Consent Order'', this Corrective Action Investigation Plan will be submitted to the Nevada Division of Environmental Protection, and field work will commence following approval.

  7. Enhanced safeguards via solution monitoring

    SciTech Connect (OSTI)

    Burr, T.; Wangen, L.

    1996-09-01T23:59:59.000Z

    Solution monitoring is defined as the essentially continuous monitoring of solution level, density, and temperature in all tanks in the process that contain, or could contain, safeguards-significant quantities of nuclear material. This report describes some of the enhancements that solution monitoring could make to international safeguards. The focus is on the quantifiable benefits of solution monitoring, but qualitatively, solution monitoring can be viewed as a form of surveillance. Quantitatively, solution monitoring can in some cases improve diversion detection probability. For example, the authors show that under certain assumptions, solution monitoring can be used to reduce the standard deviation of the annual material balance, {sigma}{sub MB}, from approximately 17 kg to approximately 4 kg. Such reduction in {sigma}{sub MB} will not always be possible, as they discuss. However, in all cases, solution monitoring would provide assurance that the measurement error models are adequate so that one has confidence in his estimate of {sigma}{sub MB}. Some of the results in this report were generated using data that were simulated with prototype solution monitoring software that they are developing. An accompanying document describes that software.

  8. 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

  9. Experiment Operations Plan for a Loss-of-Coolant Accident Simulation in the National Research Universal Reactor Materials Tests 1 and 2

    SciTech Connect (OSTI)

    Russcher, G. E.; Wilson, C. L.; Marshall, R, K.; King, L. L.; Parchen, L. J.; Pilger, J. P.; Hesson, G. M.; Mohr, C. L.

    1981-09-01T23:59:59.000Z

    A loss of Coolant Accident (LOCA) simulation program is evaluating the thermal-hydraulic and mechanical effects of LOCA conditions on pressurized water reactor test fuel bundles. This experiment operation plan for the second and third experiments of the program will provide peak fuel cladding temperatures of up to 1172K (1650{degree}F) and 1061K (1450{degree}) respectively. for a long enough time to cause test fuel cladding deformation and rupture in both. Reflood coolant delay times and the reflooding rates for the experiments were selected from thermal-hydraulic data measured in the National Research Universal (NRU) reactor facilities and test train assembly during the first experiment.

  10. Material Design, Selection, and Manufacturing Methods for System Sustainment

    SciTech Connect (OSTI)

    David Sowder, Jim Lula, Curtis Marshall

    2010-02-18T23:59:59.000Z

    This paper describes a material selection and validation process proven to be successful for manufacturing high-reliability long-life product. The National Secure Manufacturing Center business unit of the Kansas City Plant (herein called KCP) designs and manufactures complex electrical and mechanical components used in extreme environments. The material manufacturing heritage is founded in the systems design to manufacturing practices that support the U.S. Department of Energy’s National Nuclear Security Administration (DOE/NNSA). Material Engineers at KCP work with the systems designers to recommend materials, develop test methods, perform analytical analysis of test data, define cradle to grave needs, present final selection and fielding. The KCP material engineers typically will maintain cost control by utilizing commercial products when possible, but have the resources and to develop and produce unique formulations as necessary. This approach is currently being used to mature technologies to manufacture materials with improved characteristics using nano-composite filler materials that will enhance system design and production. For some products the engineers plan and carry out science-based life-cycle material surveillance processes. Recent examples of the approach include refurbished manufacturing of the high voltage power supplies for cockpit displays in operational aircraft; dry film lubricant application to improve bearing life for guided munitions gyroscope gimbals, ceramic substrate design for electrical circuit manufacturing, and tailored polymeric materials for various systems. The following examples show evidence of KCP concurrent design-to-manufacturing techniques used to achieve system solutions that satisfy or exceed demanding requirements.

  11. Self limiting features of accidental criticality in a solution system

    SciTech Connect (OSTI)

    Malenfant, R.E.

    1988-01-01T23:59:59.000Z

    Experience with the SHEBA solution critical assembly during validation testing of accidental criticality alarm detectors provided several insights into the character of potential accidental excursions. Two observations were of particular interest. First, it is nearly impossible to maintain a solution system, particularly one employing low-enrichment material, in a constant state. If super-critical, the system will heat up, expand (or form bubbles), return to a sub-critical state, and shut down of its own accord without going into short period oscillations. Second, a very slow change in the system could produce a long ''pulse'' resulting in lengthy exposures, a high dose, but a low dose rate. The experiments dramatically contradicted the popular contention that accidental criticality is characterized by a blue flash, a clap of thunder, and violet expulsion of material. 5 refs., 3 figs., 4 tabs.

  12. Material Testing of Coated Alloys in a Syngas Combustion Environment Year 6 - Activity 1.13 - Development of a National Center for Hydrogen Technology

    SciTech Connect (OSTI)

    Swanson, Michael

    2011-09-01T23:59:59.000Z

    Modifications were made to the inlet of the existing Energy & Environmental Research Center (EERC) thermal oxidizer to accommodate side-by-side coupon holders for exposure testing. Two 5-day tests with over 200 hours of total exposure time were completed. The first week of testing was conducted in enriched air-blown mode, with coupon temperatures ranging from 128° to 272°F. Carbonyl sampling was conducted, but it was discovered after the fact that the methodology used was producing very low recoveries of iron and nickel carbonyl. Therefore, the data generated during this week of testing were not considered accurate. The second week of testing was conducted in oxygen-blown mode, with coupon temperatures ranging from 220° to 265°F. Two improved methods were used to measure carbonyl concentration during this week of testing. These methods produced results closer to equilibrium calculations. Since both weeks of testing mostly produced a product gas with approximately 15%–18% carbon monoxide, it was felt that actual carbonyl concentrations for Week 1 should be very similar to those measured during Week 2. The revised carbonyl sampling methodology used during the second week of testing greatly improved the recovery of iron and nickel carbonyl in the sample. Even though the sampling results obtained from the first week were inaccurate, the results from the second week can be used as an estimate for the periods during which the gasifier was operating under similar conditions and producing similar product gas compositions. Specifically, Test Periods 2 and 3 from the first week were similar to the conditions run during the second week. For a product gas containing roughly 15%–18% CO and a coupon temperature of approximately 220°–270°F, the nickel carbonyl concentration should be about 0.05–0.1 ppm and the iron carbonyl concentration should be about 0.1–0.4 ppm. After each week of testing the coupons were recovered from the coupon holder, weighed, and shipped back to Siemens for analysis.

  13. Materials characterization center workshop on compositional and microstructural analysis of nuclear waste materials. Summary report

    SciTech Connect (OSTI)

    Daniel, J.L.; Strachan, D.M.; Shade, J.W.; Thomas, M.T.

    1981-06-01T23:59:59.000Z

    The purpose of the Workshop on Compositional and Microstructural Analysis of Nuclear Waste Materials, conducted November 11 and 12, 1980, was to critically examine and evaluate the various methods currently used to study non-radioactive, simulated, nuclear waste-form performance. Workshop participants recognized that most of the Materials Characterization Center (MCC) test data for inclusion in the Nuclear Waste Materials Handbook will result from application of appropriate analytical procedures to waste-package materials or to the products of performance tests. Therefore, the analytical methods must be reliable and of known accuracy and precision, and results must be directly comparable with those from other laboratories and from other nuclear waste materials. The 41 participants representing 18 laboratories in the United States and Canada were organized into three working groups: Analysis of Liquids and Solutions, Quantitative Analysis of Solids, and Phase and Microstructure Analysis. Each group identified the analytical methods favored by their respective laboratories, discussed areas needing attention, listed standards and reference materials currently used, and recommended means of verifying interlaboratory comparability of data. The major conclusions from this workshop are presented.

  14. Uranium Adsorption on Granular Activated Carbon – Batch Testing

    SciTech Connect (OSTI)

    Parker, Kent E.; Golovich, Elizabeth C.; Wellman, Dawn M.

    2013-09-26T23:59:59.000Z

    The uranium adsorption performance of two activated carbon samples (Tusaar Lot B-64, Tusaar ER2-189A) was tested using unadjusted source water from well 299-W19-36. These batch tests support ongoing performance optimization efforts to use the best material for uranium treatment in the Hanford Site 200 West Area groundwater pump-and-treat system. A linear response of uranium loading as a function of the solution-to-solid ratio was observed for both materials. Kd values ranged from ~380,000 to >1,900,000 ml/g for the B-64 material and ~200,000 to >1,900,000 ml/g for the ER2-189A material. Uranium loading values ranged from 10.4 to 41.6 ?g/g for the two Tusaar materials.

  15. Standard test method for exfoliation corrosion susceptibility in 2XXX and 7XXX Series Aluminum Alloys (EXCO Test)

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2007-01-01T23:59:59.000Z

    1.1 This test method covers a procedure for constant immersion exfoliation corrosion (EXCO) testing of high-strength 2XXX and 7XXX series aluminum alloys. Note 1—This test method was originally developed for research and development purposes; however, it is referenced, in specific material specifications, as applicable for evaluating production material (refer to Section 14 on Precision and Bias). 1.2 This test method applies to all wrought products such as sheet, plate, extrusions, and forgings produced from conventional ingot metallurgy process. 1.3 This test method can be used with any form of specimen or part that can be immersed in the test solution. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

  16. Progress report on the results of testing advanced conceptual design metal barrier materials under relevant environmental conditions for a tuff repository

    SciTech Connect (OSTI)

    McCright, R.D.; Halsey, W.G.; Van Konynenburg, R.A.

    1987-12-01T23:59:59.000Z

    This report discusses the performance of candidate metallic materials envisioned for fabricating waste package containers for long-term disposal at a possible geological repository at Yucca Mountain, Nevada. Candidate materials include austenitic iron-base to nickel-base alloy (AISI 304L, AISI 316L, and Alloy 825), high-purity copper (CDA 102), and copper-base alloys (CDA 613 and CDA 715). Possible degradation modes affecting these container materials are identified in the context of anticipated environmental conditions at the repository site. Low-temperature oxidation is the dominant degradation mode over most of the time period of concern (minimum of 300 yr to a maximum of 1000 yr after repository closure), but various forms of aqueous corrosion will occur when water infiltrates into the near-package environment. The results of three years of experimental work in different repository-relevant environments are presented. Much of the work was performed in water taken from Well J-13, located near the repository, and some of the experiments included gamma irradiation of the water or vapor environment. The influence of metallurgical effects on the corrosion and oxidation resistance of the material is reviewed; these effects result from container fabrication, welding, and long-term aging at moderately elevated temperatures in the repository. The report indicates the need for mechanisms to understand the physical/chemical reactions that determine the nature and rate of the different degradation modes, and the subsequent need for models based on these mechanisms for projecting the long-term performance of the container from comparatively short-term laboratory data. 91 refs., 17 figs., 16 tabs.

  17. Supplemental Material Supplemental methods

    E-Print Network [OSTI]

    Tsien, Roger Y.

    Material (ESI) for Integrative Biology This journal is © The Royal Society of Chemistry 2009 #12;Computing counter and % ID/g calculated as (counts/weight tissue)/ total counts injected. Mass Spectrometry. To extract ACPPs to obtain electrospray (ESI) mass spectra, a solution of 9M guanidinium chloride (Gu

  18. Photovoltaic Materials

    SciTech Connect (OSTI)

    Duty, C.; Angelini, J.; Armstrong, B.; Bennett, C.; Evans, B.; Jellison, G. E.; Joshi, P.; List, F.; Paranthaman, P.; Parish, C.; Wereszczak, A.

    2012-10-15T23:59:59.000Z

    The goal of the current project was to help make the US solar industry a world leader in the manufacture of thin film photovoltaics. The overall approach was to leverage ORNL’s unique characterization and processing technologies to gain a better understanding of the fundamental challenges for solar cell processing and apply that knowledge to targeted projects with industry members. ORNL has the capabilities in place and the expertise required to understand how basic material properties including defects, impurities, and grain boundaries affect the solar cell performance. ORNL also has unique processing capabilities to optimize the manufacturing process for fabrication of high efficiency and low cost solar cells. ORNL recently established the Center for Advanced Thin-film Systems (CATS), which contains a suite of optical and electrical characterization equipment specifically focused on solar cell research. Under this project, ORNL made these facilities available to industrial partners who were interested in pursuing collaborative research toward the improvement of their product or manufacturing process. Four specific projects were pursued with industrial partners: Global Solar Energy is a solar industry leader in full scale production manufacturing highly-efficient Copper Indium Gallium diSelenide (CIGS) thin film solar material, cells and products. ORNL worked with GSE to develop a scalable, non-vacuum, solution technique to deposit amorphous or nanocrystalline conducting barrier layers on untextured stainless steel substrates for fabricating high efficiency flexible CIGS PV. Ferro Corporation’s Electronic, Color and Glass Materials (“ECGM”) business unit is currently the world’s largest supplier of metallic contact materials in the crystalline solar cell marketplace. Ferro’s ECGM business unit has been the world's leading supplier of thick film metal pastes to the crystalline silicon PV industry for more than 30 years, and has had operational cells and modules in the field for 25 years. Under this project, Ferro leveraged world leading analytical capabilities at ORNL to characterize the paste-to-silicon interface microstructure and develop high efficiency next generation contact pastes. Ampulse Corporation is developing a revolutionary crystalline-silicon (c-Si) thin-film solar photovoltaic (PV) technology. Utilizing uniquely-textured substrates and buffer materials from the Oak Ridge National Laboratory (ORNL), and breakthroughs in Hot-Wire Chemical Vapor Deposition (HW-CVD) techniques in epitaxial silicon developed at the National Renewable Energy Laboratory (NREL), Ampulse is creating a solar technology that is tunable in silicon thickness, and hence in efficiency and economics, to meet the specific requirements of multiple solar PV applications. This project focused on the development of a high rate deposition process to deposit Si, Ge, and Si1-xGex films as an alternate to hot-wire CVD. Mossey Creek Solar is a start-up company with great expertise in the solar field. The primary interest is to create and preserve jobs in the solar sector by developing high-yield, low-cost, high-efficiency solar cells using MSC-patented and -proprietary technologies. The specific goal of this project was to produce large grain formation in thin, net-shape-thickness mc-Si wafers processed with high-purity silicon powder and ORNL's plasma arc lamp melting without introducing impurities that compromise absorption coefficient and carrier lifetime. As part of this project, ORNL also added specific pieces of equipment to enhance our ability to provide unique insight for the solar industry. These capabilities include a moisture barrier measurement system, a combined physical vapor deposition and sputtering system dedicated to cadmium-containing deposits, adeep level transient spectroscopy system useful for identifying defects, an integrating sphere photoluminescence system, and a high-speed ink jet printing system. These tools were combined with others to study the effect of defects on the performance of crystalline silicon and

  19. Investigation of test methods, material properties, and processes for solar cell encapsulants. Seventeenth quarterly progress report, May 12-August 12, 1980

    SciTech Connect (OSTI)

    Willis, P. B.; Baum, B.

    1980-09-01T23:59:59.000Z

    The goal of this program is to identify, evaluate, and recommend encapsulant materials and processes for the production of cost-effective, long-life solar cell modules. Development efforts have emphasized the reformulation of polybutyl acrylate, a liquid pottant used in the casting encapsulation process. This material has been modified to yield a composition with much faster cure at lower temperatures. Minimodules have been successfully prepared from this low cost compound and are currently being evaluated by thermal/humidity cycling. Differential thermal analysis (DTA) was used for the examination of thermal stability in some of the pottant compounds of current interest. This method was useful in determining the temperatures at which oxidative or pyrolysis reactions resulted in degradation of the polymers. All the candidate pottants showed degradation onsets of over 200/sup 0/C. The effectiveness of a new primer was determined during this period. This formulation was similar to the silane coupling agent used in past experimentation but was modified with a peroxide to enhance the activity. Excellent bound strengths were obtained to glass, and mild steel that were resistant to immersion in boiling water. EVA to low iron glass gave an average bond strength of 35 lbs per inch of width. This new primer was also evaluated for the corrosion protection that could be provided to metal surfaces when primed and encapsulated in EVA. (WHK)

  20. Building America Technology Solutions for New and Existing Homes...

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

    Homes: Field Testing of Compartmentalization Methods for Multifamily Construction Building America Technology Solutions for New and Existing Homes: Field Testing of...

  1. Corrosion property of 9Cr-ODS steel in nitric acid solution for spent nuclear fuel reprocessing

    SciTech Connect (OSTI)

    Takeuchi, M.; Koizumi, T. [Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki 319-1195 (Japan); Inoue, M.; Koyama, S.I. [Japan Atomic Energy Agency, Oarai-machi, Higashi-ibaraki-gun, Ibaraki 311-1393 (Japan)

    2013-07-01T23:59:59.000Z

    Corrosion tests of oxide dispersion strengthened with 9% Cr (9Cr-ODS) steel, which is one of the desirable materials for cladding tube of sodium-cooled fast reactors, in pure nitric acid solution, spent FBR fuel solution, and its simulated solution were performed to understand the corrosion behavior in a spent nuclear fuel reprocessing. In this study, the 9Cr-ODS steel with lower effective chromium content was evaluated to understand the corrosion behavior conservatively. As results, the tube-type specimens of the 9Cr-ODS steels suffered severe weight loss owing to active dissolution at the beginning of the immersion test in pure nitric acid solution in the range from 1 to 3.5 M. In contrast, the weight loss was decreased and they showed a stable corrosion in the higher nitric acid concentration, the dissolved FBR fuel solution, and its simulated solution by passivation. The corrosion rates of the 9Cr-ODS steel in the dissolved FBR fuel solution and its simulated solution were 1-2 mm/y and showed good agreement with each other. The passivation was caused by the shift of corrosion potential to noble side owing to increase in nitric acid concentration or oxidative ions in the dissolved FBR fuel solution and the simulated spent fuel solution. (authors)

  2. 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.

  3. Materials Scientist

    Broader source: Energy.gov [DOE]

    Alternate Title(s):Materials Research Engineer; Metallurgical/Chemical Engineer; Product Development Manager;

  4. Materials for defense/aerospace applications (NON-SV)

    SciTech Connect (OSTI)

    Ellis, A. R.

    2012-03-01T23:59:59.000Z

    Through this effort, Sandia and Lockheed Martin Aeronautics Company (LM Aero) sought to assess the feasibility of (1) applying special materials to a defense application; (2) developing a piezoelectric-based micro thermophotovoltaic (TPV) cell; and (3) building and delivering a prototype laboratory emission measurement system. This project supported the Stockpile Research & Development Program by contributing to the development of radio frequency (RF) MEMS- and optical MEMS-based components - such as switches, phase shifters, oscillators, and filters - with improved performance and reduced weight and size. Investigation of failure mechanisms and solutions helped to ensure that MEMS-based technology will meet performance requirements and long term reliability goals in the specified environments dictated by Lockheed Martin's commercial and defense applications. The objectives of this project were to (1) fabricate and test materials for military applications; (2) perform a feasibility study of a piezoelectric-based micro TPV cell; and (3) build and deliver a prototype laboratory emission measurement system. Sandia fabricated and tested properties of materials, studied options for manufacturing scale-up, and delivered a prototype IR Emissometer. LM Aero provided material requirements and designs. Both participated in the investigation of attachment methods and environmental effects on material performance, a feasibility study of piezoelectric TPV cells, an investigation and development of new approaches to implement the required material functionality, and analysis and validation of material performance physics, numerical models, and experimental metrology.

  5. Interplay between two-phase and solid solution reactions in highvoltag...

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

    two-phase and solid solution reactions in highvoltage spinel cathode material for lithium ion batteries. Interplay between two-phase and solid solution reactions in...

  6. Integration of advanced nuclear materials separation processes

    SciTech Connect (OSTI)

    Jarvinen, G.D.; Worl, L.A.; Padilla, D.D.; Berg, J.M.; Neu, M.P.; Reilly, S.D.; Buelow, S.

    1998-12-31T23:59:59.000Z

    This is the final report of a two-year, Laboratory Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). This project has examined the fundamental chemistry of plutonium that affects the integration of hydrothermal technology into nuclear materials processing operations. Chemical reactions in high temperature water allow new avenues for waste treatment and radionuclide separation.Successful implementation of hydrothermal technology offers the potential to effective treat many types of radioactive waste, reduce the storage hazards and disposal costs, and minimize the generation of secondary waste streams. The focus has been on the chemistry of plutonium(VI) in solution with carbonate since these are expected to be important species in the effluent from hydrothermal oxidation of Pu-containing organic wastes. The authors investigated the structure, solubility, and stability of the key plutonium complexes. Installation and testing of flow and batch hydrothermal reactors in the Plutonium Facility was accomplished. Preliminary testing with Pu-contaminated organic solutions gave effluent solutions that readily met discard requirements. A new effort in FY 1998 will build on these promising initial results.

  7. METC/3M Cooperative Agreement CRADA 94-024 high temperature high pressure filter materials exposure test program. Volume 2, Final report

    SciTech Connect (OSTI)

    NONE

    1995-06-01T23:59:59.000Z

    This report is a summary of the results of activities of the particulate monitoring group in support of the METC/3M CRADA 94024. Online particulate monitoring began in June 1994 and ended in October, 1994. The particulate monitoring group participated in four MGCR runs (No. 7 through No. 10). The instrument used in measuring the particle loadings (particle counts and size distribution) is the Particle Measuring Systems Classical Scattering Aerosol Spectrometer Probe High Temperature and High Pressure (PMS Model CSASP-100-HTHP). This PMS unit is rated to operate at temperatures up to 540{degree}C and gage pressures up to 2.0 MPa. Gas stream conditions, temperature at 540{degree}C, gage pressure at 2.93 MPa, and gas flowrate at 0.0157 SCM per second, precluded the direct measurement of particulate loadings in the gas stream with the PMS unit. A side stream was extracted from the gas stream after it came over to the MGCR, Modular Gas Cleanup Rig, from the FBG, pressurized Fluidized-Bed Gasifier, but before it entered the filter testing vessel. A sampling probe of 0.635 cm O.D. thin wall stainless steel tubing was used for extracting the sample gas isokinetically based on the expected flowrate. The sample gas stream was further split into two streams; one was directed to the PMS unit and the other to the alkali monitor unit. The alkali monitor unit was not used during runs No. 7 through No. 10.

  8. weapons material

    National Nuclear Security Administration (NNSA)

    2%2A en Office of Weapons Material Protection http:nnsa.energy.govaboutusourprogramsnonproliferationprogramofficesinternationalmaterialprotectionandcooperation-1

  9. Optical limiting materials

    DOE Patents [OSTI]

    McBranch, Duncan W. (Santa Fe, NM); Mattes, Benjamin R. (Santa Fe, NM); Koskelo, Aaron C. (Los Alamos, NM); Heeger, Alan J. (Santa Barbara, CA); Robinson, Jeanne M. (Los Alamos, NM); Smilowitz, Laura B. (Los Alamos, NM); Klimov, Victor I. (Los Alamos, NM); Cha, Myoungsik (Goleta, CA); Sariciftci, N. Serdar (Santa Barbara, CA); Hummelen, Jan C. (Groningen, NL)

    1998-01-01T23:59:59.000Z

    Optical limiting materials. Methanofullerenes, fulleroids and/or other fullerenes chemically altered for enhanced solubility, in liquid solution, and in solid blends with transparent glass (SiO.sub.2) gels or polymers, or semiconducting (conjugated) polymers, are shown to be useful as optical limiters (optical surge protectors). The nonlinear absorption is tunable such that the energy transmitted through such blends saturates at high input energy per pulse over a wide range of wavelengths from 400-1100 nm by selecting the host material for its absorption wavelength and ability to transfer the absorbed energy into the optical limiting composition dissolved therein. This phenomenon should be generalizable to other compositions than substituted fullerenes.

  10. Material Analysis for a Fire Assessment.

    SciTech Connect (OSTI)

    Brown, Alexander; Nemer, Martin

    2014-08-01T23:59:59.000Z

    This report consolidates technical information on several materials and material classes for a fire assessment. The materials include three polymeric materials, wood, and hydraulic oil. The polymers are polystyrene, polyurethane, and melamine- formaldehyde foams. Samples of two of the specific materials were tested for their behavior in a fire - like environment. Test data and the methods used to test the materials are presented. Much of the remaining data are taken from a literature survey. This report serves as a reference source of properties necessary to predict the behavior of these materials in a fire.

  11. Material permeance measurement system and method

    DOE Patents [OSTI]

    Hallman, Jr., Russell Louis (Knoxville, TN); Renner, Michael John (Oak Ridge, TN)

    2012-05-08T23:59:59.000Z

    A system for measuring the permeance of a material. The permeability of the material may also be derived. The system provides a liquid or high concentration fluid bath on one side of a material test sample, and a gas flow across the opposing side of the material test sample. The mass flow rate of permeated fluid as a fraction of the combined mass flow rate of gas and permeated fluid is used to calculate the permeance of the material. The material test sample may be a sheet, a tube, or a solid shape. Operational test conditions may be varied, including concentration of the fluid, temperature of the fluid, strain profile of the material test sample, and differential pressure across the material test sample.

  12. Solution synthesis of germanium nanocrystals

    SciTech Connect (OSTI)

    Gerung, Henry (Albuquerque, NM); Boyle, Timothy J. (Kensington, MD); Bunge, Scott D. (Cuyahoga Falls, OH)

    2009-09-22T23:59:59.000Z

    A method for providing a route for the synthesis of a Ge(0) nanometer-sized material from. A Ge(II) precursor is dissolved in a ligand heated to a temperature, generally between approximately 100.degree. C. and 400.degree. C., sufficient to thermally reduce the Ge(II) to Ge(0), where the ligand is a compound that can bond to the surface of the germanium nanomaterials to subsequently prevent agglomeration of the nanomaterials. The ligand encapsulates the surface of the Ge(0) material to prevent agglomeration. The resulting solution is cooled for handling, with the cooling characteristics useful in controlling the size and size distribution of the Ge(0) materials. The characteristics of the Ge(II) precursor determine whether the Ge(0) materials that result will be nanocrystals or nanowires.

  13. Catalyzed Ceramic Burner Material

    SciTech Connect (OSTI)

    Barnes, Amy S., Dr.

    2012-06-29T23:59:59.000Z

    Catalyzed combustion offers the advantages of increased fuel efficiency, decreased emissions (both NOx and CO), and an expanded operating range. These performance improvements are related to the ability of the catalyst to stabilize a flame at or within the burner media and to combust fuel at much lower temperatures. This technology has a diverse set of applications in industrial and commercial heating, including boilers for the paper, food and chemical industries. However, wide spread adoption of catalyzed combustion has been limited by the high cost of precious metals needed for the catalyst materials. The primary objective of this project was the development of an innovative catalyzed burner media for commercial and small industrial boiler applications that drastically reduce the unit cost of the catalyzed media without sacrificing the benefits associated with catalyzed combustion. The scope of this program was to identify both the optimum substrate material as well as the best performing catalyst construction to meet or exceed industry standards for durability, cost, energy efficiency, and emissions. It was anticipated that commercial implementation of this technology would result in significant energy savings and reduced emissions. Based on demonstrated achievements, there is a potential to reduce NOx emissions by 40,000 TPY and natural gas consumption by 8.9 TBtu in industries that heavily utilize natural gas for process heating. These industries include food manufacturing, polymer processing, and pulp and paper manufacturing. Initial evaluation of commercial solutions and upcoming EPA regulations suggests that small to midsized boilers in industrial and commercial markets could possibly see the greatest benefit from this technology. While out of scope for the current program, an extension of this technology could also be applied to catalytic oxidation for volatile organic compounds (VOCs). Considerable progress has been made over the course of the grant period in accomplishing these objectives. Our work in the area of Pd-based, methane oxidation catalysts has led to the development of highly active catalysts with relatively low loadings of Pd metal using proprietary coating methods. The thermal stability of these Pd-based catalysts were characterized using SEM and BET analyses, further demonstrating that certain catalyst supports offer enhanced stability toward both PdO decomposition and/or thermal sintering/growth of Pd particles. When applied to commercially available fiber mesh substrates (both metallic and ceramic) and tested in an open-air burner, these catalyst-support chemistries showed modest improvements in the NOx emissions and radiant output compared to uncatalyzed substrates. More significant, though, was the performance of the catalyst-support chemistries on novel media substrates. These substrates were developed to overcome the limitations that are present with commercially available substrate designs and increase the gas-catalyst contact time. When catalyzed, these substrates demonstrated a 65-75% reduction in NOx emissions across the firing range when tested in an open air burner. In testing in a residential boiler, this translated into NOx emissions of <15 ppm over the 15-150 kBtu/hr firing range.

  14. Scintillator material

    DOE Patents [OSTI]

    Anderson, D.F.; Kross, B.J.

    1992-07-28T23:59:59.000Z

    An improved scintillator material comprising cerium fluoride is disclosed. Cerium fluoride has been found to provide a balance of good stopping power, high light yield and short decay constant that is superior to known scintillator materials such as thallium-doped sodium iodide, barium fluoride and bismuth germanate. As a result, cerium fluoride is favorably suited for use as a scintillator material in positron emission tomography. 4 figs.

  15. Scintillator material

    DOE Patents [OSTI]

    Anderson, D.F.; Kross, B.J.

    1994-06-07T23:59:59.000Z

    An improved scintillator material comprising cerium fluoride is disclosed. Cerium fluoride has been found to provide a balance of good stopping power, high light yield and short decay constant that is superior to known scintillator materials such as thallium-doped sodium iodide, barium fluoride and bismuth germanate. As a result, cerium fluoride is favorably suited for use as a scintillator material in positron emission tomography. 4 figs.

  16. Scintillator material

    DOE Patents [OSTI]

    Anderson, David F. (Batavia, IL); Kross, Brian J. (Aurora, IL)

    1992-01-01T23:59:59.000Z

    An improved scintillator material comprising cerium fluoride is disclosed. Cerium fluoride has been found to provide a balance of good stopping power, high light yield and short decay constant that is superior to known scintillator materials such as thallium-doped sodium iodide, barium fluoride and bismuth germanate. As a result, cerium fluoride is favorably suited for use as a scintillator material in positron emission tomography.

  17. Scintillator material

    DOE Patents [OSTI]

    Anderson, David F. (Batavia, IL); Kross, Brian J. (Aurora, IL)

    1994-01-01T23:59:59.000Z

    An improved scintillator material comprising cerium fluoride is disclosed. Cerium fluoride has been found to provide a balance of good stopping power, high light yield and short decay constant that is superior to known scintillator materials such as thallium-doped sodium iodide, barium fluoride and bismuth germanate. As a result, cerium fluoride is favorably suited for use as a scintillator material in positron emission tomography.

  18. Radiation Awareness TrainingRadiation Awareness Training Radioactive Material &Radioactive Material &

    E-Print Network [OSTI]

    Sherrill, David

    quarterly · Radioactive waste retrieval, storage, disposal · Dosimetry exchange · Leak tests of sealedRadiation Awareness TrainingRadiation Awareness Training Radioactive Material &Radioactive Material, Chemistry, Physics, Applied Physiology · Radioactive Material ­ Sealed Sources, Unsealed Sources (liquid

  19. E-Print Network 3.0 - argonne 10-l solutions Sample Search Results

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

    ; Environmental Management and Restoration Technologies 8 JOINING ADVANCED MATERIALS BY PLASTIC FLOW PROVIDES SOLUTION FOR OXYGEN SENSOR APPLICATIONS Summary:...

  20. Critical Materials:

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

    lighting. 14 (bottom) Criticality ratings of shortlisted raw 76 materials. 15 77 2. Technology Assessment and Potential 78 This section reviews the major trends within...

  1. Corrosion testing using isotopes

    DOE Patents [OSTI]

    Hohorst, F.A.

    1995-12-05T23:59:59.000Z

    A method is described for determining the corrosion behavior of a material with respect to a medium in contact with the material by: implanting a substantially chemically inert gas in a matrix so that corrosion experienced by the material causes the inert gas to enter the medium; placing the medium in contact with the material; and measuring the amount of inert gas which enters the medium. A test sample of a material whose resistance to corrosion by a medium is to be tested is described composed of: a body of the material, which body has a surface to be contacted by the medium; and a substantially chemically inert gas implanted into the body to a depth below the surface. A test sample of a material whose resistance to corrosion by a medium is to be tested is described composed of: a substrate of material which is easily corroded by the medium, the substrate having a surface; a substantially chemically inert gas implanted into the substrate; and a sheet of the material whose resistance to corrosion is to be tested, the sheet being disposed against the surface of the substrate and having a defined thickness. 3 figs.

  2. Corrosion testing using isotopes

    DOE Patents [OSTI]

    Hohorst, Frederick A. (Idaho Falls, ID)

    1995-12-05T23:59:59.000Z

    A method for determining the corrosion behavior of a material with respect to a medium in contact with the material by: implanting a substantially chemically inert gas in a matrix so that corrosion experienced by the material causes the inert gas to enter the medium; placing the medium in contact with the material; and measuring the amount of inert gas which enters the medium. A test sample of a material whose resistance to corrosion by a medium is to be tested, composed of: a body of the material, which body has a surface to be contacted by the medium; and a substantially chemically inert gas implanted into the body to a depth below the surface. A test sample of a material whose resistance to corrosion by a medium is to be tested, composed of: a substrate of material which is easily corroded by the medium, the substrate having a surface; a substantially chemically inert gas implanted into the substrate; and a sheet of the material whose resistance to corrosion is to be tested, the sheet being disposed against the surface of the substrate and having a defined thickness.

  3. Singlet exciton fission in solution

    E-Print Network [OSTI]

    Walker, Brian J.; Musser, Andrew J.; Beljonne, David; Friend, Richard H.

    2013-11-17T23:59:59.000Z

    Physics 135, 214508 (2011). 25. Sheraw, C. D., Jackson, T. N., Eaton, D. L. & Anthony, J. E. Functionalized Pentacene Active Layer Organic Thin-Film Transistors. Advanced Materials 15, 2009–2011 (2003). 26. Giri, G. et al. Tuning charge transport... in solution-sheared organic semiconductors using lattice strain. Nature 480, 504–8 (2011). 27. Gundlach, D. J. et al. Contact-induced crystallinity for high-performance soluble acene-based transistors and circuits. Nature Materials 7, 216–21 (2008). 28...

  4. MATH 507: TEST 1.1 SOLUTIONS 1. Test 1.1 Solutions

    E-Print Network [OSTI]

    Karagueuzian, Dikran

    (v1, . . . , vn) spans V . We define T(v) = a1w1 + . . . + anwn, which is well-defined because note that T is surjective, because (w1, . . . , wn) spans W, so every vector is of the form a1w1 + . . . + anwn = T(v) for some v in V . And T is injective, because if T(v) = a1w1 + . . . + anwn = 0, then all

  5. DATE : NVLAP LAB CODE: CONSTRUCTION MATERIALS TESTING

    E-Print Network [OSTI]

    Sand Equivalent Value of Soils and Fine Aggregate _____ 02/A44 ASTM C566 Total Moisture Content by Gillmore Needles _____ 02/A31 ASTM C305 Mechanical Mixing of Hydraulic Cement Pastes and Mortars of Plastic

  6. Module Encapsulation Materials, Processing and Testing (Presentation)

    Office of Scientific and Technical Information (OSTI)

    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 May Jun Jul(Summary)morphinan antagonist Journal Article: CrystalFG36-08GO18149 Revision: - Date: 06/15/10 ABENGOA SOLAREnergy operated

  7. Cermet materials

    DOE Patents [OSTI]

    Kong, Peter C. (Idaho Falls, ID)

    2008-12-23T23:59:59.000Z

    A self-cleaning porous cermet material, filter and system utilizing the same may be used in filtering particulate and gaseous pollutants from internal combustion engines having intermetallic and ceramic phases. The porous cermet filter may be made from a transition metal aluminide phase and an alumina phase. Filler materials may be added to increase the porosity or tailor the catalytic properties of the cermet material. Additionally, the cermet material may be reinforced with fibers or screens. The porous filter may also be electrically conductive so that a current may be passed therethrough to heat the filter during use. Further, a heating element may be incorporated into the porous cermet filter during manufacture. This heating element can be coated with a ceramic material to electrically insulate the heating element. An external heating element may also be provided to heat the cermet filter during use.

  8. Materials Science and Engineering Program Objectives

    E-Print Network [OSTI]

    Lin, Zhiqun

    necessary to understand the impact of engineering solutions in a global, economic, environmentalMaterials Science and Engineering Program Objectives Within the scope of the MSE mission, the objectives of the Materials Engineering Program are to produce graduates who: A. practice materials

  9. THE DAYLIGHTING SOLUTION

    E-Print Network [OSTI]

    Selkowitz, Stephen

    2013-01-01T23:59:59.000Z

    1980, pp.l4-20 THE DAYLIGHTING SOLUTION Stephen SelkowitzEEB-W·-80-19 W-74 THE DAYLIGHTING SOLUTION Stephen Selkowitz

  10. Test Series 2. 3 detailed test plan

    SciTech Connect (OSTI)

    Not Available

    1983-12-01T23:59:59.000Z

    Test Series 2.3 is chronologically the second of the five sub-series of tests which comprise Test Series 2, the second major Test Series as part of the combustion research phase to be carried out at the Grimethorpe Experimental Pressurised Fluidised Bed Combustion Facility. Test Series 2.3 will consist of 700 data gathering hours which is expected to require some 1035 coal burning hours. The tests will be performed using US supplied coal and dolomite. This will be the first major series of tests on the Facility with other than the UK datum coal and dolomite. The document summarises the background to the facility and the experimental program. Described are modifications which have been made to the facility following Test Series 2.1 and a series of Screening Tests. Detailed test objectives are specified as are the test conditions for the experiments which comprise the test series. The test results will provide information on the effects of the bed temperature, excess air level, Ca/S ratio, number of coal feed lines, and combustion efficiency and sulphur retention. A significant aspect of the test series will be part load tests which will investigate the performance of the facility under conditions of turn down which simulate load following concepts specified for two combined cycle concepts, i.e., their CFCC combined cycle and a turbo charged combined cycle. The material test plan is also presented. The principal feature of the materials programme is the planned exposure of a set of static turbine blade specimens in a cascade test loop to the high temperature, high pressure flue gas. A schedule for the programme is presented as are contingency plans.

  11. Electrochemical Testing of Ni-Cr-Mo-Gd Alloys

    SciTech Connect (OSTI)

    T. E. Lister; R. E. Mizia; H. Tian

    2005-10-01T23:59:59.000Z

    The waste package site recommendation design specified a boron-containing stainless steel, Neutronit 976/978, for fabrication of the internal baskets that will be used as a corrosion-resistant neutron-absorbing material. Recent corrosion test results gave higher-than-expected corrosion rates for this material. The material callout for these components has been changed to a Ni-Cr-Mo-Gd alloy (ASTM-B 932-04, UNS N06464) that is being developed at the Idaho National Laboratory. This report discusses the results of initial corrosion testing of this material in simulated in-package environments that could contact the fuel baskets after breach of the waste package outer barrier. The corrosion test matrix was executed using the potentiodynamic and potentiostatic electrochemical test techniques. The alloy performance shows low rates of general corrosion after initial removal of a gadolinium-rich second phase that intersects the surface. The high halide-containing test solutions exhibited greater tendencies toward initiation of crevice corrosion.

  12. Complex Materials

    ScienceCinema (OSTI)

    Cooper, Valentino

    2014-05-23T23:59:59.000Z

    Valentino Cooper uses some of the world's most powerful computing to understand how materials work at subatomic levels, studying breakthroughs such as piezoelectrics, which convert mechanical stress to electrical energy.

  13. Complex Materials

    SciTech Connect (OSTI)

    Cooper, Valentino

    2014-04-17T23:59:59.000Z

    Valentino Cooper uses some of the world's most powerful computing to understand how materials work at subatomic levels, studying breakthroughs such as piezoelectrics, which convert mechanical stress to electrical energy.

  14. Material Symbols 

    E-Print Network [OSTI]

    Clark, Andy

    2006-01-01T23:59:59.000Z

    What is the relation between the material, conventional symbol structures that we encounter in the spoken and written word, and human thought? A common assumption, that structures a wide variety of otherwise competing ...

  15. Materializing Energy

    E-Print Network [OSTI]

    James Pierce; Eric Paulos

    Motivated and informed by perspectives on sustainability and design, this paper draws on a diverse body of scholarly works related to energy and materiality to articulate a perspective on energy-as-materiality and propose a design approach of materializing energy. Three critical themes are presented: the intangibility of energy, the undifferentiatedness of energy, and the availability of energy. Each theme is developed through combination of critical investigation and design exploration, including the development and deployment of several novel design artifacts: Energy Mementos and The Local Energy Lamp. A framework for interacting with energy-as-materiality is proposed involving collecting, keeping, sharing, and activating energy. A number of additional concepts are also introduced, such as energy attachment, energy engagement, energy attunement, local energy and energy meta-data. Our work contributes both a broader, more integrative design perspective on energy and materiality as well as a diversity of more specific concepts and artifacts that may be of service to designers and researchers of interactive systems concerned with sustainability and energy. Author Keywords Sustainability, energy, materiality, design, design theory

  16. 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.

  17. Financing Solutions | Department of Energy

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

    Solution Center Financing Solutions Financing Solutions Transitioning to a clean energy economy requires innovative financing solutions that enable state, local, and tribal...

  18. Pendulum detector testing device

    DOE Patents [OSTI]

    Gonsalves, John M. (Modesto, CA)

    1997-01-01T23:59:59.000Z

    A detector testing device which provides consistent, cost-effective, repeatable results. The testing device is primarily constructed of PVC plastic and other non-metallic materials. Sensitivity of a walk-through detector system can be checked by: 1) providing a standard test object simulating the mass, size and material content of a weapon or other contraband, 2) suspending the test object in successive positions, such as head, waist and ankle levels, simulating where the contraband might be concealed on a person walking through the detector system; and 3) swinging the suspended object through each of the positions, while operating the detector system and observing its response. The test object is retained in a holder in which the orientation of the test device or target can be readily changed, to properly complete the testing requirements.

  19. Pendulum detector testing device

    DOE Patents [OSTI]

    Gonsalves, J.M.

    1997-09-30T23:59:59.000Z

    A detector testing device is described which provides consistent, cost-effective, repeatable results. The testing device is primarily constructed of PVC plastic and other non-metallic materials. Sensitivity of a walk-through detector system can be checked by: (1) providing a standard test object simulating the mass, size and material content of a weapon or other contraband, (2) suspending the test object in successive positions, such as head, waist and ankle levels, simulating where the contraband might be concealed on a person walking through the detector system; and (3) swinging the suspended object through each of the positions, while operating the detector system and observing its response. The test object is retained in a holder in which the orientation of the test device or target can be readily changed, to properly complete the testing requirements. 5 figs.

  20. Cylinder Test Specification

    SciTech Connect (OSTI)

    Richard Catanach; Larry Hill; Herbert Harry; Ernest Aragon; Don Murk

    1999-10-01T23:59:59.000Z

    The purpose of the cylinder testis two-fold: (1) to characterize the metal-pushing ability of an explosive relative to that of other explosives as evaluated by the E{sub 19} cylinder energy and the G{sub 19} Gurney energy and (2) to help establish the explosive product equation-of-state (historically, the Jones-Wilkins-Lee (JWL) equation). This specification details the material requirements and procedures necessary to assemble and fire a typical Los Alamos National Laboratory (LANL) cylinder test. Strict adherence to the cylinder. material properties, machining tolerances, material heat-treatment and etching processes, and high explosive machining tolerances is essential for test-to-test consistency and to maximize radial wall expansions. Assembly and setup of the cylinder test require precise attention to detail, especially when placing intricate pin wires on the cylinder wall. The cylinder test is typically fired outdoors and at ambient temperature.

  1. PIA - Savannah River Nuclear Solution (SRNS) MedGate Occupational...

    Office of Environmental Management (EM)

    Occupational Health and Safety Medical System (OHS) (Includes the Drug and Alcohol Testing System (Assistant)) PIA - Savannah River Nuclear Solution (SRNS) MedGate...

  2. PIA - Savannah River Nuclear Solution (SRNS) Procurement Cycle...

    Energy Savers [EERE]

    Occupational Health and Safety Medical System (OHS) (Includes the Drug and Alcohol Testing System (Assistant)) PIA - Savannah River Nuclear Solution (SRNS) Energy Employees...

  3. PIA - Savannah River Nuclear Solution (SRNS) Energy Employees...

    Energy Savers [EERE]

    Occupational Health and Safety Medical System (OHS) (Includes the Drug and Alcohol Testing System (Assistant)) PIA - Savannah River Nuclear Solution (SRNS) Procurement Cycle...

  4. Hardfacing material

    DOE Patents [OSTI]

    Branagan, Daniel J. (Iona, ID)

    2012-01-17T23:59:59.000Z

    A method of producing a hard metallic material by forming a mixture containing at least 55% iron and at least one of boron, carbon, silicon and phosphorus. The mixture is formed into an alloy and cooled to form a metallic material having a hardness of greater than about 9.2 GPa. The invention includes a method of forming a wire by combining a metal strip and a powder. The metal strip and the powder are rolled to form a wire containing at least 55% iron and from two to seven additional elements including at least one of C, Si and B. The invention also includes a method of forming a hardened surface on a substrate by processing a solid mass to form a powder, applying the powder to a surface to form a layer containing metallic glass, and converting the glass to a crystalline material having a nanocrystalline grain size.

  5. Optical limiting materials

    DOE Patents [OSTI]

    McBranch, D.W.; Mattes, B.R.; Koskelo, A.C.; Heeger, A.J.; Robinson, J.M.; Smilowitz, L.B.; Klimov, V.I.; Cha, M.; Sariciftci, N.S.; Hummelen, J.C.

    1998-04-21T23:59:59.000Z

    Methanofullerenes, fulleroids and/or other fullerenes chemically altered for enhanced solubility, in liquid solution, and in solid blends with transparent glass (SiO{sub 2}) gels or polymers, or semiconducting (conjugated) polymers, are shown to be useful as optical limiters (optical surge protectors). The nonlinear absorption is tunable such that the energy transmitted through such blends saturates at high input energy per pulse over a wide range of wavelengths from 400--1,100 nm by selecting the host material for its absorption wavelength and ability to transfer the absorbed energy into the optical limiting composition dissolved therein. This phenomenon should be generalizable to other compositions than substituted fullerenes. 5 figs.

  6. Thermoelectric materials development. Final report

    SciTech Connect (OSTI)

    Fleurial, J.P.; Caillat, T.; Borshchevsky, A.

    1998-09-01T23:59:59.000Z

    A systematic search for advanced thermoelectric materials was initiated at JPL several years ago to evaluate candidate materials which includes consideration of the following property attributes: (1) semiconducting properties; (2) large Seebeck coefficient; (3) high carrier mobility and high electrical conductivity; (4) low lattice thermal conductivity; and (5) chemical stability and low vapor pressure. Through this candidate screening process, JPL identified several families of materials as promising candidates for improved thermoelectric materials including the skutterudite family. There are several programs supporting various phases of the effort on these materials. As part of an ongoing effort to develop skutterudite materials with lower thermal conductivity values, several solid solutions and filled skutterudite materials were investigated under the effort sponsored by DOE. The efforts have primarily focused on: (1) study of existence and properties of solid solutions between the binary compounds CoSb{sub 3} and IrSb{sub 3}, and RuSb{sub 2}Te, and (2) CeFe{sub 4{minus}x}Sb{sub 12} based filled compositions. For the solid solutions, the lattice thermal conductivity reduction was expected to be reduced by the introduction of the Te and Ru atoms while in the case of CeFe{sub 4{minus}x}Ru{sub x}Sb{sub 12} based filled compositions. For the solid solutions, the lattice thermal conductivity reduction was expected to be reduced by the introduction of the Te and Ru atoms while in the case of CeFe{sub 4{minus}x}Ru{sub x}Sb{sub 12} filled compositions, the reduction would be caused by the rattling of Ce atoms located in the empty voids of the skutterudite structure and the substitution of Fe for Ru. The details of the sample preparation and characterization of their thermoelectric properties are reported in this report.

  7. Pyrolytic graphite production : automation of material placement

    E-Print Network [OSTI]

    Olle, Chase R

    2014-01-01T23:59:59.000Z

    This research examines the process and challenges associated with the addition of an autonomous transfer robot to a manufacturing line for AvCarb Material Solutions for use in production of pyrolytic graphite. Development ...

  8. Method for liquid chromatographic extraction of strontium from acid solutions

    DOE Patents [OSTI]

    Horwitz, E. Philip (Naperville, IL); Dietz, Mark L. (Evanston, IL)

    1992-01-01T23:59:59.000Z

    A method and apparatus for extracting strontium and technetium values from biological, industrial and environmental sample solutions using a chromatographic column is described. An extractant medium for the column is prepared by generating a solution of a diluent containing a Crown ether and dispersing the solution on a resin substrate material. The sample solution is highly acidic and is introduced directed to the chromatographic column and strontium or technetium is eluted using deionized water.

  9. Advanced Test Reactor Tour

    SciTech Connect (OSTI)

    Miley, Don

    2011-01-01T23:59:59.000Z

    The Advanced Test Reactor at Idaho National Laboratory is the foremost nuclear materials test reactor in the world. This virtual tour describes the reactor, how experiments are conducted, and how spent nuclear fuel is handled and stored. For more information about INL research, visit http://www.facebook.com/idahonationallaboratory.

  10. Advanced Test Reactor Tour

    ScienceCinema (OSTI)

    Miley, Don

    2013-05-28T23:59:59.000Z

    The Advanced Test Reactor at Idaho National Laboratory is the foremost nuclear materials test reactor in the world. This virtual tour describes the reactor, how experiments are conducted, and how spent nuclear fuel is handled and stored. For more information about INL research, visit http://www.facebook.com/idahonationallaboratory.

  11. The effect of inclusions in brittle material

    E-Print Network [OSTI]

    Janeiro, Raymond Pinho

    2009-01-01T23:59:59.000Z

    This thesis experimentally investigates the cracking behavior of brittle heterogeneous materials. Unconfined, uniaxial compression tests are conducted on prismatic gypsum specimens containing either one, or two, inclusions. ...

  12. Seismic design, testing and analysis of reinforced concrete wall buildings

    E-Print Network [OSTI]

    Panagiotou, Marios

    2008-01-01T23:59:59.000Z

    based on the material testing data of concrete cylinders inDESIGN, TESTING AND ANALYSIS OF REINFORCED CONCRETE WALLDESIGN, TESTING AND ANALYSIS OF REINFORCED CONCRETE WALL

  13. Aerosol tests conducted at Aberdeen Proving Grounds MD.

    SciTech Connect (OSTI)

    Brockmann, John E.; Lucero, Daniel A.; Servantes, Brandon Lee; Hankins, Matthew Granholm

    2012-06-01T23:59:59.000Z

    Test data are reported that demonstrate the deposition from a spray dispersion system (Illinois Tool Works inductively charging rotary atomization nozzle) for application of decontamination solution to various surfaces in the passenger cabin of a Boeing 737 aircraft. The decontamination solution (EnviroTru) was tagged with a known concentration of fluorescein permitting determination of both airborne decontaminant concentration and surface deposited decontaminant solution so that the effective deposition rates and surface coverage could be determined and correlated with the amount of material sprayed. Six aerosol dispersion tests were conducted. In each test, aluminum foil deposition coupons were set out throughout the passenger area and the aerosol was dispersed. The aerosol concentration was measured with filter samplers as well as with optical techniques Average aerosol deposition ranged from 3 to 15 grams of decontamination solution per square meter. Some disagreement was observed between various instruments utilizing different measurement principles. These results demonstrate a potentially effective method to disperse decontaminant to interior surfaces of a passenger aircraft.

  14. Future Climate Engineering Solutions

    E-Print Network [OSTI]

    Future Climate Engineering Solutions Joint report 13 engineering participating engeneering. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .11 Engineering Solutions ­ A Climate call from engineers. . . . . . . . . . . . . . . . . . . . .23 Summaries of National Reports . . . . . . . . . . . . . . . . . . . .25 Summary of The Climate Plan

  15. Materials Science & Tech Division | Advanced Materials | ORNL

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

    Materials Science and Technology SHARE Materials Science and Technology Division The Materials Science and Technology Division is unique within the Department of Energy (DOE)...

  16. Solar Thermal Reactor Materials Characterization

    SciTech Connect (OSTI)

    Lichty, P. R.; Scott, A. M.; Perkins, C. M.; Bingham, C.; Weimer, A. W.

    2008-03-01T23:59:59.000Z

    Current research into hydrogen production through high temperature metal oxide water splitting cycles has created a need for robust high temperature materials. Such cycles are further enhanced by the use of concentrated solar energy as a power source. However, samples subjected to concentrated solar radiation exhibited lifetimes much shorter than expected. Characterization of the power and flux distributions representative of the High Flux Solar Furnace(HFSF) at the National Renewable Energy Laboratory(NREL) were compared to ray trace modeling of the facility. In addition, samples of candidate reactor materials were thermally cycled at the HFSF and tensile failure testing was performed to quantify material degradation. Thermal cycling tests have been completed on super alloy Haynes 214 samples and results indicate that maximum temperature plays a significant role in reduction of strength. The number of cycles was too small to establish long term failure trends for this material due to the high ductility of the material.

  17. 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...

  18. 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...

  19. In situ testing to determination field-saturated hydraulic conductivity of UMTRA Project disposal cell covers, liners, and foundation areas. Special study

    SciTech Connect (OSTI)

    Not Available

    1994-02-01T23:59:59.000Z

    This special study was conducted to prepare a guidance document for selecting in situ hydraulic conductivity (K) tests, comparing in situ testing methods, and evaluating the results of such tests. This report may be used as a practical decision-making tool by the Uranium Mill Tailings Remedial Action (UMTRA) Project staff to determine which testing method will most efficiently achieve the field-saturated K results needed for long-term planning. A detailed section on near-surface test methods discusses each method which may be applicable to characterization of UMTRA disposal cell covers, liners and foundation materials. These potentially applicable test methods include the sealed double-ring infiltrometer (SDRI), the air-entry permeameter (AEP), the guelph permeameter, the two-stage borehole technique (TSB), the pressure infiltrometer, and the disk permeameter. Analytical solutions for these methods are provided, and limitations of these solutions are discussed, and a description of testing equipment design and installation are provided.

  20. Inflow performance relationships for solution-gas-drive reservoirs

    SciTech Connect (OSTI)

    Camacho-V, R.G.; Raghavan, R.

    1989-05-01T23:59:59.000Z

    In this theoretical study, a numerical model was used to examine the influence of pressure level and skin factor on the inflow performance relationships (IPR's) of wells producing under solution-gas-drive systems. Examination of the synthetic deliverability curves suggests that the exponent of the deliverability curve is a function of time and that the exponent is usually greater than unity. The implication of this observation to field data is discussed. The accuracy of procedures given in the literature to predict oilwell deliverabilities is also examined. It is shown that these methods can be used to predict future performance provided that the exponent of the deliverability curve is known and that extrapolations over large time ranges are avoided. If single-point tests are used to predict future performance (such tests assume that the exponent of the deliverability curve is constant), then errors in predictions will be minimized. Although relative permeability and fluid property data are required, the Muskat material-balance equation and the assumption that GOR is independent of distance can be used to predict future production rates. This method avoids problems associated with other methods in the literature and always yields reliable results. New methods to modify the IPR curve to incorporate changes in skin factor are presented. A new flow-efficiency definition based on the structure of the deliverability equations for solution-gas-drive reservoirs is proposed. This definition avoids problems that result when the currently available methods are applied to heavily stimulated wells.

  1. DWPF MATERIALS EVALUATION SUMMARY REPORT

    SciTech Connect (OSTI)

    Gee, T.; Chandler, G.; Daugherty, W.; Imrich, K.; Jankins, C.

    1996-09-12T23:59:59.000Z

    To better ensure the reliability of the Defense Waste Processing Facility (DWPF) remote canyon process equipment, a materials evaluation program was performed as part of the overall startup test program. Specific test programs included FA-04 ('Process Vessels Erosion/Corrosion Studies') and FA-05 (melter inspection). At the conclusion of field testing, Test Results Reports were issued to cover the various test phases. While these reports completed the startup test requirements, DWPF-Engineering agreed to compile a more detailed report which would include essentially all of the materials testing programs performed at DWPF. The scope of the materials evaouation programs included selected equipment from the Salt Process Cell (SPC), Chemical Process Cell (CPC), Melt Cell, Canister Decon Cell (CDC), and supporting facilities. The program consisted of performing pre-service baseline inspections (work completed in 1992) and follow-up inspections after completion of the DWPF cold chemical runs. Process equipment inspected included: process vessels, pumps, agitators, coils, jumpers, and melter top head components. Various NDE (non-destructive examination) techniques were used during the inspection program, including: ultrasonic testing (UT), visual (direct or video probe), radiography, penetrant testing (PT), and dimensional analyses. Finally, coupon racks were placed in selected tanks in 1992 for subsequent removal and corrosion evaluation after chemical runs.

  2. Investigation on the co-precipitation of transuranium elements from alkaline solutions by the method of appearing reagents

    SciTech Connect (OSTI)

    Krot, N.; Shilov, V.; Bessonov, A.; Budantseva, N.; Charushnikova, I.; Perminov, V.; Astafurova, L. [Russian Academy of Science (Russian Federation). Inst. of Physical Chemistry

    1996-06-06T23:59:59.000Z

    Highly alkaline radioactive waste solutions originating from production of plutonium for military purposes are stored in underground tanks at the U.S. Department of Energy Hanford Site. The purification of alkaline solutions from neptunium and plutonium is important in the treatment and disposal of these wastes. This report describes scoping tests with sodium hydroxide solutions, where precipitation techniques were investigated to perform the separation. Hydroxides of iron (III), manganese (II), cobalt (II, III), and chromium (III); manganese (IV) oxide, and sodium uranate were investigated as carriers. The report describes the optimum conditions that were identified to precipitate these carriers homogeneously throughout the solution by reductive, hydrolytic, or catalytic decomposition of alkali-soluble precursor compounds by a technique called the Method of Appearing Reagents. The coprecipitation of pentavalent and hexavalent neptunium and plutonium was investigated for the candidate agents under optimum conditions and is described in this report along with the following results. Plutonium coprecipitated well with all tested materials except manganese (IV) oxide. Neptunium only coprecipitated well with uranate. The report presents a hypothesis to explain these behaviors. Further tests with more complex solution matrices must be performed.

  3. Decontamination by cleaning with fluorocarbon surfactant solutions

    SciTech Connect (OSTI)

    Kaiser, R. [Entropic Systems, Inc., Winchester, MA (United States); Benson, C.E.; Meyers, E.S. [Oak Ridge National Lab., TN (United States); Vaughen, V.C.A. [Chemical Engineering and Safety Consulting Services, Knoxville, TN (United States)

    1994-02-01T23:59:59.000Z

    In the nuclear industry, facilities and their components inevitably become contaminated with radioactive materials. This report documents the application of a novel particle-removal process developed by Entropic Systems, Inc. (ESI), to decontaminate critical instruments and parts that are contaminated with small radioactive particles that adhere to equipment surfaces. The tests were performed as a cooperative effort between ESI and the Chemical Technology Division of the Oak Ridge National Laboratory (ORNL). ESI developed a new, environmentally compatible process to remove small particles from solid surfaces that is more effective than spraying or sonicating with CFC-113. This process uses inert perfluorinated liquids as working media; the liquids have zero ozone-depleting potential, are nontoxic and nonflammnable, and are generally recognized as nonhazardous materials. In the ESI process, parts to be cleaned are first sprayed or sonicated with a dilute solution of a high-molecular-weight fluorocarbon surfactant in an inert perfluorinated liquid to effect particle removal. The parts are then rinsed with the perfluorinated liquid to remove the fluorocarbon surfactant applied in the first step, and the residual rinse liquid is then evaporated from the parts into an air or nitrogen stream from which it is recovered. Nuclear contamination is inherently a surface phenomenon. The presence of radioactive particles is responsible for all ``smearable`` contamination and, if the radioactive particles are small enough, for some of the fixed contamination. Because radioactivity does not influence the physical chemistry of particle adhesion, the ESI process should be just as effective in removing radioactive particles as it is in removing nonradioactive particles.

  4. BUILDING MATERIALS RECLAMATION PROGRAM

    SciTech Connect (OSTI)

    David C. Weggel; Shen-En Chen; Helene Hilger; Fabien Besnard; Tara Cavalline; Brett Tempest; Adam Alvey; Madeleine Grimmer; Rebecca Turner

    2010-08-31T23:59:59.000Z

    This report describes work conducted on the Building Materials Reclamation Program for the period of September 2008 to August 2010. The goals of the project included selecting materials from the local construction and demolition (C&D) waste stream and developing economically viable reprocessing, reuse or recycling schemes to divert them from landfill storage. Educational resources as well as conceptual designs and engineering feasibility demonstrations were provided for various aspects of the work. The project was divided into two distinct phases: Research and Engineering Feasibility and Dissemination. In the Research Phase, a literature review was initiated and data collection commenced, an advisory panel was organized, and research was conducted to evaluate high volume C&D materials for nontraditional use; five materials were selected for more detailed investigations. In the Engineering Feasibility and Dissemination Phase, a conceptual study for a regional (Mecklenburg and surrounding counties) collection and sorting facility was performed, an engineering feasibility project to demonstrate the viability of recycling or reuse schemes was created, the literature review was extended and completed, and pedagogical materials were developed. Over the two-year duration of the project, all of the tasks and subtasks outlined in the original project proposal have been completed. The Final Progress Report, which briefly describes actual project accomplishments versus the tasks/subtasks of the original project proposal, is included in Appendix A of this report. This report describes the scientific/technical aspects (hypotheses, research/testing, and findings) of six subprojects that investigated five common C&D materials. Table 1 summarizes the six subprojects, including the C&D material studied and the graduate student and the faculty advisor on each subproject.

  5. MATERIALS CURRICULUM Major: Core Courses : 21 Credits

    E-Print Network [OSTI]

    Srinivasan, N.

    :0 Diffusion in Solids MT 225 3:0 Deformation and Failure Mechanisms at Elevated Temperatures MT 233 3, and nanotechnology. MT 101 3:0 January (4th Semester) Introduction to Materials Science Bonding, types of materials of structural characterization. Thermodynamics of solid solutions, phase diagrams, defects, diffusion

  6. Reference Material

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmosphericNuclear Security Administration the1 -the Mid-Infrared at 278, 298,NIST 800-53Reference Materials There are a variety of

  7. Materials Science

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: VegetationEquipment Surfaces andMapping the Nanoscale LandscapeImports 5.90 4.86(NHMFL)X-RayMaterials

  8. Remediation of AMD using natural and waste material

    SciTech Connect (OSTI)

    Basir, Nur Athirah Mohamad; Yaacob, Wan Zuhairi Wan [Pusat pengajian Sains Sekitaran dan Sumber Alam, Fakulti Sains dan Teknologi, Universiti Kebangsaan (Malaysia)

    2014-09-03T23:59:59.000Z

    Acid Mine Drainage (AMD) is highly acidic, sulphate rich and frequently carries a high transition metal and heavy metal burden. These AMD's eventually migrate into streams and rivers and impact negatively on the quality of these water bodies. So it is dire necessary to treat this AMD. Various materials such as ladle furnace slag (LFS), bentonite, zeolite, active carbon and kaolinite are currently available to remove heavy metals from contaminated water. All these materials are capable to rise up the pH value and adsorb heavy metals. The process is divided into two stages; screening test and tank experiment. Screening test is conduct by using Batch Equilibrium Test (BET), X-Ray Fluorescene (XRF) identification also Scanning Electron Microscopic (SEM) characteristic. The results showed that all the concentration of heavy metal are decreasing extremely and pH value rise up except for kaolinite. From screening test only ladle furnace slag, bentonite, zeolite and active carbon are chosen for the tank experiment. Tank experiment design with 18cm (H) X 15cm (L) X 15cm (H) was made by silica glass. All these treatment materials were stirred in the tank for 30 days. Initial pH for all tanks is 2.4 and after 30 days is changing into 6.11, 3.91, 2.98 and 2.71 for LFS, bentonite, active carbon as well as zeolite respectively. LFS is the best material for absorption of Zn, Mn and Cu in the synthetic solution. Meanwhile, bentonite is the best absorbent for Ni, Fe and Cd. The conclusion shows that LFS might have big potentials to control AMD pollution base on neutralize pH resulting in a great improvement in the quality of the water.

  9. Process for preparing energetic materials

    DOE Patents [OSTI]

    Simpson, Randall L. (Livermore, CA); Lee, Ronald S. (Livermore, CA); Tillotson, Thomas M. (Tracy, CA; , Hrubesh, Lawrence W. (Pleasanton, CA); Swansiger, Rosalind W. (Livermore, CA); Fox, Glenn A. (Livermore, CA)

    2011-12-13T23:59:59.000Z

    Sol-gel chemistry is used for the preparation of energetic materials (explosives, propellants and pyrotechnics) with improved homogeneity, and/or which can be cast to near-net shape, and/or made into precision molding powders. The sol-gel method is a synthetic chemical process where reactive monomers are mixed into a solution, polymerization occurs leading to a highly cross-linked three dimensional solid network resulting in a gel. The energetic materials can be incorporated during the formation of the solution or during the gel stage of the process. The composition, pore, and primary particle sizes, gel time, surface areas, and density may be tailored and controlled by the solution chemistry. The gel is then dried using supercritical extraction to produce a highly porous low density aerogel or by controlled slow evaporation to produce a xerogel. Applying stress during the extraction phase can result in high density materials. Thus, the sol-gel method can be used for precision detonator explosive manufacturing as well as producing precision explosives, propellants, and pyrotechnics, along with high power composite energetic materials.

  10. Micro-tensile testing system

    DOE Patents [OSTI]

    Wenski, Edward G. (Lenexa, KS)

    2007-07-17T23:59:59.000Z

    A micro-tensile testing system providing a stand-alone test platform for testing and reporting physical or engineering properties of test samples of materials having thicknesses of approximately between 0.002 inch and 0.030 inch, including, for example, LiGA engineered materials. The testing system is able to perform a variety of static, dynamic, and cyclic tests. The testing system includes a rigid frame and adjustable gripping supports to minimize measurement errors due to deflection or bending under load; serrated grips for securing the extremely small test sample; high-speed laser scan micrometers for obtaining accurate results; and test software for controlling the testing procedure and reporting results.

  11. Micro-tensile testing system

    DOE Patents [OSTI]

    Wenski, Edward G. (Lenexa, KS)

    2007-08-21T23:59:59.000Z

    A micro-tensile testing system providing a stand-alone test platform for testing and reporting physical or engineering properties of test samples of materials having thicknesses of approximately between 0.002 inch and 0.030 inch, including, for example, LiGA engineered materials. The testing system is able to perform a variety of static, dynamic, and cyclic tests. The testing system includes a rigid frame and adjustable gripping supports to minimize measurement errors due to deflection or bending under load; serrated grips for securing the extremely small test sample; high-speed laser scan micrometers for obtaining accurate results; and test software for controlling the testing procedure and reporting results.

  12. Micro-tensile testing system

    DOE Patents [OSTI]

    Wenski, Edward G.

    2006-01-10T23:59:59.000Z

    A micro-tensile testing system providing a stand-alone test platform for testing and reporting physical or engineering properties of test samples of materials having thicknesses of approximately between 0.002 inch and 0.030 inch, including, for example, LiGA engineered materials. The testing system is able to perform a variety of static, dynamic, and cyclic tests. The testing system includes a rigid frame and adjustable gripping supports to minimize measurement errors due to deflection or bending under load; serrated grips for securing the extremely small test sample; high-speed laser scan micrometers for obtaining accurate results; and test software for controlling the testing procedure and reporting results.

  13. Method for producing microcomposite powders using a soap solution

    DOE Patents [OSTI]

    Maginnis, Michael A. (Coker, AL); Robinson, David A. (Mobile, AL)

    1996-01-01T23:59:59.000Z

    A method for producing microcomposite powders for use in superconducting and non-superconducting applications. A particular method to produce microcomposite powders for use in superconducting applications includes the steps of: (a) preparing a solution including ammonium soap; (b) dissolving a preselected amount of a soluble metallic such as silver nitrate in the solution including ammonium soap to form a first solution; (c) adding a primary phase material such as a single phase YBC superconducting material in particle form to the first solution; (d) preparing a second solution formed from a mixture of a weak acid and an alkyl-mono-ether; (e) adding the second solution to the first solution to form a resultant mixture; (f) allowing the resultant mixture to set until the resultant mixture begins to cloud and thicken into a gel precipitating around individual particles of the primary phase material; (g) thereafter drying the resultant mixture to form a YBC superconducting material/silver nitrate precursor powder; and (h) calcining the YBC superconducting material/silver nitrate precursor powder to convert the silver nitrate to silver and thereby form a YBC/silver microcomposite powder wherein the silver is substantially uniformly dispersed in the matrix of the YBC material.

  14. Solution Phase Routes to Functional Nanostructured Materials for Energy Applications

    E-Print Network [OSTI]

    Rauda, Iris Ester

    2012-01-01T23:59:59.000Z

    for Electrochemical Supercapacitors. ” Oral Presentation atE. Electrochemical Supercapacitors: Scientific FundamentalsOxide Thin Film Based Supercapacitors. Curr. Appl. Phys.

  15. Solution Phase Routes to Functional Nanostructured Materials for Energy Applications

    E-Print Network [OSTI]

    Rauda, Iris Ester

    2012-01-01T23:59:59.000Z

    Carbon Nanotubes for Enhanced Electrochemical EnergyEnergy dispersive X-ray spectra for CuInSe 2 nanowires (a) and nanotubes (Energy dispersive X-ray spectra for CuInSe 2 nanowires (a) and nanotubes (

  16. Solution Phase Routes to Functional Nanostructured Materials for Energy Applications

    E-Print Network [OSTI]

    Rauda, Iris Ester

    2012-01-01T23:59:59.000Z

    Rate Rechargeable Lithium Batteries. Small 2011, 7, 407–414.Rate Rechargeable Lithium Batteries. Small 2011, 7, 407?414.Rate Rechargeable Lithium Batteries: Relationships among

  17. Solution Phase Routes to Functional Nanostructured Materials for Energy Applications

    E-Print Network [OSTI]

    Rauda, Iris Ester

    2012-01-01T23:59:59.000Z

    of Solid-State Dye-Sensitized Solar Cell Performance bySolid-State Dye-Sensitized Solar Cell with an Amphiphilicthe Performance of Dye-Sensitized Solar Cells by Co-Grafting

  18. Solution Phase Routes to Functional Nanostructured Materials for Energy Applications

    E-Print Network [OSTI]

    Rauda, Iris Ester

    2012-01-01T23:59:59.000Z

    Carbon Nanotubes as Supercapacitor Electrodes. J. Phys.Z. Enhancing the Supercapacitor Performance of Graphene/MnO

  19. Solution Phase Routes to Functional Nanostructured Materials for Energy Applications

    E-Print Network [OSTI]

    Rauda, Iris Ester

    2012-01-01T23:59:59.000Z

    Networks: Ag 2 Se Gels and Aerogels by Cation ExchangeArea Vanadium Oxide Aerogels. Electrochem. Solid State Lett.of a 3D Graphene/Nanoparticle Aerogel. Adv. Mater. 2011, 23,

  20. Materials Solutions for Hydrogen Delivery in Pipelines | 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 RankCombustion | Department of EnergyDevelopment AccidentEnergy Objective: Develop

  1. Low-Cost Solutions for Dynamic Window Material

    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-Dimensionalthe10IO1OP001Long-Termpaul_fini@cree.com CREECummins

  2. Materials and methods for stabilizing nanoparticles in salt solutions

    DOE Patents [OSTI]

    Robinson, David Bruce; Zuckermann, Ronald; Buffleben, George M.

    2013-06-11T23:59:59.000Z

    Sequence-specific polymers are proving to be a powerful approach to assembly and manipulation of matter on the nanometer scale. Ligands that are peptoids, or sequence-specific N-functional glycine oligomers, allow precise and flexible control over the arrangement of binding groups, steric spacers, charge, and other functionality. We have synthesized short peptoids that can prevent the aggregation of gold nanoparticles in high-salt environments including divalent salt, and allow co-adsorption of a single DNA molecule. This degree of precision and versatility is likely to prove essential in bottom-up assembly of nanostructures and in biomedical applications of nanomaterials.

  3. Solution deposition assembly

    DOE Patents [OSTI]

    Roussillon, Yann; Scholz, Jeremy H; Shelton, Addison; Green, Geoff T; Utthachoo, Piyaphant

    2014-01-21T23:59:59.000Z

    Methods and devices are provided for improved deposition systems. In one embodiment of the present invention, a deposition system is provided for use with a solution and a substrate. The system comprises of a solution deposition apparatus; at least one heating chamber, at least one assembly for holding a solution over the substrate; and a substrate curling apparatus for curling at least one edge of the substrate to define a zone capable of containing a volume of the solution over the substrate. In another embodiment of the present invention, a deposition system for use with a substrate, the system comprising a solution deposition apparatus; at heating chamber; and at least assembly for holding solution over the substrate to allow for a depth of at least about 0.5 microns to 10 mm.

  4. Fossil energy materials needs assessment

    SciTech Connect (OSTI)

    King, R.T.; Judkins, R.R. (comps.)

    1980-07-01T23:59:59.000Z

    An assessment of needs for materials of construction for fossil energy systems was prepared by ORNL staff members who conducted a literature search and interviewed various individuals and organizations that are active in the area of fossil energy technology. Critical materials problems associated with fossil energy systems are identified. Background information relative to the various technologies is given and materials research needed to enhance the viability and improve the economics of fossil energy processes is discussed. The assessment is presented on the basis of materials-related disciplines that impact fossil energy material development. These disciplines include the design-materials interface, materials fabrication technology, corrosion and materials compatibility, wear phenomena, ceramic materials, and nondestructive testing. The needs of these various disciplines are correlated with the emerging fossil energy technologies that require materials consideration. Greater emphasis is given to coal technology - particularly liquefaction, gasification, and fluidized bed combustion - than to oil and gas technologies because of the perceived inevitability of US dependence on coal conversion and utilization systems as a major part of our total energy production.

  5. Mixed oxide solid solutions

    DOE Patents [OSTI]

    Magno, Scott (Dublin, CA); Wang, Ruiping (Fremont, CA); Derouane, Eric (Liverpool, GB)

    2003-01-01T23:59:59.000Z

    The present invention is a mixed oxide solid solution containing a tetravalent and a pentavalent cation that can be used as a support for a metal combustion catalyst. The invention is furthermore a combustion catalyst containing the mixed oxide solid solution and a method of making the mixed oxide solid solution. The tetravalent cation is zirconium(+4), hafnium(+4) or thorium(+4). In one embodiment, the pentavalent cation is tantalum(+5), niobium(+5) or bismuth(+5). Mixed oxide solid solutions of the present invention exhibit enhanced thermal stability, maintaining relatively high surface areas at high temperatures in the presence of water vapor.

  6. Materials performance in coal gasification pilot plants

    SciTech Connect (OSTI)

    Judkins, R.R.; Bradley, R.A.

    1987-10-15T23:59:59.000Z

    This paper presents the results of several materials testing projects which were conducted in operating coal gasification pilot plants in the United States. These projects were designed to test potential materials of construction for commercial plants under actual operating conditions. Pilot plants included in the overall test program included the Hygas, Conoco Coal, Synthane, Bi-Gas, Peatgas (Hygas operating with peat), Battelle, U-Gas, Westinghouse (now KRW), General Electric (Gegas), and Mountain Fuel Resources plants. Test results for a large variety of alloys are discussed and conclusions regarding applicability of these materials in coal gasification environments are presented. 14 refs., 2 tabs.

  7. Critical Materials Institute

    ScienceCinema (OSTI)

    Alex King

    2013-06-05T23:59:59.000Z

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

  8. Removal of metal ions from aqueous solution

    DOE Patents [OSTI]

    Jackson, Paul J. (both Los Alamos, NM); Delhaize, Emmanuel (both Los Alamos, NM); Robinson, Nigel J. (Durham, GB2); Unkefer, Clifford J. (Los Alamos, NM); Furlong, Clement (Seattle, WA)

    1990-11-13T23:59:59.000Z

    A method of removing heavy metals from aqueous solution, a composition of matter used in effecting said removal, and apparatus used in effecting said removal. One or more of the polypeptides, poly (.gamma.-glutamylcysteinyl)glycines, is immobilized on an inert material in particulate form. Upon contact with an aqueous solution containing heavy metals, the polypeptides sequester the metals, removing them from the solution. There is selectivity of poly (.gamma.-glutamylcysteinyl)glycines having a particular number of monomer repeat unit for particular metals. The polypeptides are easily regenerated by contact with a small amount of an organic acid, so that they can be used again to remove heayv metals from solution. This also results in the removal of the metals from the column in a concentrated form.

  9. Removal of metal ions from aqueous solution

    DOE Patents [OSTI]

    Jackson, Paul J. (Los Alamos, NM); Delhaize, Emmanuel (Los Alamos, NM); Robinson, Nigel J. (Durham, GB2); Unkefer, Clifford J. (Los Alamos, NM); Furlong, Clement (Seattle, WA)

    1990-01-01T23:59:59.000Z

    A method of removing heavy metals from aqueous solution, a composition of matter used in effecting said removal, and apparatus used in effecting said removal. One or more of the polypeptides, poly (.gamma.-glutamylcysteinyl)glycines, is immobilized on an inert material in particulate form. Upon contact with an aqueous solution containing heavy metals, the polypeptides sequester the metals, removing them from the solution. There is selectivity of poly (.gamma.-glutamylcysteinyl)glycines having a particular number of monomer repeat units for particular metals. The polypeptides are easily regenerated by contact with a small amount of an organic acid, so that they can be used again to remove heavy metals from solution. This also results in the removal of the metals from the column in a concentrated form.

  10. Lightweight Steel Solutions for Automotive Industry

    SciTech Connect (OSTI)

    Lee, Hong Woo; Kim, Gyosung; Park, Sung Ho [Technical Research Laboratories, POSCO, 699, Gumho-dong, Gwangyang-si, Jeonnam, 545-090 (Korea, Republic of)

    2010-06-15T23:59:59.000Z

    Recently, improvement in fuel efficiency and safety has become the biggest issue in worldwide automotive industry. Although the regulation of environment and safety has been tightened up more and more, the majority of vehicle bodies are still manufactured from stamped steel components. This means that the optimized steel solutions enable to demonstrate its ability to reduce body weight with high crashworthiness performance instead of expensive light weight materials such as Al, Mg and composites. To provide the innovative steel solutions for automotive industry, POSCO has developed AHSS and its application technologies, which is directly connected to EVI activities. EVI is a technical cooperation program with customer covering all stages of new car project from design to mass production. Integrated light weight solutions through new forming technologies such as TWB, hydroforming and HPF are continuously developed and provided for EVI activities. This paper will discuss the detailed status of these technologies especially light weight steel solutions based on innovative technologies.

  11. Processing and analysis techniques involving in-vessel material generation

    DOE Patents [OSTI]

    Schabron, John F. (Laramie, WY); Rovani, Jr., Joseph F. (Laramie, WY)

    2012-09-25T23:59:59.000Z

    In at least one embodiment, the inventive technology relates to in-vessel generation of a material from a solution of interest as part of a processing and/or analysis operation. Preferred embodiments of the in-vessel material generation (e.g., in-vessel solid material generation) include precipitation; in certain embodiments, analysis and/or processing of the solution of interest may include dissolution of the material, perhaps as part of a successive dissolution protocol using solvents of increasing ability to dissolve. Applications include, but are by no means limited to estimation of a coking onset and solution (e.g., oil) fractionating.

  12. Processing and analysis techniques involving in-vessel material generation

    DOE Patents [OSTI]

    Schabron, John F. (Laramie, WY); Rovani, Jr., Joseph F. (Laramie, WY)

    2011-01-25T23:59:59.000Z

    In at least one embodiment, the inventive technology relates to in-vessel generation of a material from a solution of interest as part of a processing and/or analysis operation. Preferred embodiments of the in-vessel material generation (e.g., in-vessel solid material generation) include precipitation; in certain embodiments, analysis and/or processing of the solution of interest may include dissolution of the material, perhaps as part of a successive dissolution protocol using solvents of increasing ability to dissolve. Applications include, but are by no means limited to estimation of a coking onset and solution (e.g., oil) fractionating.

  13. Dispersant solutions for dispersing hydrocarbons

    DOE Patents [OSTI]

    Tyndall, Richard L. (Clinton, TN)

    1997-01-01T23:59:59.000Z

    A dispersant solution includes a hydrocarbon dispersing solution derived from a bacterium from ATCC 75527, ATCC 75529, or ATCC 55638.

  14. Dispersant solutions for dispersing hydrocarbons

    DOE Patents [OSTI]

    Tyndall, R.L.

    1997-03-11T23:59:59.000Z

    A dispersant solution includes a hydrocarbon dispersing solution derived from a bacterium from ATCC 75527, ATCC 75529, or ATCC 55638.

  15. Retained Gas Sampler Calibration and Simulant Tests

    SciTech Connect (OSTI)

    CRAWFORD, B.A.

    2000-01-05T23:59:59.000Z

    This test plan provides a method for calibration of the retained gas sampler (RGS) for ammonia gas analysis. Simulant solutions of ammonium hydroxide at known concentrations will be diluted with isotopically labeled 0.04 M ammonium hydroxide solution. Sea sand solids will also be mixed with ammonium hydroxide solution and diluent to determine the accuracy of the system for ammonia gas analysis.

  16. MATERIALS MANAGEMENT MATERIALS MANAGEMENT -INVENTORY CONTROL

    E-Print Network [OSTI]

    Oliver, Douglas L.

    MATERIALS MANAGEMENT MATERIALS MANAGEMENT - INVENTORY CONTROL Record of Property Transferred from ______ ___________________________________ 2. DEAN (If Applies) ______ ___________________________________ 5. UNIVERSITY DIRECTOR OF MATERIALS MANAGEMENT ______ ___________________________________ 3. HOSPITAL DIRECTOR (If Applies) ______ IF YOU NEED

  17. Highly Dispersed Pseudo-Homogeneous and Heterogeneous Catalysts Synthesized via Inverse Micelle Solutions for the Liquefaction of Coal

    SciTech Connect (OSTI)

    Hampden-Smith, M.; Kawola, J.S.; Martino, A.; Sault, A.G.; Yamanaka, S.A.

    1999-01-05T23:59:59.000Z

    The mission of this project was to use inverse micelle solutions to synthesize nanometer sized metal particles and test the particles as catalysts in the liquefaction of coal and other related reactions. The initial focus of the project was the synthesis of iron based materials in pseudo-homogeneous form. The frost three chapters discuss the synthesis, characterization, and catalyst testing in coal liquefaction and model coal liquefaction reactions of iron based pseudo-homogeneous materials. Later, we became interested in highly dispersed catalysts for coprocessing of coal and plastic waste. Bifunctional catalysts . to hydrogenate the coal and depolymerize the plastic waste are ideal. We began studying, based on our previously devised synthesis strategies, the synthesis of heterogeneous catalysts with a bifunctional nature. In chapter 4, we discuss the fundamental principles in heterogeneous catalysis synthesis with inverse micelle solutions. In chapter 5, we extend the synthesis of chapter 4 to practical systems and use the materials in catalyst testing. Finally in chapter 6, we return to iron and coal liquefaction now studied with the heterogeneous catalysts.

  18. System and method for measuring permeability of materials

    DOE Patents [OSTI]

    Hallman, Jr., Russell Louis; Renner, Michael John

    2013-07-09T23:59:59.000Z

    Systems and methods are provided for measuring the permeance of a material. The permeability of the material may also be derived. Systems typically provide a liquid or high concentration fluid bath on one side of a material test sample, and a gas flow across the opposing side of the material test sample. The mass flow rate of permeated fluid as a fraction of the combined mass flow rate of gas and permeated fluid is used to calculate the permeance of the material. The material test sample may be a sheet, a tube, or a solid shape. Operational test conditions may be varied, including concentration of the fluid, temperature of the fluid, strain profile of the material test sample, and differential pressure across the material test sample.

  19. Functional Materials for Energy | Advanced Materials | ORNL

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

    Energy Storage Fuel Cells Thermoelectrics Separations Materials Catalysis Sensor Materials Polymers and Composites Carbon Fiber Related Research Chemistry and Physics at...

  20. Stability of nickel-coated sand as gravel-pack material for thermal wells

    SciTech Connect (OSTI)

    Sacuta, A.; Nguyen, D.M.; Kissel, G.A. (Alberta Research Council (CA))

    1988-11-01T23:59:59.000Z

    Laboratory flow tests have been carried out to study the stability of various nickel-coated sands under aqueous steam temperature and pH conditions that may exist in thermal recovery operations. Other gravel-pack materials tested include Ottawa sand, sintered bauxite, cement clinker, zirconium oxide, and nickel pellets. A comparison was made between the performances of these materials after exposure to identical thermal and hydrolytic conditions. Test results indicate that nickel-coated sands are highly resistant to dissolution at temperatures as high as 300/sup 0/C (570/sup 0/F) and to solution pH's from 4.75 to 11. Weight losses measured after a 72-hour period were less than 1%. In contrast, weight losses from sintered bauxite, zirconium oxide, and Ottawa sand dissolution tests were 30 to 70 times higher under the same conditions. Cement clinker losses were in the intermediate range under alkaline conditions. API standard crushing and acid-solubility tests for proppants also were performed on nickel-coated sands. These results were favorable in that they exceeded the recommended standards. This study of nickel-coated sand stability and mechanical strength has demonstrated its high potential for application as either a gravel-pack material or proppant in thermal recovery operations.

  1. E-Print Network 3.0 - approximate solution method Sample Search...

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

    numerical solution of partial differential... , Meshfree Approximation Methods with Matlab, Lecture Notes, IIT, 2005. Other required material... data approximation with radial...

  2. 359-06/RDS/rs A Fusion Nuclear Science Facility, ITER, Superconducting Tokamaks, and a Materials Test Facility Enable Demo 359-06/RDS/rs FDF is Viewed as a Direct Follow-on of DIII-D (50 % larger)

    E-Print Network [OSTI]

    R. D. Stambaugh

    2008-01-01T23:59:59.000Z

    By using conservative Advanced Tokamak physics to run steady-state and produce 100-250 MW fusion power – Modest energy gain (Q<5) – Continuous operation for 30 % of a year in 2 weeks periods – Test materials with high neutron fluence (3-8 MW-yr/m 2) – Further develop all elements of Advanced Tokamak physics, qualifying them for an advanced performance DEMO With ITER and IFMIF, provide the basis for a fusion DEMO Power Plant

  3. Well performance under solutions gas drive

    SciTech Connect (OSTI)

    Camacho-Velazquez, R.G.

    1987-01-01T23:59:59.000Z

    A fully implicit black-oil simulator was written to predict the drawdown and buildup responses for a single well under Solution Gas Drive. The model is capable of handling the following reservoir behaviors: Unfractured reservoir, Double-Porosity system, and Double Permeability-Double Porosity model of Bourdet. The accuracy of the model results is tested for both single-phase liquid flow and two-phase flow. The results presented here provide a basis for the empirical equations presented in the literature. New definitions of pseudopressure and dimensionless time are presented. By using these two definitions, the multiphase flow solutions correlate with the constant rate liquid flow solution for both transient and boundary-dominated flow. For pressure buildup tests, an analogue for the liquid solution is constructed from the drawdown pseudopressure, similar to the reservoir integral of J. Jones. The utility of using the producing gas-oil ration at shut in to compute pseudopressures and pseudotimes is documented. The influence of pressure level and skin factor on the Inflow Performance Relationship (IPR) of wells producing solution gas drive systems is examined. A new definition of flow efficiency that is based on the structure of the deliverability equations is proposed. This definition avoids problems that result when the presently available methods are applied to heavily stimulated wells. The need for using pseudopressures to analyze well test data for fractured reservoirs is shown. Expressions to compute sandface saturations for fractured systems are presented.

  4. A NEW PROCESS DEVELOPED FOR SEPARATION OF LIGNIN FROM AMMONIUM HYDROXIDE PRETREATMENT SOLUTIONS

    SciTech Connect (OSTI)

    Sherman, S.; Gorensek, M.; Milliken, C.

    2010-12-14T23:59:59.000Z

    A method is described for separating lignin from liquid solutions resulting from the pretreatment of lignocellulosic materials such as switchgrass with ammonium hydroxide. The method involves a sequence of steps including acidification, evaporation, and precipitation or centrifugation that are performed under defined conditions, and results in a relatively pure, solid lignin product. The method is tested on ammonium hydroxide solutions containing lignin extracted from switchgrass. Experimental results show that the method is capable of recovering between 66-95% of dissolved lignin as a precipitated solid. Cost estimates of pilot-scale and industrial-scale expressions of the process indicate that breakeven lignin prices of $2.36/kg and $0.78/kg, respectively, may be obtainable with this recovery method.

  5. Chemical deposition methods using supercritical fluid solutions

    DOE Patents [OSTI]

    Sievers, Robert E. (Boulder, CO); Hansen, Brian N. (Boulder, CO)

    1990-01-01T23:59:59.000Z

    A method for depositing a film of a desired material on a substrate comprises dissolving at least one reagent in a supercritical fluid comprising at least one solvent. Either the reagent is capable of reacting with or is a precursor of a compound capable of reacting with the solvent to form the desired product, or at least one additional reagent is included in the supercritical solution and is capable of reacting with or is a precursor of a compound capable of reacting with the first reagent or with a compound derived from the first reagent to form the desired material. The supercritical solution is expanded to produce a vapor or aerosol and a chemical reaction is induced in the vapor or aerosol so that a film of the desired material resulting from the chemical reaction is deposited on the substrate surface. In an alternate embodiment, the supercritical solution containing at least one reagent is expanded to produce a vapor or aerosol which is then mixed with a gas containing at least one additional reagent. A chemical reaction is induced in the resulting mixture so that a film of the desired material is deposited.

  6. Exact Solutions of Einstein's Field Equations

    E-Print Network [OSTI]

    P. S. Negi

    2004-01-08T23:59:59.000Z

    We examine various well known exact solutions available in the literature to investigate the recent criterion obtained in ref. [20] which should be fulfilled by any static and spherically symmetric solution in the state of hydrostatic equilibrium. It is seen that this criterion is fulfilled only by (i) the regular solutions having a vanishing surface density together with the pressure, and (ii) the singular solutions corresponding to a non-vanishing density at the surface of the configuration . On the other hand, the regular solutions corresponding to a non-vanishing surface density do not fulfill this criterion. Based upon this investigation, we point out that the exterior Schwarzschild solution itself provides necessary conditions for the types of the density distributions to be considered inside the mass, in order to obtain exact solutions or equations of state compatible with the structure of general relativity. The regular solutions with finite centre and non-zero surface densities which do not fulfill the criterion [20], in fact, can not meet the requirement of the `actual mass' set up by exterior Schwarzschild solution. The only regular solution which could be possible in this regard is represented by uniform (homogeneous) density distribution. The criterion [20] provides a necessary and sufficient condition for any static and spherical configuration (including core-envelope models) to be compatible with the structure of general relativity. Thus, it may find application to construct the appropriate core-envelope models of stellar objects like neutron stars and may be used to test various equations of state for dense nuclear matter and the models of relativistic stellar structures like star clusters.

  7. Materials Challenges in Nuclear Energy

    SciTech Connect (OSTI)

    Zinkle, Steven J [ORNL] [ORNL; Was, Gary [University of Michigan] [University of Michigan

    2013-01-01T23:59:59.000Z

    Nuclear power currently provides about 13% of the worldwide electrical power, and has emerged as a reliable baseload source of electricity. A number of materials challenges must be successfully resolved for nuclear energy to continue to make further improvements in reliability, safety and economics. The operating environment for materials in current and proposed future nuclear energy systems is summarized, along with a description of materials used for the main operating components. Materials challenges associated with power uprates and extensions of the operating lifetimes of reactors are described. The three major materials challenges for the current and next generation of water-cooled fission reactors are centered on two structural materials aging degradation issues (corrosion and stress corrosion cracking of structural materials and neutron-induced embrittlement of reactor pressure vessels), along with improved fuel system reliability and accident tolerance issues. The major corrosion and stress corrosion cracking degradation mechanisms for light water reactors are reviewed. The materials degradation issues for the Zr alloy clad UO2 fuel system currently utilized in the majority of commercial nuclear power plants is discussed for normal and off-normal operating conditions. Looking to proposed future (Generation IV) fission and fusion energy systems, there are 5 key bulk radiation degradation effects (low temperature radiation hardening and embrittlement, radiation-induced and modified solute segregation and phase stability, irradiation creep, void swelling, and high temperature helium embrittlement) and a multitude of corrosion and stress corrosion cracking effects (including irradiation-assisted phenomena) that can have a major impact on the performance of structural materials.

  8. MATERIALS MANAGEMENT MATERIALS MANAGEMENT -INVENTORY CONTROL

    E-Print Network [OSTI]

    Oliver, Douglas L.

    MATERIALS MANAGEMENT MATERIALS MANAGEMENT - INVENTORY CONTROL NOTICE OF DESIGNATED DEPARTMENTAL OF MATERIALS MANAGEMENT ______ FURTHER INSTRUCTIONS 1. Include a copy of any relevant documents. 2. Item MATERIALS COORDINATOR ­ IC-8 Mail, Fax or PDF the entire package to: MC 2010 Fax: 679-4240 REFERENCE # DMC

  9. Thermal test options

    SciTech Connect (OSTI)

    Koski, J.A.; Keltner, N.R.; Sobolik, K.B.

    1993-02-01T23:59:59.000Z

    Shipping containers for radioactive materials must be qualified to meet a thermal accident environment specified in regulations, such at Title 10, Code of Federal Regulations, Part 71. Aimed primarily at the shipping container design, this report discusses the thermal testing options available for meeting the regulatory requirements, and states the advantages and disadvantages of each approach. The principal options considered are testing with radiant heat, furnaces, and open pool fires. The report also identifies some of the facilities available and current contacts. Finally, the report makes some recommendations on the appropriate use of these different testing methods.

  10. Strategic Biomass Solutions (Mississippi)

    Broader source: Energy.gov [DOE]

    The Strategic Biomass Solutions (SBS) was formed by the Mississippi Technology Alliance in June 2009. The purpose of the SBS is to provide assistance to existing and potential companies, investors...

  11. Solution to Quiz 1

    E-Print Network [OSTI]

    jeffb_000

    2014-01-14T23:59:59.000Z

    Sep 5, 2013 ... over the next four years: Cash Flow at End of Year Amount of Cash Flow. 1. 1 Million. 2 ... project is 8%. Calculate X . Solution: By definition, the ...

  12. Method for dispersing catalyst onto particulate material

    DOE Patents [OSTI]

    Utz, Bruce R. (Pittsburgh, PA); Cugini, Anthony V. (Pittsburgh, PA)

    1992-01-01T23:59:59.000Z

    A method for dispersing finely divided catalyst precursors onto the surface of coal or other particulate material includes the steps of forming a wet paste mixture of the particulate material and a liquid solution containing a dissolved transition metal salt, for instance a solution of ferric nitrate. The wet paste mixture is in a state of incipient wetness with all of this solution adsorbed onto the surfaces of the particulate material without the presence of free moisture. On adding a precipitating agent such as ammonia, a catalyst precursor such as hydrated iron oxide is deposited on the surfaces of the coal. The catalyst is activated by converting it to the sulfide form for the hydrogenation or direct liquefaction of the coal.

  13. Solutions of Penrose's Equation

    E-Print Network [OSTI]

    E. N. Glass; Jonathan Kress

    1998-09-27T23:59:59.000Z

    The computational use of Killing potentials which satisfy Penrose's equation is discussed. Penrose's equation is presented as a conformal Killing-Yano equation and the class of possible solutions is analyzed. It is shown that solutions exist in spacetimes of Petrov type O, D or N. In the particular case of the Kerr background, it is shown that there can be no Killing potential for the axial Killing vector.

  14. Stability of Molten Core Materials

    SciTech Connect (OSTI)

    Layne Pincock; Wendell Hintze

    2013-01-01T23:59:59.000Z

    The purpose of this report is to document a literature and data search for data and information pertaining to the stability of nuclear reactor molten core materials. This includes data and analysis from TMI-2 fuel and INL’s LOFT (Loss of Fluid Test) reactor project and other sources.

  15. REPORT NO. 5 background material

    E-Print Network [OSTI]

    of atmospheric testing of nuclear weapons in 1961 and 1962 the question arose as to the possible need for protec from such events as: (1) an industrial accident, possibly involving a nuclear reactor or a nuclear fuel processing plant, and (2) release of radioactive materials from the detonation of nuclear weapons or other

  16. Progress in Fusion Materials Research

    E-Print Network [OSTI]

    reactors ­ Qualification requires all of the mechanical property testing on unirradiated material, plus. Koizumi et al., Proc. Int. Gas Turbines Conf., 2003, paper TS-119 #12;6 Managed by UT-Battelle for the U is strongly dependent on annealing conditions FHR: fast heating rate (>1000°C/min) SFR: slow heating rate (10

  17. Course Title: Material and Energy Balances Instructor: Nader Aderangi

    E-Print Network [OSTI]

    Heller, Barbara

    1 CHE 202 Fall 2012 Course Title: Material and Energy Balances Instructor: Nader Aderangi Phone:25 AM ­ 12:40 PM Objective: To develop skills of material and energy balances for physical and chemical solution. 3. To provide students the basic concepts to formulate and solve material balances, energy

  18. Prematurely terminated slug tests

    SciTech Connect (OSTI)

    Karasaki, K. (Lawrence Berkeley Lab., CA (USA))

    1990-07-01T23:59:59.000Z

    A solution of the well response to a prematurely terminated slug test (PTST) is presented. The advantages of a PTST over conventional slug tests are discussed. A systematized procedure of a PTST is proposed, where a slug test is terminated in the midpoint of the flow point, and the subsequent shut-in data is recorded and analyzed. This method requires a downhole shut-in device and a pressure transducer, which is no more than the conventional deep-well slug testing. As opposed to slug tests, which are ineffective when a skin is present, more accurate estimate of formation permeability can be made using a PTST. Premature termination also shortens the test duration considerably. Because in most cases no more information is gained by completing a slug test to the end, the author recommends that conventional slug tests be replaced by the premature termination technique. This study is part of an investigation of the feasibility of geologic isolation of nuclear wastes being carried out by the US Department of Energy and the National Cooperative for the Storage of Radioactive Waste of Switzerland.

  19. Method for forming materials

    DOE Patents [OSTI]

    Tolle, Charles R. (Idaho Falls, ID); Clark, Denis E. (Idaho Falls, ID); Smartt, Herschel B. (Idaho Falls, ID); Miller, Karen S. (Idaho Falls, ID)

    2009-10-06T23:59:59.000Z

    A material-forming tool and a method for forming a material are described including a shank portion; a shoulder portion that releasably engages the shank portion; a pin that releasably engages the shoulder portion, wherein the pin defines a passageway; and a source of a material coupled in material flowing relation relative to the pin and wherein the material-forming tool is utilized in methodology that includes providing a first material; providing a second material, and placing the second material into contact with the first material; and locally plastically deforming the first material with the material-forming tool so as mix the first material and second material together to form a resulting material having characteristics different from the respective first and second materials.

  20. Nuclear Materials Management Program at the NNSS

    SciTech Connect (OSTI)

    ,

    2012-06-08T23:59:59.000Z

    The Nevada National Security Site (NNSS), formerly the Nevada Test Site, was established in 1951 mainly for weapons testing; because special nuclear materials (SNM) were expended during the tests, a nuclear material management program was not required. That changed in December 2004 with the receipt of Category I SNM for purposes other than weapons testing. At that time, Material Control and Accountability and Nuclear Material Management were a joint laboratory (Los Alamos and Lawrence Livermore) effort with nuclear material management being performed at the laboratories. That changed in March 2006 when the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office appointed sole responsibility to the Management and Operations (M&O) contractor, National Security Technologies, LLC (NSTec). Since 2006 the basic nuclear material management work was completed by a combination of M&O employees and subcontractors, but a true Nuclear Material Management (NMM) Program was not determined to be necessary until recently. With expanding missions and more nuclear material (NM) coming to the NNSS, it became imperative to have an organization to manage these materials; therefore, an NMM Manager was officially appointed by NSTec in 2012. In June 2011 a Gap Analysis and white paper was completed by a subcontractor; this presentation will include highlights from those documents along with our plans to resolve the “gaps” and stand up a functional and compliant NMM Program at the NNSS.

  1. 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)

  2. Final Technical Report - Investigation into the Relationship between Heterogeneity and Heavy-Tailed Solute Transport

    SciTech Connect (OSTI)

    Weissmann, Gary S

    2013-12-06T23:59:59.000Z

    The objective of this project was to characterize the influence that naturally complex geologic media has on anomalous dispersion and to determine if the nature of dispersion can be estimated from the underlying heterogeneous media. The UNM portion of this project was to provide detailed representations of aquifer heterogeneity through producing highly-resolved models of outcrop analogs to aquifer materials. This project combined outcrop-scale heterogeneity characterization (conducted at the University of New Mexico), laboratory experiments (conducted at Sandia National Laboratory), and numerical simulations (conducted at Sandia National Laboratory and Colorado School of Mines). The study was designed to test whether established dispersion theory accurately predicts the behavior of solute transport through heterogeneous media and to investigate the relationship between heterogeneity and the parameters that populate these models. The dispersion theory tested by this work was based upon the fractional advection-dispersion equation (fADE) model. Unlike most dispersion studies that develop a solute transport model by fitting the solute transport breakthrough curve, this project explored the nature of the heterogeneous media to better understand the connection between the model parameters and the aquifer heterogeneity. We also evaluated methods for simulating the heterogeneity to see whether these approaches (e.g., geostatistical) could reasonably replicate realistic heterogeneity. The UNM portion of this study focused on capturing realistic geologic heterogeneity of aquifer analogs using advanced outcrop mapping methods.

  3. Alkaline earth cation extraction from acid solution

    DOE Patents [OSTI]

    Dietz, Mark (Elmhurst, IL); Horwitz, E. Philip (Naperville, IL)

    2003-01-01T23:59:59.000Z

    An extractant medium for extracting alkaline earth cations from an aqueous acidic sample solution is described as are a method and apparatus for using the same. The separation medium is free of diluent, free-flowing and particulate, and comprises a Crown ether that is a 4,4'(5')[C.sub.4 -C.sub.8 -alkylcyclohexano]18-Crown-6 dispersed on an inert substrate material.

  4. Crystallization and functionality of inorganic materials

    SciTech Connect (OSTI)

    Xue, Dongfeng, E-mail: dongfeng@ciac.jl.cn [State Key Laboratory of Rare Earth Resource Utilization, Changchun Institute of Applied Chemistry, Chinese Academy of Sciences, Changchun 130022 (China) [State Key Laboratory of Rare Earth Resource Utilization, Changchun Institute of Applied Chemistry, Chinese Academy of Sciences, Changchun 130022 (China); School of Chemical Engineering, Dalian University of Technology, Dalian 116024 (China); Li, Keyan [School of Chemical Engineering, Dalian University of Technology, Dalian 116024 (China)] [School of Chemical Engineering, Dalian University of Technology, Dalian 116024 (China); Liu, Jun [Key Laboratory of Low Dimensional Materials and Application Technology, Ministry of Education, Faculty of Materials, Optoelectronics and Physics, Xiangtan University, 411105 (China)] [Key Laboratory of Low Dimensional Materials and Application Technology, Ministry of Education, Faculty of Materials, Optoelectronics and Physics, Xiangtan University, 411105 (China); Sun, Congting; Chen, Kunfeng [State Key Laboratory of Rare Earth Resource Utilization, Changchun Institute of Applied Chemistry, Chinese Academy of Sciences, Changchun 130022 (China) [State Key Laboratory of Rare Earth Resource Utilization, Changchun Institute of Applied Chemistry, Chinese Academy of Sciences, Changchun 130022 (China); School of Chemical Engineering, Dalian University of Technology, Dalian 116024 (China)

    2012-10-15T23:59:59.000Z

    In this article, we briefly summarized our recent work on the studies of crystallization and functionality of inorganic materials. On the basis of the chemical bonding theory of single crystal growth, we can quantitatively simulate Cu{sub 2}O crystallization processes in solution system. We also kinetically controlled Cu{sub 2}O crystallization process in the reduction solution route. Lithium ion battery and supercapacitor performances of some oxides such as Co{sub 3}O{sub 4} and MnO{sub 2} were shown to elucidate the important effect of crystallization on functionality of inorganic materials. This work encourages us to create novel functionalities through the study of crystallization of inorganic materials, which warrants more chances in the field of functional materials.

  5. LWRS ATR Irradiation Testing Readiness Status

    SciTech Connect (OSTI)

    Kristine Barrett

    2012-09-01T23:59:59.000Z

    The Light Water Reactor Sustainability (LWRS) Program was established by the U.S. Department of Energy Office of Nuclear Energy (DOE-NE) to develop technologies and other solutions that can improve the reliability, sustain the safety, and extend the life of the current reactors. The LWRS Program is divided into four R&D Pathways: (1) Materials Aging and Degradation; (2) Advanced Light Water Reactor Nuclear Fuels; (3) Advanced Instrumentation, Information and Control Systems; and (4) Risk-Informed Safety Margin Characterization. This report describes an irradiation testing readiness analysis in preparation of LWRS experiments for irradiation testing at the Idaho National Laboratory (INL) Advanced Test Reactor (ATR) under Pathway (2). The focus of the Advanced LWR Nuclear Fuels Pathway is to improve the scientific knowledge basis for understanding and predicting fundamental performance of advanced nuclear fuel and cladding in nuclear power plants during both nominal and off-nominal conditions. This information will be applied in the design and development of high-performance, high burn-up fuels with improved safety, cladding integrity, and improved nuclear fuel cycle economics

  6. Method of making carbon nanotube composite materials

    DOE Patents [OSTI]

    O'Bryan, Gregory; Skinner, Jack L; Vance, Andrew; Yang, Elaine Lai; Zifer, Thomas

    2014-05-20T23:59:59.000Z

    The present invention is a method of making a composite polymeric material by dissolving a vinyl thermoplastic polymer, un-functionalized carbon nanotubes and hydroxylated carbon nanotubes and optionally additives in a solvent to make a solution and removing at least a portion of the solvent after casting onto a substrate to make thin films. The material has enhanced conductivity properties due to the blending of the un-functionalized and hydroxylated carbon nanotubes.

  7. Geothermal: Sponsored by OSTI -- A closed-form analytical solution...

    Office of Scientific and Technical Information (OSTI)

    A closed-form analytical solution for thermal single-well injection withdrawal tests Geothermal Technologies Legacy Collection HelpFAQ | Site Map | Contact Us HomeBasic Search...

  8. 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

  9. Senior Systems Analyst-PeopleSoft Campus Solutions Posting Details

    E-Print Network [OSTI]

    Liblit, Ben

    and emerging technologies. This position may lead and coordinate the design, development, and implementation assurance and testing activities required to maintain business solutions. This position reportsSenior Systems Analyst-PeopleSoft Campus Solutions Posting Details Posting Details Position Title

  10. Material Selection and Characterization for High Gradient RF Applications

    E-Print Network [OSTI]

    Arnau-Izquierdo, G; Heikkinen, S; Ramsvik, T; Sgobba, Stefano; Taborelli, M; Wuensch, W

    2007-01-01T23:59:59.000Z

    The selection of candidate materials for the accelerating cavities of the Compact Linear Collider (CLIC) is carried out in parallel with high power RF testing. The maximum DC breakdown field of copper, copper alloys, refractory metals, aluminium and titanium have been measured with a dedicated setup. Higher maximum fields are obtained for refractory metals and for titanium, which exhibits, however, important damages after conditioning. Fatigue behaviour of copper alloys has been studied for surface and bulk by pulsed laser irradiation and ultrasonic excitation, respectively. The selected copper alloys show consistently higher fatigue resistance than copper in both experiments. In order to obtain the best local properties in the device a possible solution is a bi-metallic assembly. Junctions of molybdenum and copper-zirconium UNS C15000 alloy, achieved by HIP (Hot Isostatic Pressing) diffusion bonding or explosion bonding were evaluated for their mechanical strength. The reliability of the results obtained wit...

  11. FireWise Construction: Site Design & Building Materials

    E-Print Network [OSTI]

    FireWise Construction: Site Design & Building Materials Based on the 2009 International Wildland for Testing and Materials (ASTM) committees that develop standards on the performance of materials in fire and water consumption, and the use of appropriate, resource-conserving materials. Peter developed the first

  12. Transporting particulate material

    DOE Patents [OSTI]

    Aldred, Derek Leslie (North Hollywood, CA); Rader, Jeffrey A. (North Hollywood, CA); Saunders, Timothy W. (North Hollywood, CA)

    2011-08-30T23:59:59.000Z

    A material transporting system comprises a material transporting apparatus (100) including a material transporting apparatus hopper structure (200, 202), which comprises at least one rotary transporting apparatus; a stationary hub structure (900) constraining and assisting the at least one rotary transporting apparatus; an outlet duct configuration (700) configured to permit material to exit therefrom and comprising at least one diverging portion (702, 702'); an outlet abutment configuration (800) configured to direct material to the outlet duct configuration; an outlet valve assembly from the material transporting system venting the material transporting system; and a moving wall configuration in the material transporting apparatus capable of assisting the material transporting apparatus in transporting material in the material transporting system. Material can be moved from the material transporting apparatus hopper structure to the outlet duct configuration through the at least one rotary transporting apparatus, the outlet abutment configuration, and the outlet valve assembly.

  13. Americium/Curium Vitrification Pilot Tests - Part II

    SciTech Connect (OSTI)

    Marra, J.E. [Westinghouse Savannah River Company, AIKEN, SC (United States); Baich, M.A.; Fellinger, A.P.; Hardy, B.J.; Herman, D.T.; Jones, T.M.; Miller, C.B.; Miller, D.H.; Snyder, T. K.; Stone, M.E.

    1998-05-01T23:59:59.000Z

    Isotopes of americium (Am) and curium (Cm) were produced in the past at the Savannah River Site (SRS) for research, medical, and radiological applications. These highly radioactive and valuable isotopes have been stored in an SRS reprocessing facility for a number of years. Vitrification of this solution will allow the material to be more safely stored until it is transported to the DOE Oak Ridge Reservation for use in research and medical applications. A previous paper described operation results from the Am-Cm Melter 2A pilot system, a full-scale non-radioactive pilot facility. This paper presents the results from continued testing in the Pilot Facility and also describes efforts taken to look at alternative vitrification process operations and flowsheets designed to address the problems observed during melter 2A pilot testing.

  14. Nuclear Materials Management U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO)

    SciTech Connect (OSTI)

    Jesse Schreiber

    2008-03-01T23:59:59.000Z

    In light of the changing Defense Complex mission, the high cost to storing and protecting nuclear materials, and in consideration of scarcity of resources, it is imperative that the U.S. Department of Energy (DOE) owned nuclear materials are managed effectively. The U.S. Department of Energy, National Nuclear Security Administration (NNSA) Strategic Action Plan outlines the strategy for continuing to meet America’s nuclear security goals, meeting the overall mission challenges of DOE and NNSA as well as giving focus to local missions. The mission of the NNSA/NSO Nuclear Materials Management (NMM) Program is to ensure that nuclear material inventories are accurately assessed and reported, future material needs are adequately planned, and that existing Nevada Test Site (NTS) inventories are efficiently utilized, staged, or dispositioned. The NNSA/NSO understands that the NTS has unique characteristics to serve and benefit the nation with innovative solutions to the complex problems involving Special Nuclear Materials, hazardous materials, and multi-agency, integrated operations. The NNSA/NSO is defining infrastructure requirements for known future missions, developing footprint consolidation strategic action plans, and continuing in the path of facility modernization improvements. The NNSA/NSO is striving for the NTS to be acknowledged as an ideal location towards mission expansion and growth. The NTS has the capability of providing isolated, large scale construction and development locations for nuclear power or alternate energy source facilities, expanded nuclear material storage sites, and for new development in “green” technology.

  15. Nuclear Materials Management U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO)

    SciTech Connect (OSTI)

    Jesse Schrieber

    2008-07-01T23:59:59.000Z

    In light of the changing Defense Complex mission, the high cost to storing and protecting nuclear materials, and in consideration of scarcity of resources, it is imperative that the U.S. Department of Energy (DOE) owned nuclear materials are managed effectively. The U.S. Department of Energy, National Nuclear Security Administration (NNSA) Strategic Action Plan outlines the strategy for continuing to meet America’s nuclear security goals, meeting the overall mission challenges of DOE and NNSA as well as giving focus to local missions. The mission of the NNSA/NSO Nuclear Materials Management (NMM) Program is to ensure that nuclear material inventories are accurately assessed and reported, future material needs are adequately planned, and that existing Nevada Test Site (NTS) inventories are efficiently utilized, staged, or dispositioned. The NNSA/NSO understands that the NTS has unique characteristics to serve and benefit the nation with innovative solutions to the complex problems involving Special Nuclear Materials, hazardous materials, and multi-agency, integrated operations. The NNSA/NSO is defining infrastructure requirements for known future missions, developing footprint consolidation strategic action plans, and continuing in the path of facility modernization and improvements. The NNSA/NSO is striving for the NTS to be acknowledged as an ideal location towards mission expansion and growth. The NTS has the capability of providing isolated, large scale construction and development locations for nuclear power or alternate energy source facilities, expanded nuclear material storage sites, and for new development in “green” technology.

  16. Offshore Renewable Energy Solutions

    E-Print Network [OSTI]

    power ­ to meet its target of achieving 15% of energy consumption from renewable sources by 2020. CefasOffshore Renewable Energy Solutions #12;Cefas: meeting complex requirements The Centre and maximise resource input on field and lab-based studies ­ saving you time and money.Recognised expertise

  17. Microrheological Characterisation of Anisotropic Materials

    E-Print Network [OSTI]

    I A Hasnain; A M Donald

    2006-03-03T23:59:59.000Z

    We describe the measurement of anisotropic viscoelastic moduli in complex soft materials, such as biopolymer gels, via video particle tracking microrheology of colloid tracer particles. The use of a correlation tensor to find the axes of maximum anisotropy, and hence the mechanical director, is described. The moduli of an aligned DNA gel are reported, as a test of the technique; this may have implications for high DNA concentrations in vivo. We also discuss the errors in microrheological measurement, and describe the use of frequency space filtering to improve displacement resolution, and hence probe these typically high modulus materials.

  18. Microbial Fuel Cell Using Inexpensive Materials

    E-Print Network [OSTI]

    Microbial Fuel Cell Using Inexpensive Materials Group #4 Peter McAveney Brett Pedersen Jun-Chung Wong #12;Abstract We built and tested a microbial fuel cell using low-cost materials. Our intention- critical applications such as transportation. Microbial fuel cells cannot achieve comparable power

  19. Material model library for explicit numerical codes

    SciTech Connect (OSTI)

    Hofmann, R.; Dial, B.W.

    1982-08-01T23:59:59.000Z

    A material model logic structure has been developed which is useful for most explicit finite-difference and explicit finite-element Lagrange computer codes. This structure has been implemented and tested in the STEALTH codes to provide an example for researchers who wish to implement it in generically similar codes. In parallel with these models, material parameter libraries have been created for the implemented models for materials which are often needed in DoD applications.

  20. Friction of Materials for Automotive Applications

    SciTech Connect (OSTI)

    Blau, Peter Julian [ORNL

    2013-01-01T23:59:59.000Z

    This brief overview of friction-related issues in materials for automobiles is invited for a special issue on automotive materials in the ASM journal AM&P. It describes a range of areas in a ground vehicle in which friction must be controlled or minimized. Applications range from piston rings to tires, and from brakes to fuel injector components. A perspective on new materials and lubricants, and the need for validation testing is presented.

  1. Active, polymer-based composite material implementing simple shear

    E-Print Network [OSTI]

    Lee, Sang Jin

    2009-05-15T23:59:59.000Z

    A novel active material for controllable, high work density applications was designed, fabricated, analyzed, and tested. This active material uses a lens-shaped element to implement simple shear motion with gas pressure actuation. The lens element...

  2. Liquid-Air Interface Corrosion Testing Simulating The Environment Of Hanford Double Shell Tanks

    SciTech Connect (OSTI)

    Wiersma, B.; Gray, J. R.; Garcia-Diaz, B. L.; Murphy, T. H.; Hicks, K. R.

    2014-01-30T23:59:59.000Z

    Coupon tests on A537 carbon steel materials were conducted to evaluate the Liquid-Air Interface (LAI) corrosion susceptibility in a series of solutions designed to simulate conditions in the radioactive waste tanks located at the Hanford Nuclear Facility. The new stress corrosion cracking requirements and the impact of ammonia on LAI corrosion were the primary focus. The minimum R value (i.e., molar ratio of nitrite to nitrate) of 0.15 specified by the new stress corrosion cracking requirements was found to be insufficient to prevent pitting corrosion at the LAI. The pH of the test solutions was 10, which was actually less than the required pH 11 defined by the new requirements. These tests examined the effect of the variation of the pH due to hydroxide depletion at the liquid air interface. The pits from the current testing ranged from 0.001 to 0.008 inch in solutions with nitrate concentrations of 0.4 M and 2.0 M. The pitting and general attack that occurred progressed over the four-months. No significant pitting was observed, however, for a solution with a nitrate concentration of 4.5 M. The pitting depths observed in these partial immersion tests in unevaporated condensates ranged from 0.001 to 0.005 inch after 4 months. The deeper pits were in simulants with low R values. Simulants with R values of approximately 0.6 to 0.8 appeared to significantly reduce the degree of attack. Although, the ammonia did not completely eliminate attack at the LAI, the amount of corrosion in an extremely corrosive solution was significantly reduced. Only light general attack (< 1 mil) occurred on the coupon in the vicinity of the LAI. The concentration of ammonia (i.e., 50 ppm or 500 ppm) did not have a strong effect.

  3. MA373 S12 Test 4 Solutions.pdf

    E-Print Network [OSTI]

    Owner

    2014-05-01T23:59:59.000Z

    May 1, 2012 ... (6 points) The current spot price of the stock of Johnson Corporation is .... Profit =

  4. Corrosion Testing of Carbon Steel in Acid Cleaning Solutions

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed Newcatalyst phases on &gamma;-Al2O3. |ID#: 19834 Title: Correlation ofBurn89

  5. MODELING OF A NOVEL SOLUTION POTASH MINING PROCESS Sergio Almada, Harvey Haugen

    E-Print Network [OSTI]

    by drilling followed by a number of steps to develop a solution mining cavern. Water is injected to dissolve a sump area within the salt at the base of the solution mining cavern. The sump allows insoluble materials settle within the cavern to avoid affecting the solution mining process and the dissolved salt can

  6. MATERIAL COMPATIBILITY EVALUATION FOR DWPF NITRIC-GLYCOLIC ACID - LITERATURE REVIEW

    SciTech Connect (OSTI)

    Mickalonis, J.; Skidmore, E.

    2013-06-05T23:59:59.000Z

    Glycolic acid is being evaluated as an alternative for formic and nitric acid in the DWPF flowsheet. Demonstration testing and modeling for this new flowsheet has shown that glycolic acid and glycolate has a potential to remain in certain streams generated during the production of the nuclear waste glass. A literature review was conducted to assess the impact of glycolic acid on the corrosion of the materials of construction for the DWPF facility as well as facilities downstream which may have residual glycolic acid and glycolates present. The literature data was limited to solutions containing principally glycolic acid. The reported corrosion rates and degradation characteristics have shown the following for the materials of construction. ? For C276 alloy, the primary material of construction for the CPC vessels, corrosion rates of either 2 or 20 mpy were reported up to a temperature of 93 ?C. ? For the austenitic stainless steels, 304L and 316L, variable rates were reported over a range of temperatures, varying from 2 mpy up to 200 mpy (at 100 ?C). ? For 690, G30, Allcorr, Ultimet and Stellite alloys no data were available. ? For relevant polymers where data are available, the data suggests that exposure to glycolic acid is not detrimental. The literature data had limited application to the DWPF process since only the storage and feed vessels, pumps and piping used to handle the glycolic acid are directly covered by the available data. These components are either 304L or 316L alloys for which the literature data is inconsistent (See Bullet 2 above). Corrosion rates in pure glycolic acid solutions also are not representative of the DWPF process streams. This stream is complex and contains aggressive species, i.e. chlorides, sulfates, mercury, as well as antifoaming agents which cumulatively have an unknown effect on the corrosion rates of the materials of construction. Therefore, testing is recommended to investigate any synergistic effects of the aggressive species and to verify the performance of materials in the key process vessels as well as downstream vessels and processes such as the evaporator where heating is occurring. The following testing would provide data for establishing the viability of these components. ? Electrochemical testing - evaluate the corrosion rate and susceptibility to localized corrosion within the SRAT, SME, OGCT, Quencher and Evaporator. Testing would be conducted at operational temperatures in simulants with ranges of glycolic acid, iron, chloride, sulfate, mercury, and antifoaming agents. ? Hot-wall testing – evaluate the corrosion under heat transfer conditions to simulate those for heating coils and evaporator coil surfaces. Testing would be at nominal chemistries with concentration of glycolic acid, chloride, sulfate and mercury at high expected concentrations. Some tests would be performed with antifoaming agents. ? Melter coupon testing – evaluate the performance of alloy 690 in melter feeds containing glycolic acid. This testing would be conducted as part of the melter flammability testing. ? Polymer testing – evaluate changes in polymer properties in immersion testing with DWPF simulants to provide product-specific data for service life evaluation and analyze the Hansen solubility parameters for relevant polymers in glycolic vs. formic acid. During this literature review process, the difficulties associated with measuring the liquid level in formic acid tanks were revealed. A test is recommended to resolve this issue prior to the introduction of glycolic acid into the DWPF. This testing would evaluate the feasibility of using ultrasonic inspection techniques to determine liquid level and other desirable attributes of glycolic acid in DWPF storage tanks and related equipment.

  7. Better Buildings Residential Program Solution Center Demonstration...

    Energy Savers [EERE]

    Better Buildings Residential Program Solution Center Demonstration Better Buildings Residential Program Solution Center Demonstration Better Buildings Residential Program Solution...

  8. Nanostructured magnetic materials

    E-Print Network [OSTI]

    Chan, Keith T.

    2011-01-01T23:59:59.000Z

    Magnetism and Magnetic Materials Conference, Atlanta, GA (Nanostructured Magnetic Materials by Keith T. Chan Doctor ofinduced by a Si-based material occurs at a Si/Ni interface

  9. Asbestos-free brake-lining materials for hydrogenerators

    SciTech Connect (OSTI)

    Lalonde, S.; Lanteigne, J. [Hydro-Quebec, Varennes, Quebec (Canada)

    1995-11-01T23:59:59.000Z

    Three different asbestos-free materials currently considered as new lining materials for hydrogenerator brakes were tested and compared to the original asbestos lining. Results show that these substitutes not only vary greatly from the original material in terms of mechanical properties and physical characteristics but also exhibit significantly different performances in braking tests. Consequently, these new materials are not entirely suitable for the intended application.

  10. Paper Machine Is it the material

    E-Print Network [OSTI]

    Das, Suman

    (dezincification) 7. Erosion corrosion 8. Microbiologically influenced corrosion 9. Stress-corrosion cracking Forms ­ Galvanic corrosion is the principle behind all batteries ­ There is a potential difference (voltage) between dissimilar materials immersed in a conductive solution Alkaline batteries are copper and nickel

  11. 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.

  12. MATERIALS TRANSFER AGREEMENT

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

    MTAXX-XXX 1 MATERIAL TRANSFER AGREEMENT for Manufacturing Demonstration Facility and Carbon Fiber Technology Facility In order for the RECIPIENT to obtain materials, the RECIPIENT...

  13. battery materials | EMSL

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

    battery materials battery materials Leads No leads are available at this time. Modeling Interfacial Glass-Water Reactions: Recent Advances and Current Limitations. Abstract: The...

  14. Energy Materials & Processes | EMSL

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

    in catalysts and energy materials needed to design new materials and systems for sustainable energy applications. By facilitating the development and rapid dissemination...

  15. Injection nozzle materials for a coal-fueled diesel locomotive

    SciTech Connect (OSTI)

    Mehan, R.L.; Leonard, G.L.; Johnson, R.N.; Lavigne, R.G.

    1990-12-31T23:59:59.000Z

    In order to identify materials resistant to coal water mixture (CWM) erosive wear, a number of materials were evaluated using both orifice slurry and dry air erosion tests. Both erosion tests ranked materials in the same order, and the most erosion resistant material identified was sintered diamond compact. Based on operation using CWM in a single-cylinder locomotive test, superhard nozzle materials such as diamond, cubic boron nitride, and perhaps TiB{sub 2} were found to be necessary in order to obtain a reasonable operating life. An injection nozzle using sintered diamond compacts was designed and built, and has operated successfully in a CWM fired locomotive engine.

  16. TESTING OF NOVEL INORGANIC ION EXCHANGERS FOR THE REMOVAL OF RADIOCOBALT FROM NPP WASTE EFFLUENTS

    SciTech Connect (OSTI)

    Harjula, R.; Paajanen, A.; Mueller, T.; Lehto, J.

    2002-02-25T23:59:59.000Z

    New antimonysilicate (SbSi) ion exchanger is being developed for industrial use. Tentative screening tests using simulated waste liquids have indicated that this material can remove most key radionuclides such as {sup 60}Co, {sup 90}Sr and {sup 137}Cs in much broader pH-range than existing commercial materials. As a part of the development program, the material is being tested for the removal of {sup 60}Co from real nuclear power plant waste waters. In this context, test with small-scale laboratory columns (bed volume 0.5 mL) have been carried out using a Floor Drain water samples from Ginna NPP and Diablo Canyon NPP, USA. More than 90% of {sup 60}Co in these liquids was removable by mechanical filtration (0.45 {micro}m). SbSi columns removed more than 90% of the soluble {sup 60}Co that was left in the solutions after filtration. The tests were discontinued when about 2000 bed volumes were treated due to depletion of test liquids with no sign of column exhaustion.

  17. Sandia National Laboratories: Hydrogen Effects on Materials Laboratory

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

    of -70 C to 170 C. The material properties measured are the crack velocity and subcritical cracking threshold. Dynamic-load Testing - Specimens are exposed to gaseous...

  18. Standard Test Method for Sandwich Corrosion Test

    E-Print Network [OSTI]

    American Society for Testing and Materials. Philadelphia

    2009-01-01T23:59:59.000Z

    1.1 This test method defines the procedure for evaluating the corrosivity of aircraft maintenance chemicals, when present between faying surfaces (sandwich) of aluminum alloys commonly used for aircraft structures. This test method is intended to be used in the qualification and approval of compounds employed in aircraft maintenance operations. 1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information. 1.3 This standard may involve hazardous materials, operations, and equipment. This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. Specific hazard statements appear in Section 9.

  19. Technical solutions to nonproliferation challenges

    SciTech Connect (OSTI)

    Satkowiak, Lawrence [Director, Nonproliferation, Safeguards and Security Programs, Oak Ridge National Laboratory, Oak Ridge, Tennessee (United States)

    2014-05-09T23:59:59.000Z

    The threat of nuclear terrorism is real and poses a significant challenge to both U.S. and global security. For terrorists, the challenge is not so much the actual design of an improvised nuclear device (IND) but more the acquisition of the special nuclear material (SNM), either highly enriched uranium (HEU) or plutonium, to make the fission weapon. This paper provides two examples of technical solutions that were developed in support of the nonproliferation objective of reducing the opportunity for acquisition of HEU. The first example reviews technologies used to monitor centrifuge enrichment plants to determine if there is any diversion of uranium materials or misuse of facilities to produce undeclared product. The discussion begins with a brief overview of the basics of uranium processing and enrichment. The role of the International Atomic Energy Agency (IAEA), its safeguard objectives and how the technology evolved to meet those objectives will be described. The second example focuses on technologies developed and deployed to monitor the blend down of 500 metric tons of HEU from Russia's dismantled nuclear weapons to reactor fuel or low enriched uranium (LEU) under the U.S.-Russia HEU Purchase Agreement. This reactor fuel was then purchased by U.S. fuel fabricators and provided about half the fuel for the domestic power reactors. The Department of Energy established the HEU Transparency Program to provide confidence that weapons usable HEU was being blended down and thus removed from any potential theft scenario. Two measurement technologies, an enrichment meter and a flow monitor, were combined into an automated blend down monitoring system (BDMS) and were deployed to four sites in Russia to provide 24/7 monitoring of the blend down. Data was downloaded and analyzed periodically by inspectors to provide the assurances required.

  20. Evaporation of Enriched Uranium Solutions Containing Organophosphates

    SciTech Connect (OSTI)

    Pierce, R.A.

    1999-03-18T23:59:59.000Z

    The Savannah River Site has enriched uranium (EU) solution which has been stored for almost 10 years since being purified in the second uranium cycle of the H area solvent extraction process. The preliminary SRTC data, in conjunction with information in the literature, is promising. However, very few experiments have been run, and none of the results have been confirmed with repeat tests. As a result, it is believed that insufficient data exists at this time to warrant Separations making any process or program changes based on the information contained in this report. When this data is confirmed in future testing, recommendations will be presented.

  1. Evaporation/ Solution Droplet

    E-Print Network [OSTI]

    Suslick, Kenneth S.

    · Nano-Catalysts · Fine Powders · Spray Drying MoO3 As prepared initially. After thermal annealing at 350oC. Hollow Spheres and Crystals 1st Hollow Crystals! Cooling bath Titanium Horn Collar & O-Rings Gas Production of Nano-Materials microporous shell internal macropores Hierarchically Porous Carbons Brandon Ito

  2. A method of cobalt ion concentration from dilute aqueous solutions

    SciTech Connect (OSTI)

    Amanatidou, E. [Technological Education Inst., Kila Kozanis (Greece); Stefanut, M.N.; Grozav, A. [Institute for Chemical and Technological Sciences, Timisoara (Romania)

    1996-03-01T23:59:59.000Z

    The liquid membrane technique is very useful for metal ions recovery from dilute solutions. Co{sup 2+} ions can be removed and concentrated from wastewaters with an emulsion liquid membrane. The paper describes the permeation of Co{sup 2+} using naphthenic acids as the carrier and kerosene as the membrane material. The inner phase is a HCl 3.162 x 10{sup -4} solution. The extraction yield is more than 96%.

  3. Coated ceramic breeder materials

    DOE Patents [OSTI]

    Tam, Shiu-Wing (Downers Grove, IL); Johnson, Carl E. (Elk Grove, IL)

    1987-01-01T23:59:59.000Z

    A breeder material for use in a breeder blanket of a nuclear reactor is disclosed. The breeder material comprises a core material of lithium containing ceramic particles which has been coated with a neutron multiplier such as Be or BeO, which coating has a higher thermal conductivity than the core material.

  4. HAZARDOUS MATERIALS EMERGENCY RESPONSE

    E-Print Network [OSTI]

    ANNEX Q HAZARDOUS MATERIALS EMERGENCY RESPONSE #12;ANNEX Q - HAZARDOUS MATERIALS EMERGENCY RESPONSE 03/10/2014 v.2.0 Page Q-1 PROMULGATION STATEMENT Annex Q: Hazardous Materials Emergency Response, and contents within, is a guide to how the University conducts a response specific to a hazardous materials

  5. UNDERGRADUATE Materials Science & Engineering

    E-Print Network [OSTI]

    Tipple, Brett

    UNDERGRADUATE HANDBOOK Materials Science & Engineering 2013 2014 #12;STUDYING FOR A MATERIALS SCIENCE AND ENGINEERING DEGREE Materials Science and Engineering inter-twines numerous disciplines that still gives the students the opportunity to study science while earning an engineering degree. Materials

  6. Materials Science & Engineering

    E-Print Network [OSTI]

    Simons, Jack

    Materials Science & Engineering The University of Utah 2014-15 Undergraduate Handbook #12;STUDYING FOR A MATERIALS SCIENCE AND ENGINEERING DEGREE Materials Science and Engineering inter-twines numerous disciplines that still gives the students the opportunity to study science while earning an engineering degree. Materials

  7. A Materials Facilities Initiative -

    E-Print Network [OSTI]

    A Materials Facilities Initiative - FMITS & MPEX D.L. Hillis and ORNL Team Fusion & Materials for Nuclear Systems Division July 10, 2014 #12;2 Materials Facilities Initiative JET ITER FNSF Fusion Reactor Challenges for materials: fluxes and fluence, temperatures 50 x divertor ion fluxes up to 100 x neutron

  8. Computational Chemical Materials Engineering

    E-Print Network [OSTI]

    : Thermal barrier coatings, wear resistance coatings, radiation resistant materials · Materials for opticalHome Computational Chemical and Materials Engineering Tahir Cagin Chemical Engineering Department to understand behavior and properties of materials as a function of ­ Chemical constitution ­ Composition

  9. Advanced Thermoelectric Materials and Generator Technology for Automotive Waste Heat at GM

    Broader source: Energy.gov [DOE]

    Overview of design, fabrication, integration, and test of working prototype TEG for engine waste heat recovery on Suburban test vehicle, and continuing investigation of skutterudite materials systems

  10. Implementation and Test of Numerical Optimization

    E-Print Network [OSTI]

    performance tests, and it is found that libopti is fast compared to scripting based solutions, and as much in its class. #12;ii #12;Summary (Danish) MĂĄlet for denne afhandling er at beskrive dobbelt-dimensional problems, their solution time is very large.[JN00] Because of this, optimization as we know it today did

  11. CRAD, Packaging and Transfer of Hazardous Materials and Materials...

    Office of Environmental Management (EM)

    CRAD, Packaging and Transfer of Hazardous Materials and Materials of National Security Interest Assessment Plan CRAD, Packaging and Transfer of Hazardous Materials and Materials of...

  12. Supporting Online Material Materials and Methods

    E-Print Network [OSTI]

    Wolfe, Cecily J.

    1 Supporting Online Material Materials and Methods (15) For all possible earthquake pairs. The parameters chosen for window length, filter bandpass, negative sidelobe identification, and cross-correlation threshold are appropriate for high-frequency earthquakes. In order to remove false positives or poor data

  13. SUPPORTING ONLINE MATERIAL Materials and Methods

    E-Print Network [OSTI]

    Newsome, William

    SUPPORTING ONLINE MATERIAL Materials and Methods Two adult male rhesus monkeys (Macaca mulatta with a head-holding device (S1), scleral search coil for monitoring eye position (S2) and a recording chamber monkeys remain actively engaged in experiments, so precise histological identification of recording sites

  14. Model simulation and experiments of flow and mass transport through a nano-material gas filter

    SciTech Connect (OSTI)

    Yang, Xiaofan; Zheng, Zhongquan C.; Winecki, Slawomir; Eckels, Steve

    2013-11-01T23:59:59.000Z

    A computational model for evaluating the performance of nano-material packed-bed filters was developed. The porous effects of the momentum and mass transport within the filter bed were simulated. For the momentum transport, an extended Ergun-type model was employed and the energy loss (pressure drop) along the packed-bed was simulated and compared with measurement. For the mass transport, a bulk dsorption model was developed to study the adsorption process (breakthrough behavior). Various types of porous materials and gas flows were tested in the filter system where the mathematical models used in the porous substrate were implemented and validated by comparing with experimental data and analytical solutions under similar conditions. Good agreements were obtained between experiments and model predictions.

  15. Puncture detecting barrier materials

    DOE Patents [OSTI]

    Hermes, R.E.; Ramsey, D.R.; Stampfer, J.F.; Macdonald, J.M.

    1998-03-31T23:59:59.000Z

    A method and apparatus for continuous real-time monitoring of the integrity of protective barrier materials, particularly protective barriers against toxic, radioactive and biologically hazardous materials has been developed. Conductivity, resistivity or capacitance between conductive layers in the multilayer protective materials is measured by using leads connected to electrically conductive layers in the protective barrier material. The measured conductivity, resistivity or capacitance significantly changes upon a physical breach of the protective barrier material. 4 figs.

  16. Romanian experience on packaging testing

    SciTech Connect (OSTI)

    Vieru, G. [IAEA Technical Expert, Head, Reliability and Testing Lab., Institute for Nuclear Research (Romania)

    2007-07-01T23:59:59.000Z

    With more than twenty years ago, the Institute for Nuclear Research Pitesti (INR), through its Reliability and Testing Laboratory, was licensed by the Romanian Nuclear Regulatory Body- CNCAN and to carry out qualification tests [1] for packages intended to be used for the transport and storage of radioactive materials. Radioactive materials, generated by Romanian nuclear facilities [2] are packaged in accordance with national [3] and the IAEA's Regulations [1,6] for a safe transport to the disposal center. Subjecting these packages to the normal and simulating test conditions accomplish the evaluation and certification in order to prove the package technical performances. The paper describes the qualification tests for type A and B packages used for transport and storage of radioactive materials, during a period of 20 years of experience. Testing is used to substantiate assumption in analytical models and to demonstrate package structural response. The Romanian test facilities [1,3,6] are used to simulate the required qualification tests and have been developed at INR Pitesti, the main supplier of type A packages used for transport and storage of low radioactive wastes in Romania. The testing programme will continue to be a strong option to support future package development, to perform a broad range of verification and certification tests on radioactive material packages or component sections, such as packages used for transport of radioactive sources to be used for industrial or medical purposes [2,8]. The paper describes and contain illustrations showing some of the various tests packages which have been performed during certain periods and how they relate to normal conditions and minor mishaps during transport. Quality assurance and quality controls measures taken in order to meet technical specification provided by the design there are also presented and commented. (authors)

  17. Bearwall Energy Efficient Solutions

    E-Print Network [OSTI]

    Sovero,M.

    2014-01-01T23:59:59.000Z

    CATEE Conference November 20, 2014 ENERGY EFFICIENT SOLUTIONS ESL-KT-14-11-06 CATEE 2014: Clean Air Through Efficiency Conference, Dallas, Texas Nov. 18-20 Brief History of Bearwall… Who We Are: ? Manuel Sovero ? Luis Osorio Energy Conservation... Experience: ESL-KT-14-11-06 CATEE 2014: Clean Air Through Efficiency Conference, Dallas, Texas Nov. 18-20 Energy Programs… ESL-KT-14-11-06 CATEE 2014: Clean Air Through Efficiency Conference, Dallas, Texas Nov. 18-20 Bearwall Methodology… Introduction...

  18. Cyanide Solution | EMSL

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

    AFDC Printable Version Share this resource Send a link to EERE: Alternative Fuels Data Center Home Page to someone by E-mail Share EERE: Alternative Fuels Data Center Home Page on Facebook Tweet about EERE: Alternative Fuels Data Center Home Page on Twitter Bookmark EERE:1 First Use of Energy for All Purposes (Fuel and Nonfuel),Feet) Year Jan Feb Mar Apr MayAtmospheric Optical Depth7-1D: Vegetation Proposed Newcatalyst phases onOrganization FY 2012 FYCustomer-Comments SignCyanide Solution

  19. Review: Greenhouse Solutions with Sustainable Energy

    E-Print Network [OSTI]

    Hamilton-Smith, Elery

    2009-01-01T23:59:59.000Z

    Solutions with Sustainable Energy By Mark DiesendorfSolutions with Sustainable Energy. Sydney, NSW: University

  20. Space Reflector Materials for Prometheus Application

    SciTech Connect (OSTI)

    J. Nash; V. Munne; LL Stimely

    2006-01-31T23:59:59.000Z

    The two materials studied in depth which appear to have the most promise in a Prometheus reflector application are beryllium (Be) and beryllium oxide (BeO). Three additional materials, magnesium oxide (MgO), alumina (Al{sub 2}O{sub 3}), and magnesium aluminate spinel (MgAl{sub 2}O{sub 4}) were also recently identified to be of potential interest, and may have promise in a Prometheus application as well, but are expected to be somewhat higher mass than either a Be or BeO based reflector. Literature review and analysis indicates that material properties for Be are largely known, but there are gaps in the properties of Be0 relative to the operating conditions for a Prometheus application. A detailed preconceptual design information document was issued providing material properties for both materials (Reference (a)). Beryllium oxide specimens were planned to be irradiated in the JOY0 Japanese test reactor to partially fill the material property gaps, but more testing in the High Flux Isotope Reactor (HFIR) test reactor at Oak Ridge National Laboratory (ORNL) was expected to be needed. A key issue identified for BeO was obtaining material for irradiation testing with an average grain size of {approx}5 micrometers, reminiscent of material for which prior irradiation test results were promising. Current commercially available material has an average grain size of {approx}10 micrometers. The literature indicated that improved irradiation performance could be expected (e.g., reduced irradiation-induced swelling) with the finer grain size material. Confirmation of these results would allow the use of historic irradiated materials test results from the literature, reducing the extent of required testing and therefore the cost of using this material. Environmental, safety and health (ES&H) concerns associated with manufacturing are significant but manageable for Be and BeO. Although particulate-generating operations (e.g., machining, grinding, etc.) involving Be-bearing materials require significant controls, handling of clean, finished products requires only modest controls. Neither material was initially considered to be viable as a structural material, however, based on improved understanding of its unirradiated properties, Be should be evaluated due to having potentially acceptable structural properties in the unirradiated condition, i. e., during launch, when loads might be most limiting. All three of the alternative materials are non-hazardous, and thus do not engender the ES&H concerns associated with use of Be or BeO. Aluminum oxide is a widely available ceramic material with well characterized physical properties and well developed processing practices. Although the densest (3.97 g/cm{sup 3} versus Be: 1.85, BeO: 3.01, MgO: 3.58, and MgAl{sub 2}O{sub 4}: 3.60, all theoretical density), and therefore the heaviest, of all the materials considered for this application, its ease of fabrication, mechanical properties, availability and neutronic characteristics warrant its evaluation. Similarly, MgO is widely used in the refractory materials industry and has a large established manufacturing base while being lighter than Al{sub 2}O{sub 3}. Most of the commercially available MgO products incorporate additives or a second phase to avoid the formation of Mg(OH){sub 2} due to spontaneous reaction with ambient humidity. The hygroscopicity of MgO makes it a more difficult material to work with than Al{sub 2}O{sub 3} or MgAl{sub 2}O{sub 4}. Magnesium aluminate spinel, although not as widely available as either Al{sub 2}O{sub 3} or MgO, has the advantage of a density almost as low as MgO without being hygroscopic, and shares comparable neutronic performance characteristics in the reflector application.

  1. Survey of Materials for Nanoskiving and Influence of the Cutting Process on the

    E-Print Network [OSTI]

    Church, George M.

    Survey of Materials for Nanoskiving and Influence of the Cutting Process on the Nanostructures materials (metals, ceramics, semiconductors, and conjugated polymers), deposition techniques (evaporation. The materials tested were: aluminum, titanium, nickel, copper, palladium, silver, platinum, gold, lead, bismuth

  2. ANALYTICAL NEUTRONIC STUDIES CORRELATING FAST NEUTRON FLUENCE TO MATERIAL DAMAGE IN CARBON, SILICON, AND SILICON CARBIDE

    SciTech Connect (OSTI)

    Jim Sterbentz

    2011-06-01T23:59:59.000Z

    This study evaluates how fast neutron fluence >0.1 MeV correlates to material damage (i.e., the total fluence spectrum folded with the respective material’s displacements-per- atom [dpa] damage response function) for the specific material fluence spectra encountered in Next Generation Nuclear Plant (NGNP) service and the irradiation tests conducted in material test reactors (MTRs) for the fuel materials addressed in the white paper. It also reports how the evaluated correlations of >0.1 MeV fluence to material damage vary between the different spectral conditions encountered in material service versus testing.

  3. 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...

  4. Joining of dissimilar materials

    DOE Patents [OSTI]

    Tucker, Michael C; Lau, Grace Y; Jacobson, Craig P

    2012-10-16T23:59:59.000Z

    A method of joining dissimilar materials having different ductility, involves two principal steps: Decoration of the more ductile material's surface with particles of a less ductile material to produce a composite; and, sinter-bonding the composite produced to a joining member of a less ductile material. The joining method is suitable for joining dissimilar materials that are chemically inert towards each other (e.g., metal and ceramic), while resulting in a strong bond with a sharp interface between the two materials. The joining materials may differ greatly in form or particle size. The method is applicable to various types of materials including ceramic, metal, glass, glass-ceramic, polymer, cermet, semiconductor, etc., and the materials can be in various geometrical forms, such as powders, fibers, or bulk bodies (foil, wire, plate, etc.). Composites and devices with a decorated/sintered interface are also provided.

  5. Sol-gel manufactured energetic materials

    DOE Patents [OSTI]

    Simpson, Randall L.; Lee, Ronald S.; Tillotson, Thomas M.; Hrubesh, Lawrence W.; Swansiger, Rosalind W.; Fox, Glenn A.

    2003-12-23T23:59:59.000Z

    Sol-gel chemistry is used for the preparation of energetic materials (explosives, propellants and pyrotechnics) with improved homogeneity, and/or which can be cast to near-net shape, and/or made into precision molding powders. The sol-gel method is a synthetic chemical process where reactive monomers are mixed into a solution, polymerization occurs leading to a highly cross-linked three dimensional solid network resulting in a gel. The energetic materials can be incorporated during the formation of the solution or during the gel stage of the process. The composition, pore, and primary particle sizes, gel time, surface areas, and density may be tailored and controlled by the solution chemistry. The gel is then dried using supercritical extraction to produce a highly porous low density aerogel or by controlled slow evaporation to produce a xerogel. Applying stress during the extraction phase can result in high density materials. Thus, the sol-gel method can be used for precision detonator explosive manufacturing as well as producing precision explosives, propellants, and pyrotechnics, along with high power composite energetic materials.

  6. Sol-Gel Manufactured Energetic Materials

    DOE Patents [OSTI]

    Simpson, Randall L. (Livermore, CA); Lee, Ronald S. (Livermore, CA); Tillotson, Thomas M. (Tracy, CA); Hrubesh, Lawrence W. (Pleasanton, CA); Swansiger, Rosalind W. (Livermore, CA); Fox, Glenn A. (Livermore, CA)

    2005-05-17T23:59:59.000Z

    Sol-gel chemistry is used for the preparation of energetic materials (explosives, propellants and pyrotechnics) with improved homogeneity, and/or which can be cast to near-net shape, and/or made into precision molding powders. The sol-gel method is a synthetic chemical process where reactive monomers are mixed into a solution, polymerization occurs leading to a highly cross-linked three dimensional solid network resulting in a gel. The energetic materials can be incorporated during the formation of the solution or during the gel stage of the process. The composition, pore, and primary particle sizes, gel time, surface areas, and density may be tailored and controlled by the solution chemistry. The gel is then dried using supercritical extraction to produce a highly porous low density aerogel or by controlled slow evaporation to produce a xerogel. Applying stress during the extraction phase can result in high density materials. Thus, the sol-gel method can be used for precision detonator explosive manufacturing as well as producing precision explosives, propellants, and pyrotechnics, along with high power composite energetic materials.

  7. 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

  8. 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

  9. Materials for breeding blankets

    SciTech Connect (OSTI)

    Mattas, R.F.; Billone, M.C.

    1995-09-01T23:59:59.000Z

    There are several candidate concepts for tritium breeding blankets that make use of a number of special materials. These materials can be classified as Primary Blanket Materials, which have the greatest influence in determining the overall design and performance, and Secondary Blanket Materials, which have key functions in the operation of the blanket but are less important in establishing the overall design and performance. The issues associated with the blanket materials are specified and several examples of materials performance are given. Critical data needs are identified.

  10. Singlehole GPR reflection imaging of solute transport in a granitic aquifer

    E-Print Network [OSTI]

    Paris-Sud XI, Université de

    Singlehole GPR reflection imaging of solute transport in a granitic aquifer Caroline Dorn,1 Niklas mmaperture fractures. A dipole tracer test was performed in a granitic aquifer by injecting a saline solution of solute transport in a granitic aquifer, Geophys. Res. Lett., 38, L08401, doi:10.1029/ 2011GL047152. 1

  11. Countercurrent flowsheet testing of the TRUEX process with ICPP calcine

    SciTech Connect (OSTI)

    Law, J.D.; Herbst, R.S.; Brewer, K.N.; Todd, T.A.

    1998-07-01T23:59:59.000Z

    Calcine was generated at the Idaho Chemical Processing Plant over several decades as a method of solidifying numerous raffinates and wastes from spent nuclear fuel reprocessing for convenient interim storage. Unfortunately, the bulk of the calcine is inert, with radionuclides comprising less than 1 weight percent of the total calcine mass. The bulk of the calcine currently stored at the ICPP was produced from wastes generated during reprocessing of zirconium clad fuels. Consequently, this material contains varying, but large quantities of zirconium oxide. Currently, separations options are being considered for acidic solutions of dissolved ICPP calcines to minimize high level waste volumes and economic penalties perceived for final disposal of these wastes. The actinide separation process being emphasized for the dissolved calcine solutions is the TRUEX process. Substantial problems have been encountered during TRUEX flowsheet development efforts for dissolved zirconium calcine simulant due to the high concentrations and subsequent extraction of zirconium from the feed. Alteration of the calcine dissolution parameters has resulted in the development of a successful TRUEX/Zr calcine baseline flowsheet. This flowsheet has been tested using 22 stages of a 2.0 centimeter diameter centrifugal contactor pilot plant using simulated dissolved Zr calcine solution. With this flowsheet, a removal efficiency of > 96% was obtained for {sup 241}Am (analytical detection limits were reached). Less than 0.25% of the {sup 95}Zr exited with the high-level waste strip product.

  12. Conditioning of carbonaceous material prior to physical beneficiation

    DOE Patents [OSTI]

    Warzinski, Robert P. (Venetia, PA); Ruether, John A. (McMurray, PA)

    1987-01-01T23:59:59.000Z

    A carbonaceous material such as coal is conditioned by contact with a supercritical fluid prior to physical beneficiation. The solid feed material is contacted with an organic supercritical fluid such as cyclohexane or methanol at temperatures slightly above the critical temperature and pressures of 1 to 4 times the critical pressure. A minor solute fraction is extracted into critical phase and separated from the solid residuum. The residuum is then processed by physical separation such as by froth flotation or specific gravity separation to recover a substantial fraction thereof with reduced ash content. The solute in supercritical phase can be released by pressure reduction and recombined with the low-ash, carbonaceous material.

  13. Nonproliferation Test and Evaluation Complex - NPTEC

    SciTech Connect (OSTI)

    None

    2014-11-10T23:59:59.000Z

    The Nonproliferation Test and Evaluation Complex, or NPTEC, is the world's largest facility for open air testing of hazardous toxic materials and biological simulants. NPTEC is used for testing, experimentation, and training for technologies that require the release of toxic chemicals or biological simulants into the environment.

  14. Nonproliferation Test and Evaluation Complex - NPTEC

    ScienceCinema (OSTI)

    None

    2015-01-09T23:59:59.000Z

    The Nonproliferation Test and Evaluation Complex, or NPTEC, is the world's largest facility for open air testing of hazardous toxic materials and biological simulants. NPTEC is used for testing, experimentation, and training for technologies that require the release of toxic chemicals or biological simulants into the environment.

  15. Nanocomposites as thermoelectric materials

    E-Print Network [OSTI]

    Hao, Qing

    2010-01-01T23:59:59.000Z

    Thermoelectric materials have attractive applications in electric power generation and solid-state cooling. The performance of a thermoelectric device depends on the dimensionless figure of merit (ZT) of the material, ...

  16. Factors of material consumption

    E-Print Network [OSTI]

    Silva Díaz, Pamela Cristina

    2012-01-01T23:59:59.000Z

    Historic consumption trends for materials have been studied by many researchers, and, in order to identify the main drivers of consumption, special attention has been given to material intensity, which is the consumption ...

  17. Earth-Abundant Materials

    Broader source: Energy.gov [DOE]

    DOE funds research into Earth-abundant materials for thin-film solar applications in response to the issue of materials scarcity surrounding other photovoltaic (PV) technologies. Below are a list...

  18. Nanostructured composite reinforced material

    DOE Patents [OSTI]

    Seals, Roland D. (Oak Ridge, TN); Ripley, Edward B. (Knoxville, TN); Ludtka, Gerard M. (Oak Ridge, TN)

    2012-07-31T23:59:59.000Z

    A family of materials wherein nanostructures and/or nanotubes are incorporated into a multi-component material arrangement, such as a metallic or ceramic alloy or composite/aggregate, producing a new material or metallic/ceramic alloy. The new material has significantly increased strength, up to several thousands of times normal and perhaps substantially more, as well as significantly decreased weight. The new materials may be manufactured into a component where the nanostructure or nanostructure reinforcement is incorporated into the bulk and/or matrix material, or as a coating where the nanostructure or nanostructure reinforcement is incorporated into the coating or surface of a "normal" substrate material. The nanostructures are incorporated into the material structure either randomly or aligned, within grains, or along or across grain boundaries.

  19. Institute for Materials Science

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

    Institute for Material Science Who we are and what we do 2:23 Institute for Materials Science: Alexander V. Balatsky IMS is an interdisciplinary research and educational center...

  20. Materials Science & Engineering

    E-Print Network [OSTI]

    and Forensics team in the Polymers and Coatings Group, MST-7. He graduated from the University of Toledo, aerogels, carbon fiber composites, damaged materials, and low density materials examining defects

  1. Advancing Material Models for Automotive Forming Simulations

    SciTech Connect (OSTI)

    Vegter, H.; An, Y.; Horn, C.H.L.J. ten; Atzema, E.H.; Roelofsen, M.E. [Corus Research Development and Technology, PO Box 10000, 1970 CA IJmuiden (Netherlands)

    2005-08-05T23:59:59.000Z

    Simulations in automotive industry need more advanced material models to achieve highly reliable forming and springback predictions. Conventional material models implemented in the FEM-simulation models are not capable to describe the plastic material behaviour during monotonic strain paths with sufficient accuracy. Recently, ESI and Corus co-operate on the implementation of an advanced material model in the FEM-code PAMSTAMP 2G. This applies to the strain hardening model, the influence of strain rate, and the description of the yield locus in these models. A subsequent challenge is the description of the material after a change of strain path.The use of advanced high strength steels in the automotive industry requires a description of plastic material behaviour of multiphase steels. The simplest variant is dual phase steel consisting of a ferritic and a martensitic phase. Multiphase materials also contain a bainitic phase in addition to the ferritic and martensitic phase. More physical descriptions of strain hardening than simple fitted Ludwik/Nadai curves are necessary.Methods to predict plastic behaviour of single-phase materials use a simple dislocation interaction model based on the formed cells structures only. At Corus, a new method is proposed to predict plastic behaviour of multiphase materials have to take hard phases into account, which deform less easily. The resulting deformation gradients create geometrically necessary dislocations. Additional micro-structural information such as morphology and size of hard phase particles or grains is necessary to derive the strain hardening models for this type of materials.Measurements available from the Numisheet benchmarks allow these models to be validated. At Corus, additional measured values are available from cross-die tests. This laboratory test can attain critical deformations by large variations in blank size and processing conditions. The tests are a powerful tool in optimising forming simulations prior to larger scale industrial validation.

  2. Instructions and Materials

    Broader source: Energy.gov [DOE]

    The following are 2012 Program Peer Review Meeting instructions, materials and resource links for presenters and reviewers.

  3. Soil Remediation Test

    SciTech Connect (OSTI)

    Manlapig, D. M.; Williamsws

    2002-04-01T23:59:59.000Z

    Soils contaminated with petroleum by-products can now be effectively remediated using a variety of technologies. Among these are in-situ bioremediation, land farming, and landfill/replacing of soil. The range of efficiencies and cost effectiveness of these technologies has been well documented. Exsorbet Plus is showing promise as an in-situ bioremediation agent. It is made of naturally grown Spaghnum Peat Moss which has been activated for encapsulation and blended with nitrogen-rich fertilizer. In its initial field test in Caracas, Venezuela, it was able to remediate crude oil-contaminated soil in 90 days at less than half of the cost of competing technologies. Waste Solutions, Corp and the US Department of Energy signed a Cooperative Research and Development Agreement to test Exsorbet Plus at the Rocky Mountain Oilfield Testing Center near Casper, Wyoming. As part of the test, soil contaminated with crude oil was treated with Exsorbet Plus to aid the in-situ bioremediation process. Quantitative total petroleum hydrocarbon (TPH) measurements were acquired comparing the performance of Exsorbet Plus with an adjacent plot undergoing unaided in-situ bioremediation.

  4. Vacuum Compatibility of 3D-Printed Materials

    E-Print Network [OSTI]

    Povilus, A P; Vendeiro, Z; Baquero-Ruiz, M; Fajans, J

    2013-01-01T23:59:59.000Z

    The fabrication fidelity and vacuum properties are tested for currently available 3D-printed materials including polyamide, glass, acrylic, and sterling silver. The silver was the only material found to be suitable to ultrahigh vacuum environments due to outgassing and sublimation observed in other materials.

  5. BEE 3650. Properties of Biological Materials Spring Semester 2009

    E-Print Network [OSTI]

    Walter, M.Todd

    ", in setting up the team lab project experiment and the associated specialized materials testing associatedBEE 3650. Properties of Biological Materials Spring Semester 2009 J A Bartsch, PE, 05/22/2009 Credit: 3 hours Catalogue description: Mechanics and structural properties of biological materials

  6. BEE 365. Properties of Biological Materials Spring Semester 2007

    E-Print Network [OSTI]

    Walter, M.Todd

    ", in setting up the team lab project experiment and the associated specialized materials testing associatedBEE 365. Properties of Biological Materials Spring Semester 2007 J A Bartsch, PE, 06/28/2007 Credit: 3 hours Catalogue description: Mechanics and structural properties of biological materials

  7. 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

  8. Advanced neutron absorber materials

    DOE Patents [OSTI]

    Branagan, Daniel J. (Idaho Falls, ID); Smolik, Galen R. (Idaho Falls, ID)

    2000-01-01T23:59:59.000Z

    A neutron absorbing material and method utilizing rare earth elements such as gadolinium, europium and samarium to form metallic glasses and/or noble base nano/microcrystalline materials, the neutron absorbing material having a combination of superior neutron capture cross sections coupled with enhanced resistance to corrosion, oxidation and leaching.

  9. Magnetocaloric Materials Stinus Jeppesen

    E-Print Network [OSTI]

    Magnetocaloric Materials Stinus Jeppesen Risø-PhD-43(EN) Risø National Laboratory for Sustainable Jeppesen Title: Magnetocaloric Materials Division: Fuel Cells and Solid State Chemistry Division Risø.D. degree at The University of Copenhagen Abstract: New and improved magnetocaloric materials are one

  10. Radioactive Materials License Commitments

    E-Print Network [OSTI]

    Radioactive Materials License Commitments for The University of Texas at Austin May 2009 July 2009 in the use of radioactive materials. In July 1963, the State of Texas granted The University of Texas at Austin a broad radioactive materials license for research, development and instruction. While this means

  11. Interlaboratory study of the reproducibility of the single-pass flow-through test method : measuring the dissolution rate of LRM glass at 70 {sup {degree}}C and pH 10.

    SciTech Connect (OSTI)

    Ebert, W. L.; Chemical Engineering

    2006-02-28T23:59:59.000Z

    An international interlaboratory study (ILS) was conducted to evaluate the precision with which single-pass flow-through (SPFT) tests can be conducted by following a method to be standardized by the American Society for Testing and Materials - International. Tests for the ILS were conducted with the low-activity reference material (LRM) glass developed previously for use as a glass test standard. Tests were conducted at 70 {+-} 2 C using a LiCl/LiOH solution as the leachant to impose an initial pH of about 10 (at 70 C). Participants were provided with LRM glass that had been crushed and sieved to isolate the -100 +200 mesh size fraction, and then washed to remove fines. Participants were asked to conduct a series of tests using different solution flow rate-to-sample mass ratios to generate a range of steady-state Si concentrations. The glass dissolution rate under each test condition was calculated using the steady-state Si concentration and solution flow rate that were measured in the test. The glass surface area was estimated from the mass of glass used in the test and the Si content of LRM glass was known. A linear relationship between the rate and the steady-state Si concentration (at Si concentrations less than 10 mg/L) was used to estimate the forward dissolution rate, which is the rate in the absence of dissolved Si. Participants were asked to sample the effluent solution at least five times after reaction times of between 3 and 14 days to measure the Si concentration and flow rate, and to verify that steady-state was achieved. Results were provided by seven participants and the data sets provided by five participants were sufficient to determine the forward rates independently.

  12. Verification Testing Test Driven Development Testing with JUnit Verification

    E-Print Network [OSTI]

    Peters, Dennis

    Verification Testing Test Driven Development Testing with JUnit Verification Any activity should be verified. #12;Verification Testing Test Driven Development Testing with JUnit Approaches to verification 1 Testing 2 Static Analysis · Peer review · Insepction/Walk-through/Structured review · Formal

  13. Modeling of a Modified Rocha Slot Test in welded tuff

    SciTech Connect (OSTI)

    Blanford, M.L.; Zimmerman, R.M.

    1987-12-31T23:59:59.000Z

    The design of nuclear waste repositories in hard rock underground requires an understanding of how the jointed rock mass responds to the various loads introduced. The Nevada Nuclear Waste Storage Investigations (NNWSI) is conducting a series of field tests in G-Tunnel on the Nevada Test Site to characterize the behavior of welded tuff. In particular, one of the ways its modulus of deformation is being measured in situ is by means of a slot loaded by a pressurized flatjack. This is called the Modified Rocha Slot Test, after Manuel Rocha who pioneered investigations using this type of test. Numerical calculations were undertaken using the stress-wave dynamic finite difference code STEALTH. Using dynamic relaxation, the code is able to follow the quasi-static loading curve quite closely, so that the path-dependent aspects of the solution are captured economically. The material model (CAVS) represents an elastic-plastic rock matrix with evenly-spaced joints in three mutually perpendicular planes. The joints have nonlinear normal compliance, shear cohesion, and shear strength that depend on the slip history. Slip-induced dilation of the joints is also taken into consideration. Results of the calculations are presented which illustrate the stresses, deformations, and joint slippages resulting from the application of pressure loading in the slot. The stress field is remarkably sensitive to joint orientation and cohension, but rather insensitive to the normal compliance. The effect of a confining in situ stress field is also examined.

  14. Copyright 2001 by William F. Pratt. Published by Society for the Advancement of Material and Process Engineering with permission.

    E-Print Network [OSTI]

    Allen, Matthew S.

    , Carbon Fiber, Constrained Layer Damping, Composite Materials, Passive Vibration Control, Testing with permission. - 2 - Characterizing the dynamic performance of damped composite materials presents a number of the composite with a single test apparatus. Third, most dynamic test methods don't allow testing of the material

  15. Solution-Procesed Small-Molecule OLED Luminaire for Interior Illumination

    SciTech Connect (OSTI)

    Parker, Ian

    2012-02-29T23:59:59.000Z

    Prototype lighting panels and luminaires were fabricated using DuPont Displaysâ?? solution-processed small-molecule OLED technology. These lighting panels were based on a spatially-patterned, 3-color design, similar in concept to an OLED display panel, with materials chosen to maximize device efficacy. The majority of the processing steps take place in air (rather than high vacuum). Optimization of device architecture, processing and construction was undertaken, with a final prototype design of 50 cm{sup 2} being fabricated and tested. Performance of these panels reached 35 lm/W at illuminant-A. A unique feature of this technology is the ability to color tune the emission, and color temperatures ranging from 2700 to > 6,500K were attained in the final build. Significant attention was paid to low-cost fabrication techniques.

  16. Solution-processed coreshell nanowires for efficient photovoltaic cells

    E-Print Network [OSTI]

    Yang, Peidong

    Solution-processed core­shell nanowires for efficient photovoltaic cells Jinyao Tang1,3 , Ziyang are promising for photovoltaic appli- cations1­11 , but, so far, nanowire-based solar cells have had lower efficiencies than planar cells made from the same materials6­10,12,13 , even allowing for the generally lower

  17. Oxy-Combustion Boiler Material Development

    SciTech Connect (OSTI)

    Michael Gagliano; Andrew Seltzer; Hans Agarwal; Archie Robertson; Lun Wang

    2012-01-31T23:59:59.000Z

    Under U.S. Department of Energy Cooperative Agreement No. DE-NT0005262 Foster Wheeler North America Corp conducted a laboratory test program to determine the effect of oxy-combustion on boiler tube corrosion. In this program, CFD modeling was used to predict the gas compositions that will exist throughout and along the walls of air-fired and oxy-fired boilers operating with low to high sulfur coals. Test coupons of boiler tube materials were coated with deposits representative of those coals and exposed to the CFD predicted flue gases for up to 1000 hours. The tests were conducted in electric tube furnaces using oxy-combustion and air-fired flue gases synthesized from pressurized cylinders. Following exposure, the test coupons were evaluated to determine the total metal wastage experienced under air and oxy-combustions conditions and materials recommendations were made. Similar to air-fired operation, oxy-combustion corrosion rates were found to vary with the boiler material, test temperature, deposit composition, and gas composition. Despite this, comparison of air-fired and oxy-fired corrosion rates showed that oxy-firing rates were, for the most part, similar to, if not lower than those of air-firing; this finding applied to the seven furnace waterwall materials (wrought and weld overlay) and the ten superheater/reheater materials (wrought and weld overlay) that were tested. The results of the laboratory oxy-combustion tests, which are based on a maximum bulk flue gas SO{sub 2} level of 3200 ppmv (wet) / 4050 ppmv (dry), suggest that, from a corrosion standpoint, the materials used in conventional subcritical and supercritical, air-fired boilers should also be suitable for oxy-combustion retrofits. Although the laboratory test results are encouraging, they are only the first step of a material evaluation process and it is recommended that follow-on corrosion tests be conducted in coal-fired boilers operating under oxy-combustion to provide longer term (one to two year) data. The test program details and data are presented herein.

  18. Oxy-Combustion Boiler Material Development

    SciTech Connect (OSTI)

    Gagliano, Michael; Seltzer, Andrew; Agarwal, Hans; Robertson, Archie; Wang, Lun

    2012-01-31T23:59:59.000Z

    Under U.S. Department of Energy Cooperative Agreement No. DE-NT0005262 Foster Wheeler North America Corp conducted a laboratory test program to determine the effect of oxy-combustion on boiler tube corrosion. In this program, CFD modeling was used to predict the gas compositions that will exist throughout and along the walls of air-fired and oxy-fired boilers operating with low to high sulfur coals. Test coupons of boiler tube materials were coated with deposits representative of those coals and exposed to the CFD predicted flue gases for up to 1000 hours. The tests were conducted in electric tube furnaces using oxy-combustion and air-fired flue gases synthesized from pressurized cylinders. Following exposure, the test coupons were evaluated to determine the total metal wastage experienced under air and oxy-combustions conditions and materials recommendations were made. Similar to air-fired operation, oxy-combustion corrosion rates were found to vary with the boiler material, test temperature, deposit composition, and gas composition. Despite this, comparison of air-fired and oxy-fired corrosion rates showed that oxy-firing rates were, for the most part, similar to, if not lower than those of air-firing; this finding applied to the seven furnace waterwall materials (wrought and weld overlay) and the ten superheater/reheater materials (wrought and weld overlay) that were tested. The results of the laboratory oxy-combustion tests, which are based on a maximum bulk flue gas SO2 level of 3200 ppmv (wet) / 4050 ppmv (dry), suggest that, from a corrosion standpoint, the materials used in conventional subcritical and supercritical, air-fired boilers should also be suitable for oxy-combustion retrofits. Although the laboratory test results are encouraging, they are only the first step of a material evaluation process and it is recommended that follow-on corrosion tests be conducted in coal-fired boilers operating under oxy-combustion to provide longer term (one to two year) data. The test program details and data are presented herein.

  19. The aqueous corrosion behavior of technetium - Alloy and composite materials

    SciTech Connect (OSTI)

    Jarvinen, G.; Kolman, D.; Taylor, C.; Goff, G.; Cisneros, M. [Los Alamos National Laboratory, Los Alamos, NM 87545 (United States); Mausolf, E.; Poineau, F.; Koury, D.; Czerwinski, K. [Department of Chemistry, University of Nevada, Las Vegas, Las Vegas, NV 89154 (United States)

    2013-07-01T23:59:59.000Z

    Metal waste forms are under study as possible disposal forms for technetium and other fission products. The alloying of Tc is desirable to reduce the melting point of the Tc-containing metal waste form and potentially improve its corrosion resistance. Technetium-nickel composites were made by mixing the two metal powders and pressing the mixture to make a pellet. The as-pressed composite materials were compared to sintered composites and alloys of identical composition in electrochemical corrosion tests. As-pressed samples were not robust enough for fine polishing and only a limited number of corrosion tests were performed. Alloys and composites with 10 wt% Tc appear to be more corrosion resistant at open circuit than the individual components based on linear polarization resistance and polarization data. The addition of 10 wt% Tc to Ni appears beneficial at open circuit, but detrimental upon anodic polarization. Qualitatively, the polarizations of 10 wt% Tc alloys and composites appear like crude addition of Tc plus Ni. The 1 wt% Tc alloys behave like pure Ni, but some effect of Tc is seen upon polarization. Cathodic polarization of Tc by Ni appears feasible based on open circuit potential measurements, however, zero resistance ammetry and solution measurements are necessary to confirm cathodic protection.

  20. Mechanical properties of thermal protection system materials.

    SciTech Connect (OSTI)

    Hardy, Robert Douglas; Bronowski, David R.; Lee, Moo Yul; Hofer, John H.

    2005-06-01T23:59:59.000Z

    An experimental study was conducted to measure the mechanical properties of the Thermal Protection System (TPS) materials used for the Space Shuttle. Three types of TPS materials (LI-900, LI-2200, and FRCI-12) were tested in 'in-plane' and 'out-of-plane' orientations. Four types of quasi-static mechanical tests (uniaxial tension, uniaxial compression, uniaxial strain, and shear) were performed under low (10{sup -4} to 10{sup -3}/s) and intermediate (1 to 10/s) strain rate conditions. In addition, split Hopkinson pressure bar tests were conducted to obtain the strength of the materials under a relatively higher strain rate ({approx}10{sup 2} to 10{sup 3}/s) condition. In general, TPS materials have higher strength and higher Young's modulus when tested in 'in-plane' than in 'through-the-thickness' orientation under compressive (unconfined and confined) and tensile stress conditions. In both stress conditions, the strength of the material increases as the strain rate increases. The rate of increase in LI-900 is relatively small compared to those for the other two TPS materials tested in this study. But, the Young's modulus appears to be insensitive to the different strain rates applied. The FRCI-12 material, designed to replace the heavier LI-2200, showed higher strengths under tensile and shear stress conditions. But, under a compressive stress condition, LI-2200 showed higher strength than FRCI-12. As far as the modulus is concerned, LI-2200 has higher Young's modulus both in compression and in tension. The shear modulus of FRCI-12 and LI-2200 fell in the same range.