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Sample records for test program final

  1. Manipulator Comparative Testing Program: Final report

    International Nuclear Information System (INIS)

    Draper, J.V.; Handel, S.J.; Sundstrom, E.; Herndon, J.N; Fujita, Y.; Maeda, M.

    1987-02-01

    The manipulator systems tested included the Meidensha BILARM 83A, the Central Research Laboratories Model M-2, and the GCA PaR Systems Model 6000. Six manipulator and control mode combinations were evaluated: (1) the BILARM in master/slave mode without force reflection, (2) the BILARM in master/slave mode with force reflection, (3) the Model M-2 in master/slave mode without force reflection, (4) the Model M-2 in master/slave mode with force reflection, (5) the BILARM with switchbox controls, and (6) the PaR 6000 with switchbox controls. The experiments examined differences between master/slave systems with and without force reflection and differences between master/slave systems and switchbox-controlled systems. A fourth experiment examined the relative contributions of the remote viewing system and the manipulator system to the performance of remote handling tasks. Results of the experiments showed that operators using the Model M-2 in master/slave mode had significantly faster times to completion than operators using the BILARM in master/slave mode, with about the same error rate per trial. Operators were slower using the BILARM with force reflection than without it, and they committed more errors. There was no statistically significant difference between force-reflection and nonforce-reflection conditions for the M-2 manipulator for any of the performance criteria. Tasks and procedures used in this testing were not sensitive to differences within any single system. No inferences about the effect of force reflection on remote task performance should be made from these data. The two manipulator systems in switchbox mode had significantly slower times to completion than any system in master/slave mode, with approximately the same error rate per trial. There were no significant differences between the BILARM in switchbox mode and the PaR arm

  2. KNK I Test Program, Final Report Part 1

    International Nuclear Information System (INIS)

    Kathol, W.

    1976-01-01

    The compact sodium cooled nuclear reactor KNK I of the Karlsruhe Research Center reached full power for the first time in February 1974. The goal of KNK I is to collect experience for the construction and operation of larger reactors, such as SNR 300. In order to deepen these experiences, a test program was drawn up and conducted from 1973 until 1975 within the framework of R and D work on the development of fast breeder reactors. The program included individual tasks concerning reactor design, safety instrumentation, irradiation and post-examination as well as behavior of components during operation. The performance of the tests was essentially governed by the licensing procedure imposed under the atomic energy act for the construction and operation of nuclear facilities. This report is the first part of the final report of the test program

  3. Sheath insulator final test report, TFE Verification Program

    International Nuclear Information System (INIS)

    1994-07-01

    The sheath insulator in a thermionic cell has two functions. First, the sheath insulator must electrically isolate the collector form the outer containment sheath tube that is in contact with the reactor liquid metal coolant. Second, The sheath insulator must provide for high uniform thermal conductance between the collector and the reactor coolant to remove away waste heat. The goals of the sheath insulator test program were to demonstrate that suitable ceramic materials and fabrication processes were available, and to validate the performance of the sheath insulator for TFE-VP requirements. This report discusses the objectives of the test program, fabrication development, ex-reactor test program, in-reactor test program, and the insulator seal specifications

  4. Sheath insulator final test report, TFE Verification Program

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    The sheath insulator in a thermionic cell has two functions. First, the sheath insulator must electrically isolate the collector form the outer containment sheath tube that is in contact with the reactor liquid metal coolant. Second, The sheath insulator must provide for high uniform thermal conductance between the collector and the reactor coolant to remove away waste heat. The goals of the sheath insulator test program were to demonstrate that suitable ceramic materials and fabrication processes were available, and to validate the performance of the sheath insulator for TFE-VP requirements. This report discusses the objectives of the test program, fabrication development, ex-reactor test program, in-reactor test program, and the insulator seal specifications.

  5. Cooperative field test program for wind systems. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Bollmeier, W.S. II; Dodge, D.M.

    1992-03-01

    The objectives of the Federal Wind Energy Program, managed by the US Department of Energy (DOE), are (1) to assist industry and utilities in achieving a multi-regional US market penetration of wind systems, and (2) to establish the United States as the world leader in the development of advanced wind turbine technology. In 1984, the program conducted a series of planning workshops with representatives from the wind energy industry to obtain input on the Five-Year Research Plan then being prepared by DOE. One specific suggestion that came out of these meetings was that the federal program should conduct cooperative research tests with industry to enhance the technology transfer process. It was also felt that the active involvement of industry in DOE-funded research would improve the state of the art of wind turbine technology. DOE established the Cooperative Field Test Program (CFTP) in response to that suggestion. This program was one of the first in DOE to feature joint industry-government research test teams working toward common objectives.

  6. Focus group testing for the vehicle scrappage program : final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-03-15

    Canada's national vehicle scrappage program was designed to reduce greenhouse gas (GHG) and smog-forming emissions by removing personal vehicles with model years of 1995 and older from Canadian road systems. The program will also promote sustainable transportation alternatives and recycling programs to prevent the release of other toxic substances into the environment. Incentives designed to encourage Canadians to scrap older vehicles may include cash incentives and rebates towards the purchase of a new vehicle, free transit passes, and other options designed to support sustainable transportation. This paper discussed a research program conducted to assess target audience responses to the programs and its proposed incentives. The survey was conducted with a series of 20 focus groups located in major cities across Canada. Sessions were comprised of between 6 to 10 participants from lower-income and higher-income households. All groups responded negatively to both the overall policy as well as to specific program elements. The study showed that most participants were not aware that older vehicles emit significantly higher levels of harmful emissions. The research audience did not understand distinctions between smog-producing emissions and GHG emissions. Participants also believed that personal vehicles had a minor negative impact on the environment compared to trucks, industry, and vehicle fleets. Participants felt a sense of pride in the ways in which they had maintained their older vehicles, and also perceived them as safer than newer vehicles. It was concluded that many participants were resistant to facts presented to them about older vehicles, and felt that the incentives were insufficient to trigger action. The effectiveness of advertising materials designed to promote the program was also assessed. 3 tabs., 9 figs.

  7. GSDO Program Hexavalent Chrome Alternatives: Final Pretreatments Test Report

    Science.gov (United States)

    Kessel, Kurt

    2013-01-01

    Hexavalent chrome free pretreatments should be considered for use on Ground Support Equipment (OSE) and Electrical Ground Support Equipment (EOSE). Both of the hexavalent chrome free pretreatments (Metalast TCP HF and SurTec 650C) evaluated by this project met, and in some instances exceeded, the requirements ofMIL-DTL-5541 "Chemical Conversion Coatings on Aluminum and Aluminum Alloys". For DC resistance measurements, both Metalast TCP HF and SurTec (!50C met initial requirements following assembly and in many cases continued to maintain passing readings for the duration of testing.

  8. Spent fuel sabotage test program, characterization of aerosol dispersal : interim final report

    International Nuclear Information System (INIS)

    Gregson, Michael Warren; Brockmann, John E.; Loiseau, Olivier; Klennert, Lindsay A.; Nolte, Oliver; Molecke, Martin Alan; Autrusson, Bruno A.; Koch, Wolfgang; Pretzsch, Gunter Guido; Brucher, Wenzel; Steyskal, Michele D.

    2008-01-01

    This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program provides source-term data that are relevant to plausible sabotage scenarios in relation to spent fuel transport and storage casks and associated risk assessments. We present details and significant results obtained from this program from 2001 through 2007. Measured aerosol results include: respirable fractions produced; amounts, nuclide content, and produced particle size distributions and morphology; measurements of volatile fission product species enhanced sorption--enrichment factors onto respirable particles; and, status on determination of the spent fuel ratio, SFR, needed for scaling studies. Emphasis is provided on recent Phase 3 tests using depleted uranium oxide pellets plus non-radioactive fission product dopants in surrogate spent fuel test rodlets, plus the latest surrogate cerium oxide results and aerosol laboratory supporting calibration work. The DUO 2 , CeO 2 , plus fission product dopant aerosol particle results are compared with available historical data. We also provide a status review on continuing preparations for the final Phase 4 in this program, tests using individual short rodlets containing actual spent fuel from U.S. PWR reactors, with both high- and lower-burnup fuel. The source-term data, aerosol results, and program design have been tailored to support and guide follow-on computer modeling of aerosol dispersal hazards and radiological consequence assessments. This spent fuel sabotage, aerosol test program was performed primarily at Sandia National Laboratories, with support provided by both the U.S. Department of Energy and the Nuclear Regulatory Commission. This program has significant input from, and is cooperatively supported and

  9. Active vibration control testing of the SPICES program: final demonstration article

    Science.gov (United States)

    Dunne, James P.; Jacobs, Jack H.

    1996-05-01

    The Synthesis and Processing of Intelligent Cost Effective Structures (SPICES) Program is a partnership program sponsored by the Advanced Research Projects Agency. The mission of the program is to develop cost effective material processing and synthesis technologies to enable new products employing active vibration suppression and control devices to be brought to market. The two year program came to fruition in 1995 through the fabrication of the final smart components and testing of an active plate combined with two trapezoidal rails, forming an active mount. Testing of the SPICES combined active mount took place at McDonnell Douglas facilities in St. Louis, MO, in October-December 1995. Approximately 15 dB reduction in overall response of a motor mounted on the active structure was achieved. Further details and results of the SPICES combined active mount demonstration testing are outlined. Results of numerous damping and control strategies that were developed and employed in the testing are presented, as well as aspects of the design and fabrication of the SPICES active mount components.

  10. Spent fuel sabotage test program, characterization of aerosol dispersal : interim final report.

    Energy Technology Data Exchange (ETDEWEB)

    Gregson, Michael Warren; Brockmann, John E.; Loiseau, Olivier (Institut de Radioprotection et de Surete Nucleaire, France); Klennert, Lindsay A.; Nolte, Oliver (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Molecke, Martin Alan; Autrusson, Bruno A. (Institut de Radioprotection et de Surete Nucleaire, France); Koch, Wolfgang (Fraunhofer Institut fur Toxikologie und Experimentelle Medizin, Germany); Pretzsch, Gunter Guido (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Brucher, Wenzel (Gesellschaft fur Anlagen- und Reaktorsicherheit, Germany); Steyskal, Michele D.

    2008-03-01

    This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program provides source-term data that are relevant to plausible sabotage scenarios in relation to spent fuel transport and storage casks and associated risk assessments. We present details and significant results obtained from this program from 2001 through 2007. Measured aerosol results include: respirable fractions produced; amounts, nuclide content, and produced particle size distributions and morphology; measurements of volatile fission product species enhanced sorption--enrichment factors onto respirable particles; and, status on determination of the spent fuel ratio, SFR, needed for scaling studies. Emphasis is provided on recent Phase 3 tests using depleted uranium oxide pellets plus non-radioactive fission product dopants in surrogate spent fuel test rodlets, plus the latest surrogate cerium oxide results and aerosol laboratory supporting calibration work. The DUO{sub 2}, CeO{sub 2}, plus fission product dopant aerosol particle results are compared with available historical data. We also provide a status review on continuing preparations for the final Phase 4 in this program, tests using individual short rodlets containing actual spent fuel from U.S. PWR reactors, with both high- and lower-burnup fuel. The source-term data, aerosol results, and program design have been tailored to support and guide follow-on computer modeling of aerosol dispersal hazards and radiological consequence assessments. This spent fuel sabotage, aerosol test program was performed primarily at Sandia National Laboratories, with support provided by both the U.S. Department of Energy and the Nuclear Regulatory Commission. This program has significant input from, and is cooperatively

  11. A Study of Minimum Competency Testing Programs. Final Summary and Analysis Report.

    Science.gov (United States)

    Gorth, William Phillip; Perkins, Marcy R.

    To portray the status of minimum competency testing programs nationwide; as of June 30, 1979, on-site visits were conducted with directors of all 31 state programs and 20 local district programs. Most programs were developed since 1976; 14 state and 13 local programs are fully implemented. The state board of education mandated 16 state programs;…

  12. Ocean Thermal Energy Converstion (OTEC) test facilities study program. Final report. Volume II. Part B

    Energy Technology Data Exchange (ETDEWEB)

    None

    1977-01-17

    Results are presented of an 8-month study to develop alternative non-site-specific OTEC facilities/platform requirements for an integrated OTEC test program which may include land and floating test facilities. Volume II--Appendixes is bound in three parts (A, B, and C) which together comprise a compendium of the most significant detailed data developed during the study. Part B provides an annotated test list and describes component tests and system tests.

  13. Selenide isotope generator for the Galileo Mission: SIG/Galileo hermetic receptable test program final report

    International Nuclear Information System (INIS)

    Roedel, S.

    1979-06-01

    The purpose of the receptacle test program was to test various types of hermetically sealed electrical receptacles and to select one model as the spaceflight hardware item for SIG/Galileo thermoelectric generators. The design goal of the program was to qualify a hermetic seal integrity of less than or equal to 1 x 10 -9 std cc He/sec -atm at 400 0 F (204 0 C) and verify a reliability of 0.95 at a 50% confidence level for a flight mission in excess of 7 years

  14. Wildfire ignition resistant home design(WIRHD) program: Full-scale testing and demonstration final report.

    Energy Technology Data Exchange (ETDEWEB)

    Quarles, Stephen, L.; Sindelar, Melissa

    2011-12-13

    The primary goal of the Wildfire ignition resistant home design(WIRHD) program was to develop a home evaluation tool that could assess the ignition potential of a structure subjected to wildfire exposures. This report describes the tests that were conducted, summarizes the results, and discusses the implications of these results with regard to the vulnerabilities to homes and buildings.

  15. DEVELOPMENT OF A PROGRAMED TEXT IN SALESMANSHIP FOR FEASIBILITY TESTING IN ADULT EDUCATION. FINAL REPORT.

    Science.gov (United States)

    RUSSELL, RAYMOND B.

    A PROGRAMED TEXT ON SALESMANSHIP WAS DEVELOPED, FIELD TESTED FOR CLARITY, AND REVIEWED BY AN ADVISORY COMMITTEE. PROMOTION OF THE TEXT IN A RANDOM SAMPLE OF 10 TOWNS OF 2,000 TO 7,000 POPULATION WAS CONDUCTED. THE PROMOTION CONSISTED OF CONTACT WITH THE LOCAL CHAMBER OF COMMERCE. SIX COMMUNITIES ACCEPTED. WITH 267 ADULTS ENROLLED UNDER LOCAL…

  16. The AP600 advanced simplified nuclear power plant. Results of the test program and progress made toward final design approval

    International Nuclear Information System (INIS)

    Bruschi, H.J.

    1996-01-01

    At the 1994 Pacific Basin Conference, Mr. Bruschi presented a paper describing the AP600, Westinghouse's advanced light water reactor design with passive safety features. Since then, a rigorous test program was completed and AP600 became the most thoroughly tested advanced reactor system design in history. Westinghouse is now well on its way toward receiving Final Design Approval from the U.S. Nuclear Regulatory Commission for AP600. In this paper, the results of the test program will be discussed and an update on prospects for building the plant will be covered. (author)

  17. The AP600 advanced simplified nuclear power plant. Results of the test program and progress made toward final design approval

    Energy Technology Data Exchange (ETDEWEB)

    Bruschi, H.J. [Westinghouse Electric Corp., Pittsburgh, PA (United States)

    1996-10-01

    At the 1994 Pacific Basin Conference, Mr. Bruschi presented a paper describing the AP600, Westinghouse`s advanced light water reactor design with passive safety features. Since then, a rigorous test program was completed and AP600 became the most thoroughly tested advanced reactor system design in history. Westinghouse is now well on its way toward receiving Final Design Approval from the U.S. Nuclear Regulatory Commission for AP600. In this paper, the results of the test program will be discussed and an update on prospects for building the plant will be covered. (author)

  18. Final focus test beam

    International Nuclear Information System (INIS)

    1991-03-01

    This report discusses the following: the Final Focus Test Beam Project; optical design; magnets; instrumentation; magnetic measurement and BPM calibration; mechanical alignment and stabilization; vacuum system; power supplies; control system; radiation shielding and personnel protection; infrastructure; and administration

  19. Hydraulic impact end effector final test report. Automation and robotics section, ER/WM-AT Program

    International Nuclear Information System (INIS)

    Couture, S.

    1994-01-01

    One tool being developed for dislodging and fragmenting the hard salt cake waste in the single-shell nuclear waste tanks at the Hanford Reservation near Richland, Washington, is the hydraulic impact end effector (HIEE). This total operates by discharging 11-in. slugs of water at ultrahigh pressures. The HIEE was designed, built, and initially tested in 1992. Work in 1993 included advanced developments of the HIEE to further investigate its fragmentation abilities and to determine more effective operating procedures. These tests showed that more fragmentation can be achieved by increasing the charge pressure of 40 kpsi to 55 kpsi and by the use of different operating procedures. The size of the material and the impact energy of the water slug fired from the HIEE are believed to be major factors in material fragmentation. The material's ability to fracture also appears to depend on the distance a fracture or crack line must travel to a free surface. Thus, larger material is more difficult to fracture than smaller material. Discharge pressures of 40 kpsi resulted in little penetration or fracturing of the material. At 55 kpsi, however, the size and depth of the fractures increased. Nozzle geometry had a significant effect on fragment size and quantity. Fragmentation was about an order of magnitude greater when the HIEE was discharged into drilled holes rather than onto the material surface. Since surface shots tend to create craters, a multi-shot procedure, coupled with an advanced nozzle design, was used to drill (crater) deep holes into large material. With this procedure, a 600-lb block was reduced to smaller pieces without the use of any additional equipment. Through this advanced development program, the HIEE has demonstrated that it can quickly fragment salt cake material into small, easily removable fragments. The HIEE's material fragmentation ability can be substantially increased through the use of different nozzle geometries and operating procedures

  20. Ferrocyanide safety program: Final report on adiabatic calorimetry and tube propagation tests with synthetic ferrocyanide materials

    International Nuclear Information System (INIS)

    Fauske, H.F.; Meacham, J.E.; Cash, R.J.

    1995-01-01

    Based on Fauske and Associates, Inc. Reactive System Screening Tool tests, the onset or initiation temperature for a ferrocyanide-nitrate propagating reaction is about 250 degrees Celcius. This is at about 200 degrees Celcius higher than current waste temperatures in the highest temperature ferrocyanide tanks. Furthermore, for current ambient waste temperatures, the tube propagation tests show that a ferrocyanide concentration of 15.5 wt% or more is required to sustain a propagation reaction in the complete absence of free water. Ignoring the presence of free water, this finding rules out propagating reactions for all the Hanford flowsheet materials with the exception of the ferrocyanide waste produced by the original In Farm flowsheet

  1. Final report on physical test program of Spanish clays (Saponites and bentonites)

    Energy Technology Data Exchange (ETDEWEB)

    Pusch, R.; Karnland, O.; Sanden, T.

    1996-10-01

    Two Spanish candidate buffer clays were hydrothermally treated and then investigated with respect to the physical properties and chemical and mineralogical compositions. four temperatures were used: room temperature 70 degree centigree, 120 degree centigree and 170 degree centigree, and three periods of testing: 10 days, 60 days and 360 days. The hydrothermal treatment was made by use of pressurized vessels with different solutions rich in Na``+/Ca``2+, K``+ and Mg``2+, respectively. The testing comprised determination of physical properties, e.g. the hydraulic conductivity and the rheological behavior, as well as of chemical and mineralogical changes. The hydraulic conductivity was found to be significantly affected by the type of dominant cation. With time, the conductivity dropped due to microstructural homogenization but exposure to higher temperatures caused an increased conductivity. The mechanical strength was highest of the Saponites primarily due to colloid-chemical effects. The dominant chemical effect up to 120 degree centigree was cation exchange. At 170 degree centigree significant dissolution took place, releasing silica from the clay. Mineral changes were insignificant and no conversion of the smectite to illite could be identified in the montmorillonitic clay, while some slight alteration of saponite to illite took place to about the same extent at all temperatures, including room temperature.

  2. Astron Program final report

    International Nuclear Information System (INIS)

    Briggs, R.J.; Hester, R.E.; Porter, G.D.; Sherwood, W.A.; Spoerlein, R.; Stallard, B.W.; Taska, J.; Weiss, P.B.

    1975-01-01

    This report describes important experimental results obtained in the last two years of the Astron Program, an LLL controlled nuclear fusion program which terminated in 1973. Little theoretical work is included, but an extensive bibliography is given

  3. Development and Field Test of Competency Based Instructional Material for a Career Mobility Program for Licensed Practical Nurses. Final Report.

    Science.gov (United States)

    Bergen Community Coll., Paramus, NJ.

    The Associate Degree Nursing Program at Bergen Community College developed and field tested competency-based instructional modules in a program designed to allow licensed practical nurses to qualify to take the certification examination for registered nurses after a year of study. Thirteen licensed practical nurses were enrolled in the first class…

  4. Testing geopressured geothermal reservoirs in existing wells. Wells of Opportunity Program final contract report, 1980-1981

    Energy Technology Data Exchange (ETDEWEB)

    1982-01-01

    The geopressured-geothermal candidates for the Wells of Opportunity program were located by the screening of published information on oil industry activity and through direct contact with the oil and gas operators. This process resulted in the recommendation to the DOE of 33 candidate wells for the program. Seven of the 33 recommended wells were accepted for testing. Of these seven wells, six were actually tested. The first well, the No. 1 Kennedy, was acquired but not tested. The seventh well, the No. 1 Godchaux, was abandoned due to mechanical problems during re-entry. The well search activities, which culminated in the acceptance by the DOE of 7 recommended wells, were substantial. A total of 90,270 well reports were reviewed, leading to 1990 wells selected for thorough geological analysis. All of the reservoirs tested in this program have been restricted by one or more faults or permeability barriers. A comprehensive discussion of test results is presented.

  5. Temperature buffer test. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Aakesson, Mattias [Clay Technology AB, Lund (Sweden)

    2012-04-15

    The Temperature Buffer Test (TBT) is a joint project between SKB/ANDRA and supported by ENRESA (modelling) and DBE (instrumentation), which aims at improving the understanding and to model the thermo-hydro-mechanical behavior of buffers made of swelling clay submitted to high temperatures (over 100 deg C) during the water saturation process. The test has been carried out in a KBS-3 deposition hole at Aspo HRL. It was installed during the spring of 2003. Two steel heaters (3 m long, 0.6 m diameter) and two buffer arrangements have been investigated: the lower heater was surrounded by rings of compacted Wyoming bentonite only, whereas the upper heater was surrounded by a composite barrier, with a sand shield between the heater and the bentonite. The test was dismantled and sampled during the winter of 2009/2010. This report is the final report and a summary of all work performed within the TBT project. The design and the installation of the different components are summarized: the depositions hole, the heating system, the bentonite blocks with emphasis on the initial density and water content in these, the filling of slots with sand or pellets, the retaining construction with the plug, lid and nine anchor cables, the artificial saturation system, and finally the instrumentation. An overview of the operational conditions is presented: the power output from heaters, which was 1,500 W (and also 1,600 W) from each heater during the first {approx}1,700 days, and then changed to 1,000 and 2,000 W, for the upper and lower heater respectively, during the last {approx}600 days. From the start, the bentonite was hydrated with a groundwater from a nearby bore-hole, but this groundwater was replaced with de-ionized water from day {approx}1,500, due to the high flow resistance of the injections points in the filter, which implied that a high filter pressure couldn't be sustained. The sand shield around the upper heater was hydrated from day {approx}1,500 to day {approx}1

  6. Temperature buffer test. Final report

    International Nuclear Information System (INIS)

    Aakesson, Mattias

    2012-04-01

    The Temperature Buffer Test (TBT) is a joint project between SKB/ANDRA and supported by ENRESA (modelling) and DBE (instrumentation), which aims at improving the understanding and to model the thermo-hydro-mechanical behavior of buffers made of swelling clay submitted to high temperatures (over 100 deg C) during the water saturation process. The test has been carried out in a KBS-3 deposition hole at Aspo HRL. It was installed during the spring of 2003. Two steel heaters (3 m long, 0.6 m diameter) and two buffer arrangements have been investigated: the lower heater was surrounded by rings of compacted Wyoming bentonite only, whereas the upper heater was surrounded by a composite barrier, with a sand shield between the heater and the bentonite. The test was dismantled and sampled during the winter of 2009/2010. This report is the final report and a summary of all work performed within the TBT project. The design and the installation of the different components are summarized: the depositions hole, the heating system, the bentonite blocks with emphasis on the initial density and water content in these, the filling of slots with sand or pellets, the retaining construction with the plug, lid and nine anchor cables, the artificial saturation system, and finally the instrumentation. An overview of the operational conditions is presented: the power output from heaters, which was 1,500 W (and also 1,600 W) from each heater during the first ∼1,700 days, and then changed to 1,000 and 2,000 W, for the upper and lower heater respectively, during the last ∼600 days. From the start, the bentonite was hydrated with a groundwater from a nearby bore-hole, but this groundwater was replaced with de-ionized water from day ∼1,500, due to the high flow resistance of the injections points in the filter, which implied that a high filter pressure couldn't be sustained. The sand shield around the upper heater was hydrated from day ∼1,500 to day ∼1,800. The sensors data concerning

  7. Leadership Development Program Final Project

    Science.gov (United States)

    Parrish, Teresa C.

    2016-01-01

    TOSC is NASA's prime contractor tasked to successfully assemble, test, and launch the EM1 spacecraft. TOSC success is highly dependent on design products from the other NASA Programs manufacturing and delivering the flight hardware; Space Launch System(SLS) and Multi-Purpose Crew Vehicle(MPCV). Design products directly feed into TOSC's: Procedures, Personnel training, Hardware assembly, Software development, Integrated vehicle test and checkout, Launch. TOSC senior management recognized a significant schedule risk as these products are still being developed by the other two (2) programs; SVE and ACE positions were created.

  8. SINGLE HEATER TEST FINAL REPORT

    Energy Technology Data Exchange (ETDEWEB)

    J.B. Cho

    1999-05-01

    The Single Heater Test is the first of the in-situ thermal tests conducted by the U.S. Department of Energy as part of its program of characterizing Yucca Mountain in Nevada as the potential site for a proposed deep geologic repository for the disposal of spent nuclear fuel and high-level nuclear waste. The Site Characterization Plan (DOE 1988) contained an extensive plan of in-situ thermal tests aimed at understanding specific aspects of the response of the local rock-mass around the potential repository to the heat from the radioactive decay of the emplaced waste. With the refocusing of the Site Characterization Plan by the ''Civilian Radioactive Waste Management Program Plan'' (DOE 1994), a consolidated thermal testing program emerged by 1995 as documented in the reports ''In-Situ Thermal Testing Program Strategy'' (DOE 1995) and ''Updated In-Situ Thermal Testing Program Strategy'' (CRWMS M&O 1997a). The concept of the Single Heater Test took shape in the summer of 1995 and detailed planning and design of the test started with the beginning fiscal year 1996. The overall objective of the Single Heater Test was to gain an understanding of the coupled thermal, mechanical, hydrological, and chemical processes that are anticipated to occur in the local rock-mass in the potential repository as a result of heat from radioactive decay of the emplaced waste. This included making a priori predictions of the test results using existing models and subsequently refining or modifying the models, on the basis of comparative and interpretive analyses of the measurements and predictions. A second, no less important, objective was to try out, in a full-scale field setting, the various instruments and equipment to be employed in the future on a much larger, more complex, thermal test of longer duration, such as the Drift Scale Test. This ''shake down'' or trial aspect of the Single Heater Test applied

  9. SINGLE HEATER TEST FINAL REPORT

    International Nuclear Information System (INIS)

    J.B. Cho

    1999-01-01

    The Single Heater Test is the first of the in-situ thermal tests conducted by the U.S. Department of Energy as part of its program of characterizing Yucca Mountain in Nevada as the potential site for a proposed deep geologic repository for the disposal of spent nuclear fuel and high-level nuclear waste. The Site Characterization Plan (DOE 1988) contained an extensive plan of in-situ thermal tests aimed at understanding specific aspects of the response of the local rock-mass around the potential repository to the heat from the radioactive decay of the emplaced waste. With the refocusing of the Site Characterization Plan by the ''Civilian Radioactive Waste Management Program Plan'' (DOE 1994), a consolidated thermal testing program emerged by 1995 as documented in the reports ''In-Situ Thermal Testing Program Strategy'' (DOE 1995) and ''Updated In-Situ Thermal Testing Program Strategy'' (CRWMS M and O 1997a). The concept of the Single Heater Test took shape in the summer of 1995 and detailed planning and design of the test started with the beginning fiscal year 1996. The overall objective of the Single Heater Test was to gain an understanding of the coupled thermal, mechanical, hydrological, and chemical processes that are anticipated to occur in the local rock-mass in the potential repository as a result of heat from radioactive decay of the emplaced waste. This included making a priori predictions of the test results using existing models and subsequently refining or modifying the models, on the basis of comparative and interpretive analyses of the measurements and predictions. A second, no less important, objective was to try out, in a full-scale field setting, the various instruments and equipment to be employed in the future on a much larger, more complex, thermal test of longer duration, such as the Drift Scale Test. This ''shake down'' or trial aspect of the Single Heater Test applied not just to the hardware, but also to the teamwork and cooperation between

  10. FLECHT SEASET program. Final report

    International Nuclear Information System (INIS)

    Hochreiter, L.E.

    1985-11-01

    This report presents the highlights and main findings of the USNRC, EPRI, and Westinghouse cooperative FLECHT SEASET program. The report indicates areas in which the results of the program can contribute to revising the current licensing requirements for Loss of Coolant (LOCA) safety analysis for PWRs. Also identified are several technical areas in which the new FLECHT SEASET data and analysis can lead to improved safety analysis modeling, and thereby to predicted PWR response for postulated accident scenarios. Significant progress has been made in the modeling areas of nonequilibrium dispersed two-phase flow during reflood. Improved models and understanding of this rod bundle cooling regime are summarized in this report. Another important result of the FLECHT SEASET program arises from the natural circulation test series, which investigated single-phase, two-phase, and reflux condensation cooling modes of a scaled PWR under small-break LOCA conditions. The tests and subsequent analysis constitute one of few complete sets of data for these cooling modes in which full-height, multitube steam generators with sufficient instrumentation were used to examine primary-to-secondary heat transfer in the generators. It is believed that the natural circulation test data will be extremely useful to benchmark the improved post-TMI small-break LOCA computer codes. 170 figs., 13 tabs

  11. Grimsel Test Site: heat test, final report

    International Nuclear Information System (INIS)

    Schneefuss, J.; Glaess, F.; Gommlich, G.; Schmidt, M.

    1989-05-01

    The Swiss concept for the storage of radioactive waste consists in placing it in compact, dense rock formations. An experiment 'Heat Test' carried out by the 'Gesellschaft fuer Strahlen- und Umweltforschung' in Nagra's Grimsel rock laboratory simulated the heat production of stored radioactive waste. The aim was to evaluate processes for the demonstration of the suitability of a final repository for heat-producing radioactive waste in cristalline rock, to investigate the thermic, mechanic and hydraulic reactions to an artificial heat source, and to develop corresponding calculating models. The duration of the tests was about 3 years. In this report the measured thermic, mechanic and hydraulic reactions are documented and discussed in detail. A simple, rotation symmetrical FEM-model was used for the preparatory and experiment-accompanying modelling of the thermomechanical conditions in the heat test. The test showed that suitable measuring methods for the surveillance of the geomechanics of a final repository are available and that the reactions of the crystalline host rock to the heat source remain locally limited and can be modelled with relatively small effort. 29 refs., 33 figs., 10 tabs

  12. Archaeology audit program final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-04-15

    In order to review oil and gas companies' archaeological management systems, the British Columbia Oil and Gas Commission (OGC) introduced its archaeology audit program (AAP) in April 2008. As part of this audit, twenty six oil and gas companies were selected for an office documentation review and a corresponding field audit. This document presented and described these audit results. The purpose of the final audit report was to provide information to assist oil and gas companies to improve their management systems by increasing the emphasis of the preservation of cultural resources. This report presented an overview of the AAP scope and methodology and provided examples from the audit of both good management practices encountered and practices in which opportunities for improvement to archaeological management systems could be implemented. Recommendations to address improvement opportunities were also discussed. It was concluded that the oil and gas companies subject to the audit were found to have met or exceeded OGC expectations for maintaining archaeological management systems. 2 tabs., 7 figs.

  13. Readability Levels of the Reading Passages in the ITED: Final Report. Iowa Testing Programs Research Report. Number 6.

    Science.gov (United States)

    Forsyth, Robert

    The readability level of passages from three subtests of the Iowa Tests of Educational Development (ITED), Forms X-6 and Y-6, were compared with the readability level of passages selected from the Des Moines Resister, Reader's Digest, Time, Newsweek, Saturday Review, and 18 high school textbooks from the fields of social studies, science, and…

  14. Polymer systems testing: Final report

    International Nuclear Information System (INIS)

    1993-01-01

    Los Alamos National Laboratory (LANL) is in the process of decontaminating lead shielding material. The procedure involves abrasive surface etching of the shielding to remove the outer layer of lead that contains the majority of the radioactive contaminants. This procedure generates a small volume of mixed waste in the form of a wet residue containing lead, abrasive grit (Al 2 O 3 ), uranium and water. IC Technologies, Inc. (ICT) has developed several processes for the treatment of mixed wastes involving stabilizing/encapsulating the waste in a polymer monolith. The objective of the test program was to verify the applicability of ICT's technology to this specific waste stream and provide LANL baseline data on the performance of polymer encapsulation techniques. Polymer microencapsulation of lead shielding/blasting grit (surrogate) mixed waste was evaluated. Two polymers, melamine formaldehyde and polyester xylene, were used to examine the effect of waste loading on Toxicity Characteristic Leaching Procedure (TCLP) extract Pb concentration. Six levels of waste loading were evaluated by eleven tests. Significant reduction in Pb solubility during TCLP was achieved. Additional optimization to the single-stage microencapsulation technique utilized will be necessary to mitigate the toxic (RCRA) characteristic of the waste

  15. Neighborhood electric vehicle market test development project: Sacramento electric transportation consortium Ra 93-23 program. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Warf, W.R.

    1997-02-01

    The neighborhood electric vehicle (NEV) niche is the object of this market and product test project. The project availed itself of a limited production three wheel, single passenger low performance NEV designed and produced in Denmark to determine the acceptability of the design for production and use in North America. This vehicle, as well as a prototype four wheel vehicle designed and constructed through this project, are entirely reinforced plastic chassis and body. Pacific Electric Vehicles was the primary participant in the Project. Included are the evaluation of drive system components, battery charging schemes, body and chassis and glazing material suitability. The project determined and/or verified many of the realities of motor vehicle development and usage in the U.S., which remain more restrictive than elsewhere. Statistical usage data, maintenance requirements, and user experiences are reported and analyzed.

  16. Bisphenol A; Final Test Rule

    Science.gov (United States)

    EPA is issuing a final rule, under section 4 of the Toxic Substances Control Act (TSCA) requiring manufacturers and processors of bisphenol A, hereinafter BPA, (4.4’-isopropylidenediphenol, CAS No. 80-05—7) to conduct a 90-day inhalation study.

  17. Relay test program

    International Nuclear Information System (INIS)

    Bandyopadhyay, K.K.; Kunkel, C.; Shteyngart, S.

    1994-02-01

    This report presents the results of a relay test program conducted by Brookhaven National Laboratory (BNL) under the sponsorship of the US Nuclear Regulatory Commission (NRC). The program is a continuation of an earlier test program the results of which were published in NUREG/CR-4867. The current program was carried out in two phases: electrical testing and vibration testing. The objective was primarily to focus on the electrical discontinuity or continuity of relays and circuit breaker tripping mechanisms subjected to electrical pulses and vibration loads. The electrical testing was conducted by KEMA-Powertest Company and the vibration testing was performed at Wyle Laboratories, Huntsville, Alabama. This report discusses the test procedures, presents the test data, includes an analysis of the data and provides recommendations regarding reliable relay testing

  18. DOE Matching Grant Program; FINAL

    International Nuclear Information System (INIS)

    Dr Marvin Adams

    2002-01-01

    OAK 270 - The DOE Matching Grant Program provided$50,000.00 to the Dept of N.E. at TAMU, matching a gift of$50,000.00 from TXU Electric. The$100,000.00 total was spent on scholarships, departmental labs, and computing network

  19. Final Empirical Test Case Specification

    DEFF Research Database (Denmark)

    Kalyanova, Olena; Heiselberg, Per

    This document includes the empirical specification on the IEA task of evaluation building energy simulation computer programs for the Double Skin Facades (DSF) constructions. There are two approaches involved into this procedure, one is the comparative approach and another is the empirical one....

  20. Testing of GFL Geosiphon; FINAL

    International Nuclear Information System (INIS)

    Steimke, J.L.

    2001-01-01

    A full-scale, transparent replica of a GeoSiphon was constructed in the TFL to test a new concept, using a solar powered vacuum pump to remove accumulated gases from the air chamber. It did not have a treatment cell containing iron filings as do the actual TNX GeoSiphons in the field, but it was accurate in all other respects. The gas generation that is observed in an actual GeoSiphon was simulated by air injection at the inlet of the TFL GeoSiphon. After facility shakedown, three stages of testing were conducted: verification testing, parametric testing and long term testing. In verification testing, the TFL GeoSiphon was used to reproduce a particular test at TNX in which the water flowrate decreased gradually as the result of air accumulation at the crest of a siphon without an air chamber. For this test the vacuum pump was not used and the air chamber was initially filled with air rather than water. Agreement between data from the TNX GeoSiphon and the TFL GeoSiphon was good, which gave confidence that the TFL GeoSiphon was a good hydraulic representation of the TNX GeoSiphon. For the remaining tests, the solar powered vacuum pump and air chamber were used. In parametric testing, steady state runs were made for water flowrates ranging from 1 gpm to 19 gpm, air injection rates ranging from 0 to 77 standard cc/min and outfall line angles ranging from vertical to 60 degrees from vertical. In all cases, the air chamber and vacuum pump removed nearly all of the air and the GeoSiphon operated without problems. In long term testing, the GeoSiphon was allowed to run continuously for 21 days at one set of conditions. During this time the solar cell kept the storage battery fully charged at all times and the control circuit for the vacuum pump operated reliably. The solar panel was observed to have a large excess capacity when used with the vacuum pump. With two changes, the concept of using a solar powered vacuum pump attached to an air chamber should be ready for long

  1. Manipulator comparative testing program

    International Nuclear Information System (INIS)

    Draper, J.V.; Handel, S.J.; Sundstrom, E.; Herndon, J.N.; Fujita, Y.; Maeda, M.

    1986-01-01

    The Manipulator Comparative Testing Program examined differences among manipulator systems from the United States and Japan. The manipulator systems included the Meidensha BILARM 83A, the Model M-2 of Central Research Laboratories Division of Sargent Industries (CRL), and the GCA Corporation PaR Systems Model 6000. The site of testing was the Remote Operations Maintenance Demonstration (ROMD) facility, operated by the Fuel Recycle Division in the Consolidated Fuel Reprocessing Program at the Oak Ridge National Laboratory (ORNL). In all stages of testing, operators using the CRL Model M-2 manipulator had consistently lower times to completion and error rates than they did using other machines. Performance was second best with the Meidensha BILARM 83A in master-slave mode. Performance with the BILARM in switchbox mode and the PaR 6000 manipulator was approximately equivalent in terms of criteria recorded in testing. These data show no impact of force reflection on task performance

  2. Electrodril system field test program. Phase II: Task C-1-deep drilling system demonstration. Final report for Phase II: Task C-1

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, P D

    1981-04-01

    The Electrodril Deep Drilling System field test demonstrations were aborted in July 1979, due to connector problems. Subsequent post test analyses concluded that the field replacable connectors were the probable cause of the problems encountered. The designs for both the male and female connectors, together with their manufacturing processes, were subsequently modified, as was the acceptance test procedures. A total of nine male and nine female connectors were manufactured and delivered during the 2nd Quarter 1980. Exhaustive testing was then conducted on each connector as a precursor to formal qualification testing conducted during the month of October 1980, at the Brown Oil Tool test facility located in Houston, Texas. With this report, requirements under Phase II, Task C-1 are satisfied. The report documents the results of the connector qualification test program which was successfully completed October 28, 1980. In general, it was concluded that connector qualification had been achieved and plans are now in progress to resume the field test demonstration program so that Electrodril System performance predictions and economic viability can be evaluated.

  3. Program Development Plan and Team up; FINAL

    International Nuclear Information System (INIS)

    Solar Electric Power Association

    2001-01-01

    The final summary report is a comprehensive view of TEAM-UP, with documented data, information, and experiences that SEPA has collected throughout the program, including lessons learned by participating ventures, and sections covering costs and other information on both large and small systems. This report also covers the barriers that TEAM-UP faced to PV commercialization at the beginning of the program, barriers the project was able to remove or reduce, and what barriers remain on the road ahead

  4. NCSU reactor sharing program. Final technical report

    International Nuclear Information System (INIS)

    Perez, P.B.

    1997-01-01

    The Nuclear Reactor Program at North Carolina State University provides the PULSTAR Research Reactor and associated facilities to eligible institutions with support, in part, from the Department of Energy Reactor Sharing Program. Participation in the NCSU Reactor Sharing Program continues to increase steadily with visitors ranging from advance high school physics and chemistry students to Ph.D. level research from neighboring universities. This report is the Final Technical Report for the DOE award reference number DE-FG05-95NE38136 which covers the period September 30, 1995 through September 30, 1996

  5. Innovative Technology Development Program. Final summary report

    International Nuclear Information System (INIS)

    Beller, J.

    1995-08-01

    Through the Office of Technology Development (OTD), the U.S. Department of Energy (DOE) has initiated a national applied research, development, demonstration, testing, and evaluation program, whose goal has been to resolve the major technical issues and rapidly advance technologies for environmental restoration and waste management. The Innovative Technology Development (ITD) Program was established as a part of the DOE, Research, Development, Demonstration, Testing, and Evaluation (RDDT ampersand E) Program. The plan is part of the DOE's program to restore sites impacted by weapons production and to upgrade future waste management operations. On July 10, 1990, DOE issued a Program Research and Development Announcement (PRDA) through the Idaho Operations Office to solicit private sector help in developing innovative technologies to support DOE's clean-up goals. This report presents summaries of each of the seven projects, which developed and tested the technologies proposed by the seven private contractors selected through the PRDA process

  6. The final focus test beam project

    International Nuclear Information System (INIS)

    Burke, D.

    1991-05-01

    An overview is given of the Final Focus Test Beam (FFTB) that is being constructed as a prototype final focus system for a future electron-positron linear collider. This beam line will use as input the 50 GeV electron beam from the SLC linac, and is designed to reduce the transverse dimensions of the beam spot at the focal point to 1 μm. 5 refs., 2 figs., 1 tab

  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

    International Nuclear Information System (INIS)

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

    1987-09-01

    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. BWR Refill-Reflood Program. Final report

    International Nuclear Information System (INIS)

    Myers, L.L.

    1983-09-01

    The BWR Refill-Reflood Program is part of the continuing Loss of Coolant Accident (LOCA) research in the United States which is jointly sponsored by the Nuclear Regulatory Commission, the Electric Power Research Institute, and the General Electric Company. The current program expanded the focus of this research to include full scale experimental evaluations of multidimensional and multichannel effects during system refill. The program has also made major contributions to the BWR version of the Transient Reactor Analysis Code (TRAC) which has been developed cooperatively with the Idaho National Engineering Laboratory (INEL) for application to BWR transients. A summary description of the complete program is provided including the principal findings and main conclusions of the program. The results of the program have shown that multidimensional and parallel channel effects have the potential to significantly improve the system response over that observed in single channel tests

  9. Dresden 1 plutonium recycle program. Final report

    International Nuclear Information System (INIS)

    Bresnick, S.D.

    1980-01-01

    This is the final report on the Dresden 1 Plutonium Recycle Demonstration Program. It covers the work performed from July 1, 1978 to completion, which includes in-pool inspection of two fuel assemblies, removal of two fuel rods, and post-irradiation examination (PIE) of six fuel rods. Appendix A describes the inspection and rod removal operations, and Appendix B describes the PIE work

  10. Navy radon assessment and mitigation program: Final report

    International Nuclear Information System (INIS)

    1994-10-01

    This final report encompasses the events from the beginning of the Navy Radon Assessment and Mitigation Program to the closure of the program on October 31, 1994. Included in the report are discussions of the phases of the program including screening, assessment, mitigation, and post-mitigation. The primary discussion involves screening and assessment. The report addresses recommendations made to the Naval Facilities Engineering Command by the Hazardous Waste Remedial Actions Program of Martin Marietta Energy Systems, Inc., and the final decisions that were made. Special emphasis is placed on quality assurance/quality control (QA/QC), since QA/QC was given top priority during the implementation of this program. Included in the discussion on QA/QC are ana overview of the measurement process, positive and negative controls, replicated measurements, and application of chamber exposures to data calibration. The report concludes with a discussion of testing considerations for naval facilities and radon mitigation considerations for the Department of the Navy

  11. Providing Transparency and Credibility: The Selection of International Students for Australian Universities. An Examination of the Relationship between Scores in the International Student Admissions Test (ISAT), Final Year Academic Programs and an Australian University's Foundation Program

    Science.gov (United States)

    Lai, Kelvin; Nankervis, Susan; Story, Margot; Hodgson, Wayne; Lewenberg, Michael; Ball, Marita MacMahon

    2008-01-01

    Throughout 2003-04 five cohorts of students in their final year of school studies in various Malaysian colleges and a group of students completing an Australian university foundation year in Malaysia sat the International Student Admissions Test (ISAT). The ISAT is a multiple-choice test of general academic abilities developed for students whose…

  12. Final report on testing of ACONF technology for the US Coast Guard National Distress Systems : a study for the DOE Energy Storage Systems Program.

    Energy Technology Data Exchange (ETDEWEB)

    Storey, Leanne M.; Byrd, Thomas M., Jr.; Murray, Aaron T.; Ginn, Jerry W.; Symons, Philip C. (Electrochemical Engineering Consultants, Inc., Morgan Hill, CA); Corey, Garth P.

    2005-08-01

    This report documents the results of a six month test program of an Alternative Configuration (ACONF) power management system design for a typical United States Coast Guard (USCG) National Distress System (NDS) site. The USCG/USDOE funded work was performed at Sandia National Laboratories to evaluate the effect of a Sandia developed battery management technology known as ACONF on the performance of energy storage systems at NDS sites. This report demonstrates the savings of propane gas, and the improvement of battery performance when utilizing the new ACONF designs. The fuel savings and battery performance improvements resulting from ACONF use would be applicable to all current NDS sites in the field. The inherent savings realized when using the ACONF battery management design was found to be significant when compared to battery replacement and propane refueling at the remote NDS sites.

  13. Results of Final Focus Test Beam

    Energy Technology Data Exchange (ETDEWEB)

    Walz, Dieter R

    2003-06-13

    The beam experiments of Final Focus Test Beam (FFTB) started in September 1993 at SLAC, and have produced a 1.7 {micro}m x 75 nm spot of 46 GeV electron beam. A number of new techniques involving two nanometer spot-size monitors have been developed. Several beam diagnostic/tuning schemes are applied to achieve and maintain the small spot. This experiment opens the way toward the nanometer world for future linear colliders.

  14. N Area Final Project Program Plan

    International Nuclear Information System (INIS)

    Day, R.S.; Duncan, G.M; Trent, S.J.

    1998-07-01

    The N Area Final Project Program Plan is issued for information and use by the U.S. Department of Energy (DOE), the Environmental Restoration Contractor (ERC) for the Hanford Site, and other parties that require workscope knowledge for the deactivation of N Reactor facilities and remediation of the 100-N Area. This revision to the program plan contains the updated critical path schedule to deactivate N Reactor and its supporting facilities, cleanout of the N Reactor Fuel Storage Basin (105-N Basin), and remediate the 100-N Area. This document reflects notable changes in the deactivation plan for N Reactor, including changes in deactivation status, the N Basin cleanout task, and 100-N Area remediation

  15. 83-inch cyclotron research program. Final report

    International Nuclear Information System (INIS)

    Parkinson, W.C.

    1983-07-01

    In June of 1960 the US Atomic Energy Commission authorized the construction of a modern variable energy cyclotron facility at The University of Michigan to be used for research in nuclear spectroscopy. The Legislature of the State of Michigan made available funds for construction of a building to house the 83-inch cyclotron and auxiliary equipment as well as the University's remodeled 42-inch cyclotron. The research program centered around the 83-inch cyclotron was funded by the AEC and its successors, the Energy Research and Development Administration (ERDA) and the Department of Energy (DOE), from September 1964 through March 1977. The program represented a continuation of the research effort using the 42-inch cyclotron facility which had been supported continuously by the AEC since February 1950. This final report to DOE briefly describes the research facility, the research program, and highlights the principal accomplishments of the effort. It begins with a historical note to place this effort within the context of nuclear physics research in the Department of Physics of the University of Michigan

  16. Underground Nuclear Testing Program, Nevada Test Site

    International Nuclear Information System (INIS)

    1975-09-01

    The Energy Research and Development Administration (ERDA) continues to conduct an underground nuclear testing program which includes tests for nuclear weapons development and other tests for development of nuclear explosives and methods for their application for peaceful uses. ERDA also continues to provide nuclear explosive and test site support for nuclear effects tests sponsored by the Department of Defense. This Supplement extends the Environmental Statement (WASH-1526) to cover all underground nuclear tests and preparations for tests of one megaton (1 MT) or less at the Nevada Test Site (NTS) during Fiscal Year 1976. The test activities covered include numerous continuing programs, both nuclear and non-nuclear, which can best be conducted in a remote area. However, if nuclear excavation tests or tests of yields above 1 MT or tests away from NTS should be planned, these will be covered by separate environmental statements

  17. AISI Direct Steelmaking Program. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    Aukrust, E.

    1994-08-01

    This final report deals with the results of a 5-yr project for developing a more energy-efficient, environmentally friendly, less costly process for producing hot metal than current coke ovens and blast furnaces. In the process, iron ore pellets are smelted in a foamy slag created by reaction of coal char with molten slag to produce CO. The CO further reacts with oxygen, which also reacts with coal volatile matter, to produce the heat necessary to sustain the endothermic reduction reaction. The uncombusted CO and H{sub 2} from the coal are used to preheat and prereduce hematite pellets for the most efficient use of the energy in the coal. Laboratory programs confirmed that the process steps worked. Pilot plant studies were successful. Economic analysis for a 1 million tpy plant is promising.

  18. Spacecraft fabrication and test MODIL. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Saito, T.T.

    1994-05-01

    This report covers the period from October 1992 through the close of the project. FY 92 closed out with the successful briefing to industry and with many potential and important initiatives in the spacecraft arena. Due to the funding uncertainties, we were directed to proceed as if our funding would be approximately the same as FY 92 ($2M), but not to make any major new commitments. However, the MODIL`s FY 93 funding was reduced to $810K and we were directed to concentrate on the cryocooler area. The cryocooler effort completed its demonstration project. The final meetings with the cryocooler fabricators were very encouraging as we witnessed the enthusiastic reception of technology to help them reduce fabrication uncertainties. Support of the USAF Phillips Laboratory cryocooler program was continued including kick-off meetings for the Prototype Spacecraft Cryocooler (PSC). Under Phillips Laboratory support, Gill Cruz visited British Aerospace and Lucas Aerospace in the United Kingdom to assess their manufacturing capabilities. In the Automated Spacecraft & Assembly Project (ASAP), contracts were pursued for the analysis by four Brilliant Eyes prime contractors to provide a proprietary snap shot of their current status of Integrated Product Development. In the materials and structure thrust the final analysis was completed of the samples made under the contract (``Partial Automation of Matched Metal Net Shape Molding of Continuous Fiber Composites``) to SPARTA. The Precision Technologies thrust funded the Jet Propulsion Laboratory to prepare a plan to develop a Computer Aided Alignment capability to significantly reduce the time for alignment and even possibly provide real time and remote alignment capability of systems in flight.

  19. Industry to Education Technical Transfer Program & Composite Materials. Composite Materials Course. Fabrication I Course. Fabrication II Course. Composite Materials Testing Course. Final Report.

    Science.gov (United States)

    Massuda, Rachel

    These four reports provide details of projects to design and implement courses to be offered as requirements for the associate degree program in composites and reinforced plastics technology. The reports describe project activities that led to development of curricula for four courses: composite materials, composite materials fabrication I,…

  20. Final Environmental Impact Statement Resource Programs

    International Nuclear Information System (INIS)

    1993-02-01

    BPA's preferred alternative is the Emphasize Conservation Alternative. System and environmental costs are low. Environmental impacts from conservation are minimal. This alternative is cost-effective and environmentally responsible; only the High Conservation Alternative has lower costs and fewer environmental impacts. However, there is some concern about the cost-effectiveness, reliability, and commercial availability of the high conservation resources. If the supply of the additional conservation potential was confirmed and it became cost-effective, the High Conservation Alternative would be preferred. The Draft Resource Programs EIS was released for public review during the summer of 1992. Comments received by letter or in the public hearing held June 16, 1992, were used to revise and update data and analyses of the EIS (public comments and BPA's responses are contained in Volume III of the Final EIS). In addition, a number of revisions were made in the Chapter 3 material describing each resource type, and in Chapter 4 and the Summary, to assure consistency with the modeling and analysis in Chapter 5. Additional information about the capacity aspects of each resource type and alternative has been added, and the material on conservation and its impacts has been reorganized

  1. In-situ test programs related to design and construction of high-level nuclear waste (HLW) deep geologic repositories. Final report (Task 2), June 1981-November 1982

    International Nuclear Information System (INIS)

    Roberds, W.; Bauhof, F.; Gonano, L.

    1983-03-01

    The media and sites considered include (1) basalt at Hanford, Washington; (2) tuff at Yucca Mountain, Nevada Test Site; (3) domal salt at specific Gulf Coast sites; (4) bedded salt at an unspecified site; and (5) granite at an unspecified site. A licensing perspective is outlined and a defensible rationale developed and utilized for the test selection process. This rationale essentially consists of: establishing the information needs for construction authorization; assessing the relevant capabilities of available tests; and matching the capabilities of specific tests to the perceived information needs. The information needs at any time consist of the additional information (if any) needed in order to predict satisfactory repository system performance with the required level of confidence, and thus are a function of: the significance of the repository engineered components and site characteristics to system performance; the currently available information, which may be supplemented with time; and the acceptable level of confidence in satisfactory performance for each licensing step. Determination of the acceptable levels of confidence and the significance of repository system components is outside the scope of this report. Suitable assumptions have thus been made regarding the development of information needs for construction authorization by the time of initial site submittals. Tests which are available and respond to the perceived media/site specific information needs, either by simulation or assessment of site characteristics, are identified and their capabilities assessed. Specific in situ tests are investigated and described in detail. Research and development which might be effective in improving test capabilities have been recommended

  2. Temperature Buffer Test. Final THM modelling

    International Nuclear Information System (INIS)

    Aakesson, Mattias; Malmberg, Daniel; Boergesson, Lennart; Hernelind, Jan; Ledesma, Alberto; Jacinto, Abel

    2012-01-01

    The Temperature Buffer Test (TBT) is a joint project between SKB/ANDRA and supported by ENRESA (modelling) and DBE (instrumentation), which aims at improving the understanding and to model the thermo-hydro-mechanical behavior of buffers made of swelling clay submitted to high temperatures (over 100 deg C) during the water saturation process. The test has been carried out in a KBS-3 deposition hole at Aespoe HRL. It was installed during the spring of 2003. Two heaters (3 m long, 0.6 m diameter) and two buffer arrangements have been investigated: the lower heater was surrounded by bentonite only, whereas the upper heater was surrounded by a composite barrier, with a sand shield between the heater and the bentonite. The test was dismantled and sampled during the winter of 2009/2010. This report presents the final THM modelling which was resumed subsequent to the dismantling operation. The main part of this work has been numerical modelling of the field test. Three different modelling teams have presented several model cases for different geometries and different degree of process complexity. Two different numerical codes, Code B right and Abaqus, have been used. The modelling performed by UPC-Cimne using Code B right, has been divided in three subtasks: i) analysis of the response observed in the lower part of the test, by inclusion of a number of considerations: (a) the use of the Barcelona Expansive Model for MX-80 bentonite; (b) updated parameters in the vapour diffusive flow term; (c) the use of a non-conventional water retention curve for MX-80 at high temperature; ii) assessment of a possible relation between the cracks observed in the bentonite blocks in the upper part of TBT, and the cycles of suction and stresses registered in that zone at the start of the experiment; and iii) analysis of the performance, observations and interpretation of the entire test. It was however not possible to carry out a full THM analysis until the end of the test due to

  3. Temperature Buffer Test. Final THM modelling

    Energy Technology Data Exchange (ETDEWEB)

    Aakesson, Mattias; Malmberg, Daniel; Boergesson, Lennart; Hernelind, Jan [Clay Technology AB, Lund (Sweden); Ledesma, Alberto; Jacinto, Abel [UPC, Universitat Politecnica de Catalunya, Barcelona (Spain)

    2012-01-15

    The Temperature Buffer Test (TBT) is a joint project between SKB/ANDRA and supported by ENRESA (modelling) and DBE (instrumentation), which aims at improving the understanding and to model the thermo-hydro-mechanical behavior of buffers made of swelling clay submitted to high temperatures (over 100 deg C) during the water saturation process. The test has been carried out in a KBS-3 deposition hole at Aespoe HRL. It was installed during the spring of 2003. Two heaters (3 m long, 0.6 m diameter) and two buffer arrangements have been investigated: the lower heater was surrounded by bentonite only, whereas the upper heater was surrounded by a composite barrier, with a sand shield between the heater and the bentonite. The test was dismantled and sampled during the winter of 2009/2010. This report presents the final THM modelling which was resumed subsequent to the dismantling operation. The main part of this work has been numerical modelling of the field test. Three different modelling teams have presented several model cases for different geometries and different degree of process complexity. Two different numerical codes, Code{sub B}right and Abaqus, have been used. The modelling performed by UPC-Cimne using Code{sub B}right, has been divided in three subtasks: i) analysis of the response observed in the lower part of the test, by inclusion of a number of considerations: (a) the use of the Barcelona Expansive Model for MX-80 bentonite; (b) updated parameters in the vapour diffusive flow term; (c) the use of a non-conventional water retention curve for MX-80 at high temperature; ii) assessment of a possible relation between the cracks observed in the bentonite blocks in the upper part of TBT, and the cycles of suction and stresses registered in that zone at the start of the experiment; and iii) analysis of the performance, observations and interpretation of the entire test. It was however not possible to carry out a full THM analysis until the end of the test due to

  4. Accelerated test program

    Science.gov (United States)

    Ford, F. E.; Harkness, J. M.

    1977-01-01

    A brief discussion on the accelerated testing of batteries is given. The statistical analysis and the various aspects of the modeling that was done and the results attained from the model are also briefly discussed.

  5. Now Enhancing Working Skills: The ``NEWS`` Program. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Kuiper, A. [Merex Corp. (United States)

    1995-01-23

    In October of 1992, Los Alamos National Laboratory and Merex Corporation began a pilot basic skills program to enhance workers` skills. The program, known as the NEWS (Now Enhancing Working Skills) Program, was implemented by the Training and Development Group of the Human Resources Division. A group of 106 employees known as Radiological Control Technicians (RCTs) from ESH-1 (Environmental, Safety, and Health) were targeted to take mandated DOE (Department of Energy) training. The main goal of the LANL/Merex partnership was to help RCTs prepare for mandated DOE Rad Con training and job performance by improving their information processing and math skills. A second goal of this project was to use the information from this small group to make some predictions about the Laboratory as a whole. This final report contains the description and an appendix for the ``NEWS`` program. The topics in this report include Merex class descriptions, test score results for the MAT, the WAT, the TABE, and Challenge test, a follow-up survey to Merex IPS and math training, student feedback statistics for skills programs, and lessons learned from the program.

  6. Study of a spherical torus based volumetric neutron source for nuclear technology testing and development. Final report of a scientific research supported by the USDOE/SBIR program

    International Nuclear Information System (INIS)

    Cheng, E.T.

    1999-01-01

    A plasma based, deuterium and tritium (DT) fueled, volumetric 14 MeV neutron source (VNS) has been considered as a possible facility to support the development of the demonstration fusion power reactor (DEMO). It can be used to test and develop necessary fusion blanket and divertor components and provide sufficient database, particularly on the reliability of nuclear components necessary for DEMO. The VNS device complement to ITER by reducing the cost and risk in the development of DEMO. A low cost, scientifically attractive, and technologically feasible volumetric neutron source based on the spherical torus (ST) concept has been conceived. The ST-VNS, which has a major radius of 1.07 m, aspect ratio 1.4, and plasma elongation 3, can produce a neutron wall loading from 0.5 to 5 MW/m 2 at the outboard test section with a modest fusion power level from 38 to 380 MW. It can be used to test necessary nuclear technologies for fusion power reactor and develop fusion core components include divertor, first wall, and power blanket. Using staged operation leading to high neutron wall loading and optimistic availability, a neutron fluence of more than 30 MW-y/m 2 is obtainable within 20 years of operation. This will permit the assessments of lifetime and reliability of promising fusion core components in a reactor relevant environment. A full scale demonstration of power reactor fusion core components is also made possible because of the high neutron wall loading capability. Tritium breeding in such a full scale demonstration can be very useful to ensure the self-sufficiency of fuel cycle for a candidate power blanket concept

  7. Workplace Wellness Programs Study: Final Report

    OpenAIRE

    Mattke, Soeren; Liu, Hangsheng; Caloyeras, John; Huang, Christina Y.; Van Busum, Kristin R.; Khodyakov, Dmitry; Shier, Victoria

    2013-01-01

    This article investigates the characteristics of workplace wellness programs, their prevalence, their impact on employee health and medical cost, facilitators of their success, and the role of incentives in such programs.

  8. Environmental Assessment : Squawfish Management Program : Final.

    Energy Technology Data Exchange (ETDEWEB)

    United States. Bonneville Power Administration.

    1992-05-01

    Bonneville Power Administration (BPA) proposes to decrease the number of northern squawfish (Ptychocheilus oregonensis) in reservoirs in the Columbia River system. The goal of the Squawfish Management Program is to reduce losses of outmigrating juvenile salmon and steelhead (salmonids) to northern squawfish predation. The objective is to reduce the number of northern squawfish that feed on juvenile salmonids (smolts) by 10 to 20 percent to alter the age and size structure of the northern squawfish population. The hypothesis, based on computer modeling, indicates that sustained northern squawfish harvest (5 to 10 years) and the resultant population restructuring may reduce losses of juvenile salmonids to predation by up to 50 percent or more within 10 years. The proposed action would target northern squawfish 11 inches and longer, the size in which northern squawfish being preying significantly on juvenile salmonids. BPA proposes to fund three types of fisheries to harvest northern squawfish. BPA also proposes to fund monitoring activities of these fisheries to determine whether desired or other results occur. The three fisheries methods proposed are: (1) commercial Tribal fishing; (2) sport reward fishing; and (3) fishing from restricted areas of each dam ( dam angling''). These fisheries were tested in 1990 and 1991.

  9. TMI-2 instrumentation and electrical program final evaluation report

    International Nuclear Information System (INIS)

    Mayo, C.W.; Huzdovich, J.W.; Roby, A.R.; Test, L.D.

    1986-11-01

    This report presents the authors collective opinions on the value to the nuclear industry of the various investigations performed at TMI-2 by the Instrumentation and Electrical Program. The authors demonstrate that more attention must be given to the prevention of moisture intrusion during design, construction, operation, and maintenance of a nuclear power plant. They also point out that, while basic engineering designs of instruments are more than adequate, the applications engineering and specifications could be improved. Finally, they show that advanced testing technology, exemplified by the Electrical Circuit Characterization and Diagnostics (ECCAD) System, may be very useful as a diagnostic tool when used as part of the testing or maintenance program in a nuclear power plant

  10. The testing effect for mediator final test cues and related final test cues in online and laboratory experiments

    NARCIS (Netherlands)

    L.C. Coppens; P.P.J.L. Verkoeijen; S. Bouwmeester; R.M.J.P. Rikers

    2016-01-01

    Background The testing effect is the finding that information that is retrieved during learning is more often correctly retrieved on a final test than information that is restudied. According to the semantic mediator hypothesis the testing effect arises because retrieval practice of cue-target

  11. The testing effect for mediator final test cues and related final test cues in online and laboratory experiments

    NARCIS (Netherlands)

    Coppens, Leonora C.; Verkoeijen, Peter P. J. L.; Bouwmeester, Samantha; Rikers, Remy M. J. P.

    2016-01-01

    Background The testing effect is the finding that information that is retrieved during learning is more often correctly retrieved on a final test than information that is restudied. According to the semantic mediator hypothesis the testing effect arises because retrieval practice of cue-target pairs

  12. Final Technical Report, reEnergize Program

    Energy Technology Data Exchange (ETDEWEB)

    Wamstad-Evans, Kristi [City of Omaha; Williams, Eric [City of Omaha; Kubicek, Jason [City of Omaha

    2013-12-27

    The reEnergize Program helped to build a market for residential and commercial energy evaluations and upgrades. The program provided incentives to encourage participants to save energy, save money, and make their homes and businesses more safe, healthy, and comfortable. As part of the Better Buildings Neighborhood Program (BBNP), the successful investment of this $10 million grant toward market development was the first grant funding collaboration between the cities of Omaha and Lincoln. Through more than three years of work, thousands of participants, contractors, and community members worked together to make the reEnergize Program a demonstration of how to “Build Energy Smart Communities.”

  13. Test Program Set (TPS) Lab

    Data.gov (United States)

    Federal Laboratory Consortium — The ARDEC TPS Laboratory provides an organic Test Program Set (TPS) development, maintenance, and life cycle management capability for DoD LCMC materiel developers....

  14. Nevada Test Site closure program

    International Nuclear Information System (INIS)

    Shenk, D.P.

    1994-08-01

    This report is a summary of the history, design and development, procurement, fabrication, installation and operation of the closures used as containment devices on underground nuclear tests at the Nevada Test Site. It also addresses the closure program mothball and start-up procedures. The Closure Program Document Index and equipment inventories, included as appendices, serve as location directories for future document reference and equipment use

  15. INEL Geothermal Environmental Program. Final environmental report

    Energy Technology Data Exchange (ETDEWEB)

    Thurow, T.L.; Cahn, L.S.

    1982-09-01

    An overview of environmental monitoring programs and research during development of a moderate temperature geothermal resource in the Raft River Valley is presented. One of the major objectives was to develop programs for environmental assessment and protection that could serve as an example for similar types of development. The monitoring studies were designed to establish baseline conditions (predevelopment) of the physical, biological, and human environment. Potential changes were assessed and adverse environmental impacts minimized. No major environmental impacts resulted from development of the Raft River Geothermal Research Facility. The results of the physical, biological, and human environment monitoring programs are summarized.

  16. Final Test Analysis of Post Graduate Medical Residents

    Directory of Open Access Journals (Sweden)

    Maliheh Arab

    2009-04-01

    Full Text Available Background and purpose: Multiple choice questions are the most frequent test for medical students. It is important to analysis the overall response to individual  questions in the test.The aim of this study is to analyse questions of post graduate medical residency  tests.Methods: Final annual local (Ramadan medical school and national tests given to three Residency groups  including  17 Obstetrics  and gynecology testees,  7 pediatrics  and  12 internal  medicine  in 2004 were studied. In local tests residents answered to 148, 150 and 144 and in national  tests to ISO MCQS. Questions were  evaluated regarding cognitive domain level, Difficultly index and Discriminative index  and finally to evaluate  the optimal,  proper, acceptable and  ''must  omitted" questions.Results: Questions of local Obstetrics and gynecology, pediatrics and internal medicine tests evaluated the "recall" level in 72%, 72% and 51% and in national  tests 71%,  35% and 19%,  respectively. Questions  with  Discriminative indices  of 0.7 or more (proper  were 3 and  5% in  Obstetrics  and gynecology, 3.5% and 1% in pediatrics and 1% in local and national tests. Proper difficulty indices (30-70  were shown in 53% and 54% in Obstetrics  and gynecology, 34% and 43% in pediatrics and 40% and  42% in internal  medicine.  Generally  evaluating,  "must  omitted" questions in local and national tests were 76% in Obstetrics and gynecology, 81% and 79% in pediatrics and 91% and 85% in internal medicine. The most common causes making the questions to be considered  "must omitted" in studied tests were negative, zero or less than 0.2 Discriminative indices.Conclusion: Test analysis  of final  annual  local  (Ramadan medical  school  and national  tests  of Obstetrics  and gynecology, Pediatrics and internal medicine residency  programs  in 2004 revealed that most of the questions  are planned  in  "recall" level, harbor  improper

  17. DECONTAMINATION SYSTEMS AND INFORMATION RESEARCH PROGRAM; FINAL

    International Nuclear Information System (INIS)

    Echol E. Cook, Ph.D., PE.

    1998-01-01

    During the five plus years this Cooperative Agreement existed, more than 45 different projects were funded. Most projects were funded for a one year period but there were some, deemed of such quality and importance, funded for multiple years. Approximately 22 external agencies, businesses, and other entities have cooperated with or been funded through the WVU Cooperative Agreement over the five plus years. These external entities received 33% of the funding by this Agreement. The scope of this Agreement encompassed all forms of hazardous waste remediation including radioactive, organic, and inorganic contaminants. All matrices were of interest; generally soil, water, and contaminated structures. Economic, health, and regulatory aspects of technologies were also within the scope of the agreement. The highest priority was given to small businesses funded by the Federal Energy Technology Center (FETC) and Department of Energy (DOE) involved in research and development of innovative remediation processes. These projects were to assist in the removal of barriers to development and commercialization of these new technologies. Studies of existing, underdeveloped technologies, were preferred to fundamental research into remediation technologies. Sound development of completely new technologies was preferred to minor improvements in existing methods. Solid technological improvements in existing technologies or significant cost reduction through innovative redesign were the preferred projects. Development, evaluation, and bench scale testing projects were preferred for the WVU research component. In the effort to fill gaps in current remediation technologies, the worth of the WVU Cooperative Agreement was proven. Two great technologies came out of the program. The Prefabricated Vertical Drain Technology for enhancing soil flushing was developed over the 6-year period and is presently being demonstrated on a 0.10 acre Trichloroethylene contaminated site in Ohio. The Spin

  18. Space Solar Power Program. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Arif, Humayun; Barbosa, Hugo; Bardet, Christophe; Baroud, Michel; Behar, Alberto; Berrier, Keith; Berthe, Phillipe; Bertrand, Reinhold; Bibyk, Irene; Bisson, Joel; Bloch, Lawrence; Bobadilla, Gabriel; Bourque, Denis; Bush, Lawrence; Carandang, Romeo; Chiku, Takemi; Crosby, Norma; De Seixas, Manuel; De Vries, Joha; Doll, Susan; Dufour, Francois; Eckart, Peter; Fahey, Michael; Fenot, Frederic; Foeckersperger, Stefan; Fontaine, Jean-Emmanuel; Fowler, Robert; Frey, Harald; Fujio, Hironobu; Gasa, Jaume Munich; Gleave, Janet; Godoe, Jostein; Green, Iain; Haeberli, Roman; Hanada, Toshiya; Harris, Peter; Hucteau, Mario; Jacobs, Didier Fernand; Johnson, Richard; Kanno, Yoshitsugu; Koenig, Eva Maria; Kojima, Kazuo; Kondepudi, Phani; Kottbauer, Christian; Kulper, Doede; Kulagin, Konstantin; Kumara, Pekka; Kurz, Rainer; Laaksonen, Jyrki; Lang, Andrew Neill; Lathan, Corinna; Le Fur, Thierry; Lewis, David; Louis, Alain; Mori, Takeshi; Morlanes, Juan; Murbach, Marcus; Nagatomo, Hideo; O' brien, Ivan; Paines, Justin; Palaszewski, Bryan; Palmnaes, Ulf; Paraschivolu, Marius; Pathare, Asmin; Perov, Egor; Persson, Jan; Pessoa-Lopes, Isabel; Pinto, Michel; Porro, Irene; Reichert, Michael; Ritt-Fischer, Monika; Roberts, Margaret; Robertson II, Lawrence; Rogers, Keith; Sasaki, Tetsuo; Scire, Francesca; Shibatou, Katsuya; Shirai, Tatsuya; Shiraishi, Atsushi; Soucaille, Jean-Francois; Spivack, Nova; St. Pierre, Dany; Suleman, Afzal; Sullivan, Thomas; Theelen, Bas Johan; Thonstad, Hallvard; Tsuji, Masatoshi; Uchiumi, Masaharu; Vidqvist, Jouni; Warrell, David; Watanabe, Takafumi; Willis, Richard; Wolf, Frank; Yamakawa, Hiroshi; Zhao, Hong

    1992-08-01

    Information pertaining to the Space Solar Power Program is presented on energy analysis; markets; overall development plan; organizational plan; environmental and safety issues; power systems; space transportation; space manufacturing, construction, operations; design examples; and finance.

  19. Insulating Structural Ceramics Program, Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Andrews, Mark J.; Tandon, Raj; Ott, Eric; Hind, Abi Akar; Long, Mike; Jensen, Robert; Wheat, Leonard; Cusac, Dave; Lin, H. T.; Wereszczak, Andrew A.; Ferber, Mattison K.; Lee, Sun Kun; Yoon, Hyung K.; Moreti, James; Park, Paul; Rockwood, Jill; Boyer, Carrie; Ragle, Christie; Balmer-Millar, Marilou; Aardahl, Chris; Habeger, Craig; Rappe, Ken; Tran, Diana; Koshkarian, Kent; Readey, Michael

    2005-11-22

    turbine community over the last fifty years. Characterization of these high temperature materials has, consequently, concentrated heavily upon application conditions similiar to to that encountered in the turbine engine environment. Significantly less work has been performed on hot corrosion degradation of these materials in a diesel engine environment. This report examines both the current high temperature alloy capability and examines the capability of advanced nickle-based alloys and methods to improve production costs. Microstructures, mechanical properties, and the oxidation/corrosion behavior of commercially available silicon nitride ceramics were investigated for diesel engine valve train applications. Contact, sliding, and scratch damage mechanisms of commercially available silicon nitride ceramics were investigated as a function of microstructure. The silicon nitrides with a course microstructure showed a higher material removal rate that agrees with a higher wear volume in the sliding contact tests. The overall objective of this program is to develop catalyst materials systems for an advanced Lean-NOx aftertreatment system that will provide high NOx reduction with minimum engine fuel efficiency penalty. With Government regulations on diesel engine NOx emissions increasingly becoming more restrictive, engine manufacturers are finding it difficult to meet the regulations solely with engine design strategies (i.e. improved combustion, retarded timing, exhaust gas recirculation, etc.). Aftertreatment is the logical technical approach that will be necessary to achieve the required emission levels while at the same time minimally impacting the engine design and its associated reliability and durability concerns.

  20. Multi-frac test series. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt, R A; Warpinski, N R; Finley, S J; Shear, R C

    1981-11-01

    This paper describes a series of five full-scale tests performed to evaluate various multi-frac concepts. The tests were conducted at the Nevada Test Site in horizontal boreholes drilled in ash-fall tuff from a tunnel under 1300 ft of overburden.

  1. Massachusetts Large Blade Test Facility Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Rahul Yarala; Rob Priore

    2011-09-02

    Project Objective: The Massachusetts Clean Energy Center (CEC) will design, construct, and ultimately have responsibility for the operation of the Large Wind Turbine Blade Test Facility, which is an advanced blade testing facility capable of testing wind turbine blades up to at least 90 meters in length on three test stands. Background: Wind turbine blade testing is required to meet international design standards, and is a critical factor in maintaining high levels of reliability and mitigating the technical and financial risk of deploying massproduced wind turbine models. Testing is also needed to identify specific blade design issues that may contribute to reduced wind turbine reliability and performance. Testing is also required to optimize aerodynamics, structural performance, encourage new technologies and materials development making wind even more competitive. The objective of this project is to accelerate the design and construction of a large wind blade testing facility capable of testing blades with minimum queue times at a reasonable cost. This testing facility will encourage and provide the opportunity for the U.S wind industry to conduct more rigorous testing of blades to improve wind turbine reliability.

  2. Accelerated leach test development program

    International Nuclear Information System (INIS)

    Fuhrmann, M.; Pietrzak, R.F.; Heiser, J.; Franz, E.M.; Colombo, P.

    1990-11-01

    In FY 1989, a draft accelerated leach test for solidified waste was written. Combined test conditions that accelerate leaching were validated through experimental and modeling efforts. A computer program was developed that calculates test results and models leaching mechanisms. This program allows the user to determine if diffusion controls leaching and, if this is the case, to make projections of releases. Leaching mechanisms other than diffusion (diffusion plus source term partitioning and solubility limited leaching) are included in the program is indicators of other processes that may control leaching. Leach test data are presented and modeling results are discussed for laboratory scale waste forms composed of portland cement containing sodium sulfate salt, portland cement containing incinerator ash, and vinyl ester-styrene containing sodium sulfate. 16 refs., 38 figs., 5 tabs

  3. Fusion Simulation Program Definition. Final report

    International Nuclear Information System (INIS)

    Cary, John R.

    2012-01-01

    We have completed our contributions to the Fusion Simulation Program Definition Project. Our contributions were in the overall planning with concentration in the definition of the area of Software Integration and Support. We contributed to the planning of multiple meetings, and we contributed to multiple planning documents

  4. The testing effect for mediator final test cues and related final test cues in online and laboratory experiments.

    Science.gov (United States)

    Coppens, Leonora C; Verkoeijen, Peter P J L; Bouwmeester, Samantha; Rikers, Remy M J P

    2016-05-31

    The testing effect is the finding that information that is retrieved during learning is more often correctly retrieved on a final test than information that is restudied. According to the semantic mediator hypothesis the testing effect arises because retrieval practice of cue-target pairs (mother-child) activates semantically related mediators (father) more than restudying. Hence, the mediator-target (father-child) association should be stronger for retrieved than restudied pairs. Indeed, Carpenter (2011) found a larger testing effect when participants received mediators (father) than when they received target-related words (birth) as final test cues. The present study started as an attempt to test an alternative account of Carpenter's results. However, it turned into a series of conceptual (Experiment 1) and direct (Experiment 2 and 3) replications conducted with online samples. The results of these online replications were compared with those of similar existing laboratory experiments through small-scale meta-analyses. The results showed that (1) the magnitude of the raw mediator testing effect advantage is comparable for online and laboratory experiments, (2) in both online and laboratory experiments the magnitude of the raw mediator testing effect advantage is smaller than in Carpenter's original experiment, and (3) the testing effect for related cues varies considerably between online experiments. The variability in the testing effect for related cues in online experiments could point toward moderators of the related cue short-term testing effect. The raw mediator testing effect advantage is smaller than in Carpenter's original experiment.

  5. DOE Utility Matching Program Final Technical Report

    International Nuclear Information System (INIS)

    Haghighat, Alireza

    2002-01-01

    This is the Final report for the DOE Match Grant (DE-FG02-99NE38163) awarded to the Nuclear and Radiological Engineering (NRE) Department, University of Florida, for the period of September 1999 to January 2002. This grant has been instrumental for maintaining high-quality graduate and undergraduate education at the NRE department. The grant has been used for supporting student entry and retention and for upgrading nuclear educational facilities, nuclear instrumentation, computer facilities, and computer codes to better enable the incorporation of experimental experiences and computer simulations related to advanced light water fission reactor engineering and other advanced reactor concepts into the nuclear engineering course curricula

  6. Resource Programs: Final Environmental Impact Statement

    International Nuclear Information System (INIS)

    1993-02-01

    Every two years, BA prepares a Resource Program, which identifies the resource actions BA will take to meet its obligation to serve the forecasted power requirements of its customers. The Resource Programs Environmental Impact Statement (RPEIS) is a programmatic environmental document that will support decisions made in several future Resource Programs. Environmental documents tiered to this EIS may be prepared on a site-specific basis. The RPEIS includes a description of the environmental effects and mitigation for the various resource types available in order to evaluate the trade-offs among them. It also assesses the environmental impacts of adding thirteen alternative combinations of resources to the existing power system. The alternatives represent the range of actions BA could take to meet its load obligations. Each of the alternatives allows BA to meet the almost 5,000 average megawatt load increase that could occur with high load growth, or an equivalent need for resources caused by a combination of load growth and any future loss of resources

  7. Wilsonville wastewater sampling program. Final report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1983-10-01

    As part of its contrast to design, build and operate the SRC-1 Demonstration Plant in cooperation with the US Department of Energy (DOE), International Coal Refining Company (ICRC) was required to collect and evaluate data related to wastewater streams and wastewater treatment procedures at the SRC-1 Pilot Plant facility. The pilot plant is located at Wilsonville, Alabama and is operated by Catalytic, Inc. under the direction of Southern Company Services. The plant is funded in part by the Electric Power Research Institute and the DOE. ICRC contracted with Catalytic, Inc. to conduct wastewater sampling. Tasks 1 through 5 included sampling and analysis of various wastewater sources and points of different steps in the biological treatment facility at the plant. The sampling program ran from May 1 to July 31, 1982. Also included in the sampling program was the generation and analysis of leachate from SRC product using standard laboratory leaching procedures. For Task 6, available plant wastewater data covering the period from February 1978 to December 1981 was analyzed to gain information that might be useful for a demonstration plant design basis. This report contains a tabulation of the analytical data, a summary tabulation of the historical operating data that was evaluated and comments concerning the data. The procedures used during the sampling program are also documented.

  8. Sanitary Landfill Supplemental Test Final Report

    International Nuclear Information System (INIS)

    Altman, D.J.

    1999-01-01

    This report summarizes the performance of the Sanitary Landfill Supplemental Test data, an evaluation of applicability, conclusions, recommendations, and related information for implementation of this remediation technology at the SRS Sanitary Landfill

  9. Deep Impact's EPO Program: Final Report

    Science.gov (United States)

    McFadden, Lucy-Ann A.; Warner, E. M.; McLaughlin, S.; Behne, J.; Ristvey, J.; Rountree-Brown, M.

    2006-09-01

    NASA's Deep Impact mission sent an impactor spacecraft into the path of periodic comet 9P/Tempel 1 on July 4, 2005. The Education and Public Outreach goals of the mission were to effectively communicate the mission to target audiences, particularly educators and students with an emphasis on critical thinking using science, math and engineering concepts. A second goal was to invite audiences to participate throughout the mission using products and interactive programs. In the six-years of the mission, we built a community of scientists, educators, students, and both amateur and technically proficient astronomers, who brought the excitement of the mission to their own community. The web site was the focus of the program (http://deepimpact.umd.edu or deepimpact.jpl.nasa.gov). A monthly electronic newsletter sent to an ever- growing distribution list kept subscribers up to date on mission activities. A program to send your name to the comet engaged the public. Curriculum enhancements covering the physics of crater formation, nature of comets and a case study in optimized decision-making designed for students are available (http://deepimpact.umd.edu/educ/index.html). Mathematical (http://deepimpact.umd.edu/disczone/challenge.html) and conceptual questions of a technical nature (http://deepimpact.umd.edu/disczone/braintwist.html) are posed and solved in Mission Challenges and Brain Twisters. Materials provided for students and amateur astronomers to acquire comet observing skills are available (http://deepimpact.umd.edu/amateur/index.shtml).The Small Telescope Science Program was a successful pro-amateur collaboration providing information on brightness variations of the comet both before and after impact (http://deepimpact.umd.edu/stsp/). The night, of impact, events were held at public venues around the world where the excitement of a successful mission exploring the inside of a comet was felt. Results are at http://deepimpact.umd.edu/results/index.html. The mission is

  10. FIR laser-development program. Final report

    International Nuclear Information System (INIS)

    Danielwicz, E.J.; Hodges, D.T.

    1980-01-01

    The important features for a source intended for use as a local oscillator in a low noise receiver have been tested on a developmental model of a cw FIR laser package. High output power (45 mW), good long term amplitude stability (+- 3%), high spectral purity and excellent frequency stability have all been demonstrated in the laboratory environment

  11. Nondestructive testing of thermocompression bonds. Final report

    International Nuclear Information System (INIS)

    Hale, G.M.

    1981-02-01

    A Scanning Laser Acoustic Microscope (SLAM) was used to characterize hybrid microcircuit beam lead bonds formed on thin film networks by a thermocompression process. Results from subsequent pull testing show that the SLAM offered no significant advantage over visual inspection for detecting bad bonds. Infrared microscopy and resistance measurements were also reviewed and rejected as being ineffective inspection methods

  12. Amchitka Radiobiological Program. Final report, July 1970-December 1979

    International Nuclear Information System (INIS)

    Sibley, T.H.; Tornberg, L.D.

    1982-11-01

    The Amchitka Radiobiological Program, to collect biological and environmental samples for radiological analyses, began in 1970 and continued through 1979. The principal objective was to determine the extent of radionuclide contamination from worldwide atmospheric fallout and from the detonation of three underground nuclear tests on Amchitka. Leakage of radionuclides from the underground test sites would be suspected if the amount of contamination was significantly greater than could be attributed to worldwide fallout or if an unexpected assemblage of radionuclides was detected. No radionuclides from the underground sites were detected, except for tritium from the Long Shot test (1965) which produced increased tritium concentrations in surface water and freshwater plants near the test site. This final report compiles all previous data into one report and considers the temporal trends in these data. Two naturally occurring radionuclides, 40 K and 7 Be, were the most abundantly occurring radionuclides in most samples; in lichen samples either 137 Cs or 144 Ce had the highest activity. All samples were below applicable Radiation Protection Guides and by 1979 most samples were near or below the statistical detection limits. Increased concentrations of short-lived fallout radionuclides following the Chinese atmospheric tests were found in freshwater and seawater samples and in most indicator organisms

  13. A final test for AMS at ESTEC

    CERN Multimedia

    Paola Catapano

    2010-01-01

    The Alpha Magnetic Spectrometer (AMS) left CERN on Friday 12th February on the first leg of its journey to the International Space Station (ISS). The special convoy carrying the experiment arrived at the European Space Agency’s research and technology centre (ESTEC) in the Netherlands at 4.30 pm on Tuesday 16th February. AMS will then fly to the Kennedy Space Center in Florida before lifting off aboard the space shuttle.   Arrival of the AMS detector at ESTEC in the Netherlands (Credit ESA/Jari Makinen) The transportation of an 8.5-tonne load filled with superfluid helium across Europe is no ordinary shipment. The AMS detector was first inserted into a supporting structure, specially built by the collaboration’s mechanical engineers, then surrounded by protective plastic foil, placed in a box and finally carefully loaded onto the special lorry also carrying a diesel generator running a pump to keep the helium at the right temperature (about 2 K). Its initial destination is ES...

  14. NANA Wind Resource Assessment Program Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Jay Hermanson

    2010-09-23

    NANA Regional Corporation (NRC) of northwest Alaska is located in an area with abundant wind energy resources. In 2007, NRC was awarded grant DE-FG36-07GO17076 by the US Department of Energy's Tribal Energy Program for funding a Wind Resource Assessment Project (WRAP) for the NANA region. The NANA region, including Kotzebue Electric Association (KEA) and Alaska Village Electric Cooperative (AVEC) have been national leaders at developing, designing, building, and operating wind-diesel hybrid systems in Kotzebue (starting in 1996) and Selawik (2002). Promising sites for the development of new wind energy projects in the region have been identified by the WRAP, including Buckland, Deering, and the Kivalina/Red Dog Mine Port Area. Ambler, Shungnak, Kobuk, Kiana, Noorvik & Noatak were determined to have poor wind resources at sites in or very near each community. However, all five of these communities may have better wind resources atop hills or at sites with slightly higher elevations several miles away.

  15. NANA Geothermal Assessment Program Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Jay Hermanson

    2010-06-22

    In 2008, NANA Regional Corporation (NRC) assessed geothermal energy potential in the NANA region for both heat and/or electricity production. The Geothermal Assessment Project (GAP) was a systematic process that looked at community resources and the community's capacity and desire to develop these resources. In October 2007, the US Department of Energy's Tribal Energy Program awarded grant DE-FG36-07GO17075 to NRC for the GAP studies. Two moderately remote sites in the NANA region were judged to have the most potential for geothermal development: (1) Granite Mountain, about 40 miles south of Buckland, and (2) the Division Hot Springs area in the Purcell Mountains, about 40 miles south of Shungnak and Kobuk. Data were collected on-site at Granite Mountain Hot Springs in September 2009, and at Division Hot Springs in April 2010. Although both target geothermal areas could be further investigated with a variety of exploration techniques such as a remote sensing study, a soil geochemical study, or ground-based geophysical surveys, it was recommended that on-site or direct heat use development options are more attractive at this time, rather than investigations aimed more at electric power generation.

  16. Wildlife mitigation program final environmental impact statement

    International Nuclear Information System (INIS)

    1997-03-01

    BPA is responsible for mitigating the loss of wildlife habitat caused by the development of the Federal Columbia River Power System. BPA accomplishes this mitigation by funding projects consistent with those recommended by the Northwest Power Planning Council (Council). The projects are submitted to the Council from Indian Tribes, state agencies, property owners, private conservation groups, and other Federal agencies. future wildlife mitigation actions with potential environmental impacts are expected to include land acquisition and management, water rights acquisition and management, habitat restoration and improvement, installation of watering devices, riparian fencing, and similar wildlife conservation actions. BPA needs to ensure that individual wildlife mitigation projects are planned and managed with appropriate consistency across projects, jurisdictions, and ecosystems, as well as across time. BPA proposes to standardize the planning and implementation of individual wildlife mitigation projects funded by BPA. Alternative 1 is the No Action alternative, i.e., not to establish program-wide standards. Five standardizing (action) alternatives are identified to represent the range of possible strategies, goals, and procedural requirements reasonably applicable to BPA-funded projects under a standardized approach to project planning and implementation. All action alternatives are based on a single project planning process designed to resolve site-specific issues in an ecosystem context and to adapt to changing conditions and information

  17. Single event upset test programs

    International Nuclear Information System (INIS)

    Russen, L.C.

    1984-11-01

    It has been shown that the heavy ions in cosmic rays can give rise to single event upsets in VLSI random access memory devices (RAMs). Details are given of the programs written to test 1K, 4K, 16K and 64K memories during their irradiation with heavy charged ions, in order to simulate the effects of cosmic rays in space. The test equipment, which is used to load the memory device to be tested with a known bit pattern, and subsequently interrogate it for upsets, or ''flips'', is fully described. (author)

  18. Status of CCTF test program

    International Nuclear Information System (INIS)

    Murao, Y.; Iguchi, T.; Sugimoto, J.; Akimoto, H.; Okubo, T.; Okabe, K.

    1984-01-01

    The cylindrical core test facility (CCTF) is one of the facilities of the large scale reflood test program which was initiated in April, 1976. The first series of the CCTF test (CCTF CORE I Test) was completed in April, 1981 and the second series (CCTF Core II Test) has been conducted since April, 1982. In the test, the following has been intended to be examined: (1) The conservativeness of the assumption of the safety analysis with the evaluation model (EM) code. (2) The refill and reflood phenomena for analytical modeling of thermo-hydrodynamics in the core and the system. (3) The validity of the models in the EM code and the application to the best estimate code development. In this paper, presented are the quantative evaluation of the REFLA code and the discussion of some CCTF Core II Test results. The REFLA code consists of REFLA-1D core code developed with the results of small scale tests and a simple system model developed with the results of the CCTF Core I Test. The CCTF Core II Test was perfored for developing more realistic model for the alternative ECCS as well as for the cold leg injection type ECCS

  19. Flammability Assessment Methodology Program Phase I: Final Report

    Energy Technology Data Exchange (ETDEWEB)

    C. A. Loehr; S. M. Djordjevic; K. J. Liekhus; M. J. Connolly

    1997-09-01

    The Flammability Assessment Methodology Program (FAMP) was established to investigate the flammability of gas mixtures found in transuranic (TRU) waste containers. The FAMP results provide a basis for increasing the permissible concentrations of flammable volatile organic compounds (VOCs) in TRU waste containers. The FAMP results will be used to modify the ''Safety Analysis Report for the TRUPACT-II Shipping Package'' (TRUPACT-II SARP) upon acceptance of the methodology by the Nuclear Regulatory Commission. Implementation of the methodology would substantially increase the number of drums that can be shipped to the Waste Isolation Pilot Plant (WIPP) without repackaging or treatment. Central to the program was experimental testing and modeling to predict the gas mixture lower explosive limit (MLEL) of gases observed in TRU waste containers. The experimental data supported selection of an MLEL model that was used in constructing screening limits for flammable VOC and flammable gas concentrations. The MLEL values predicted by the model for individual drums will be utilized to assess flammability for drums that do not meet the screening criteria. Finally, the predicted MLEL values will be used to derive acceptable gas generation rates, decay heat limits, and aspiration time requirements for drums that do not pass the screening limits. The results of the program demonstrate that an increased number of waste containers can be shipped to WIPP within the flammability safety envelope established in the TRUPACT-II SARP.

  20. Automated [inservice testing] IST program

    International Nuclear Information System (INIS)

    Wright, W.M.

    1990-01-01

    There are two methods used to manage a Section XI program: Manual and Automated. The manual method usually consists of hand written records of test results and scheduling requirements. This method while initially lower in cost, results in problems later on in the life of a plant as data continues to accumulate. Automation allows instant access to forty years of test results. Due to the lower cost and higher performance of todays' personal computers, an automated method via a computer program provides an excellent method for managing the vast amount of data that accumulates over the forty year life of a plant. Through the use of a computer, special functions involving this data are available, which through a manual method would not be practical. This paper will describe some of the advantages in using a computer program to manage the Section XI 1ST program. The ISTBASE consists of program code and numerous databases. The source code is written and complied in CLIPPER (tm) language. Graphing routines are performed by dGE (tm) graphics library. Graphs are displayed in EGA form. Since it was estimated that the total complied code, would exceed 640K of ram, overlays through the use of modular programming were used to facilitate the DOS restrictions of 640K ram. The use of overlays still require the user to gain access to ISTBASE through the PASSWORD module. The database files are designed to be compatible with dBASE III+ (tm) data structure. This allows transfer of data between ISTBASE and other database managers/applications. A math co-processor is utilized to speed up calculations on graphs and other mathematical calculations. Program code and data files require a hard disk drive with at least 28 Meg capacity. While ISTBASE will execute on a 8088 based computer, an 80286 computer with a 12 MHz operating speed should be considered the minimum system configuration

  1. Medicaid program; health care-related taxes. Final rule.

    Science.gov (United States)

    2009-06-30

    This rule finalizes our proposal to delay enforcement of certain clarifications regarding standards for determining hold harmless arrangements in the final rule entitled, "Medicaid Program; Health Care-Related Taxes" from the expiration of a Congressional moratorium on enforcement from July 1, 2009 to June 30, 2010.

  2. Sanitary landfill in situ bioremediation optimization test. Final report

    International Nuclear Information System (INIS)

    1996-01-01

    This work was performed as part of a corrective action plan for the Savannah River Site Sanitary Landfill. This work was performed for the Westinghouse Savannah River Company Environmental Restoration Department as part of final implementation of a groundwater remediation system for the SRS Sanitary Landfill. Primary regulatory surveillance was provided by the South Carolina Department of Health and Environmental Control and the US Environmental Protection Agency (Region IV). The characterization, monitoring and remediation systems in the program generally consisted of a combination of innovative and baseline methods to allow comparison and evaluation. The results of these studies will be used to provide input for the full-scale groundwater remediation system for the SRS Sanitary Landfill. This report summarizes the performance of the Sanitary Landfill In Situ Optimization Test data, an evaluation of applicability, conclusions, recommendations, and related information for implementation of this remediation technology at the SRS Sanitary Landfill

  3. VA Dental Insurance Program--federalism. Direct final rule.

    Science.gov (United States)

    2013-10-22

    The Department of Veterans Affairs (VA) is taking direct final action to amend its regulations related to the VA Dental Insurance Program (VADIP), a pilot program to offer premium-based dental insurance to enrolled veterans and certain survivors and dependents of veterans. Specifically, this rule will add language to clarify the limited preemptive effect of certain criteria in the VADIP regulations.

  4. 75 FR 45563 - Terrorism Risk Insurance Program; Final Netting

    Science.gov (United States)

    2010-08-03

    ... DEPARTMENT OF THE TREASURY 31 CFR Part 50 RIN 1505-AC24 Terrorism Risk Insurance Program; Final... Title I of the Terrorism Risk Insurance Act of 2002 (``TRIA'' or ``the Act''), as amended by the Terrorism Risk Insurance Extension Act of 2005 (``Extension Act'') and the Terrorism Risk Insurance Program...

  5. 75 FR 53786 - Senior Community Service Employment Program; Final Rule

    Science.gov (United States)

    2010-09-01

    ... Part IV Department of Labor Employment and Training Administration 20 CFR Part 641 Senior... Administration 20 CFR Part 641 RIN 1205-AB48 and RIN 1205-AB47 Senior Community Service Employment Program; Final... implement changes in the Senior Community Service Employment Program (SCSEP) resulting from the 2006...

  6. Minimum Leakage Condenser Test Program

    International Nuclear Information System (INIS)

    1978-05-01

    This report presents the results and analysis of tests performed on four critical areas of large surface condensers: the tubes, tubesheets, tube/tubesheet joints and the water chambers. Significant changes in operation, service duty and the reliability considerations require that certain existing design criteria be verified and that improved design features be developed. The four critical areas were treated analytically and experimentally. The ANSYS finite element computer program was the basic analytical method and strain gages were used for obtaining experimental data. The results of test and analytical data are compared and recommendations made regarding potential improvement in condenser design features and analytical techniques

  7. DOE Defense Program (DP) safety programs. Final report, Task 003

    International Nuclear Information System (INIS)

    1998-01-01

    The overall objective of the work on Task 003 of Subcontract 9-X52-W7423-1 was to provide LANL with support to the DOE Defense Program (DP) Safety Programs. The effort included the identification of appropriate safety requirements, the refinement of a DP-specific Safety Analysis Report (SAR) Format and Content Guide (FCG) and Comprehensive Review Plan (CRP), incorporation of graded approach instructions into the guidance, and the development of a safety analysis methodologies document. All tasks which were assigned under this Task Order were completed. Descriptions of the objectives of each task and effort performed to complete each objective is provided here

  8. The Advanced Test Reactor Strategic Evaluation Program

    International Nuclear Information System (INIS)

    Buescher, B.J.

    1990-01-01

    A systematic evaluation of safety, environmental, and operational issues has been initiated at the Advanced Test Reactor (ATR). This program, the Strategic Evaluation Program (STEP), provides an integrated review of safety and operational issues against the standards applied to licensed commercial facilities. In the review of safety issues, 18 deviations were identified which required prompt attention. Resolution of these items has been accelerated in the program. An integrated living schedule is being developed to address the remaining findings. A risk evaluation is being performed on the proposed corrective actions and these actions will then be formally ranked in order of priority based on considerations of safety and operational significance. Once the final ranking is completed, an integrated schedule will be developed, which will include considerations of availability of funding and operating schedule. 3 refs., 2 figs

  9. Anthraquinone Final Reporting and Recordkeeping Requirements and Test Rule

    Science.gov (United States)

    EPA is issuing a final rule, under section 4 of the Toxic Substances Control Act (TSCA), requiring manufacturers and processors of 9,10-anthraquinone (CAS No. 84—65—1), hereinafter anthraquinone, to perform testing.

  10. A Monte Carlo program for generating hadronic final states

    International Nuclear Information System (INIS)

    Angelini, L.; Pellicoro, M.; Nitti, L.; Preparata, G.; Valenti, G.

    1991-01-01

    FIRST is a computer program to generate final states from high energy hadronic interactions using the Monte Carlo technique. It is based on a theoretical model in which the high degree of universality in such interactions is related with the existence of highly excited quark-antiquark bound states, called fire-strings. The program handles the decay of both fire-strings and unstable particles produced in the intermediate states. (orig.)

  11. NRC Confirmatory Testing Program for SBWR

    International Nuclear Information System (INIS)

    Han, J.T.; Bessette, D.E.; Shotkin, L.M.

    1994-01-01

    The objective of the NRC Confirmatory Testing Program for SBWR is to provide integral data for code assessment, which reasonably reproduce the important phenomena and processes expected in the SBWR under various loss-of-coolant accident (LOCA) and transient conditions. To achieve this objective, the Program consists of four coupled elements: (1) to design and construct an integral, carefully-scaled SBWR test facility at Purdue Univ., (2) to provide pre-construction RELAP5/CONTAIN predictions of the facility design, (3) to provide confirmatory data for code assessment, and (4) to assess the RELAP5/CONTAIN code with data. A description of the open-quotes preliminary designclose quotes of the Purdue test facility and test matrix is presented. The facility is scheduled to be built by December 1994. Approximately 50 tests will be performed from April 1995 through April 1996 and documented by interim data reports. A final and complete data report is scheduled to be published by July 31, 1996

  12. 75 FR 59105 - Procedures for Transportation Workplace Drug and Alcohol Testing Programs: Federal Drug Testing...

    Science.gov (United States)

    2010-09-27

    ... 2105-AE03 Procedures for Transportation Workplace Drug and Alcohol Testing Programs: Federal Drug... the Federal workplace drug testing program but also pointed out that ``* * * the Department of.... Executive Order 12866 and Regulatory Flexibility Act This Interim Final Rule is not significant for purposes...

  13. The high level vibration test program

    International Nuclear Information System (INIS)

    Hofmayer, C.H.; Curreri, J.R.; Park, Y.J.; Kato, W.Y.; Kawakami, S.

    1989-01-01

    As part of cooperative agreements between the US and Japan, tests have been performed on the seismic vibration table at the Tadotsu Engineering Laboratory of Nuclear Power Engineering Test Center (NUPEC) in Japan. The objective of the test program was to use the NUPEC vibration table to drive large diameter nuclear power piping to substantial plastic strain with an earthquake excitation and to compare the results with state-of-the-art analysis of the problem. The test model was subjected to a maximum acceleration well beyond what nuclear power plants are designed to withstand. A modified earthquake excitation was applied and the excitation level was increased carefully to minimize the cumulative fatigue damage due to the intermediate level excitations. Since the piping was pressurized, and the high level earthquake excitation was repeated several times, it was possible to investigate the effects of ratchetting and fatigue as well. Elastic and inelastic seismic response behavior of the test model was measured in a number of test runs with an increasing excitation input level up to the limit of the vibration table. In the maximum input condition, large dynamic plastic strains were obtained in the piping. Crack initiation was detected following the second maximum excitation run. Crack growth was carefully monitored during the next two additional maximum excitation runs. The final test resulted in a maximum crack depth of approximately 94% of the wall thickness. The HLVT (high level vibration test) program has enhanced understanding of the behavior of piping systems under severe earthquake loading. As in other tests to failure of piping components, it has demonstrated significant seismic margin in nuclear power plant piping

  14. 40 CFR 85.1509 - Final admission of modification and test vehicles.

    Science.gov (United States)

    2010-07-01

    ... test vehicles. 85.1509 Section 85.1509 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) CONTROL OF AIR POLLUTION FROM MOBILE SOURCES Importation of Motor Vehicles and Motor Vehicle Engines § 85.1509 Final admission of modification and test vehicles. (a) Except...

  15. International piping integrity research group (IPIRG) program final report

    International Nuclear Information System (INIS)

    Schmidt, R.; Wilkowski, G.; Scott, P.; Olsen, R.; Marschall, C.; Vieth, P.; Paul, D.

    1992-04-01

    This is the final report of the International Piping Integrity Research Group (IPIRG) Programme. The IPIRG Programme was an international group programme managed by the U.S. Nuclear Regulatory Commission and funded by a consortium of organizations from nine nations: Canada, France, Italy, Japan, Sweden, Switzerland, Taiwan, the United Kingdom, and the United states. The objective of the programme was to develop data needed to verify engineering methods for assessing the integrity of nuclear power plant piping that contains circumferential defects. The primary focus was an experimental task that investigated the behaviour of circumferentially flawed piping and piping systems to high-rate loading typical of seismic events. To accomplish these objectives a unique pipe loop test facility was designed and constructed. The pipe system was an expansion loop with over 30 m of 406-mm diameter pipe and five long radius elbows. Five experiments on flawed piping were conducted to failure in this facility with dynamic excitation. The report: provides background information on leak-before-break and flaw evaluation procedures in piping; summarizes the technical results of the programme; gives a relatively detailed assessment of the results from the various pipe fracture experiments and complementary analyses; and, summarizes the advances in the state-of-the-art of pipe fracture technology resulting from the IPIRG Program

  16. Advanced Fuel Cycle Initiative University Fellowship Program. Final Progress Report

    International Nuclear Information System (INIS)

    Dixon, Cathy

    2012-01-01

    2004-2011 Final Report for AFCI University Fellowship Program. The goal of this effort was to be supportive of university students and university programs - particularly those students and programs that will help to strengthen the development of nuclear-related fields. The program also supported the stability of the nuclear infrastructure and developed research partnerships that are helping to enlarge the national nuclear science technology base. In this fellowship program, the U.S. Department of Energy sought master's degree students in nuclear, mechanical, or chemical engineering, engineering/applied physics, physics, chemistry, radiochemistry, or fields of science and engineering applicable to the AFCI/Gen IV/GNEP missions in order to meet future U.S. nuclear program needs. The fellowship program identified candidates and selected full time students of high-caliber who were taking nuclear courses as part of their degree programs. The DOE Academic Program Managers encouraged fellows to pursue summer internships at national laboratories and supported the students with appropriate information so that both the fellows and the nation's nuclear energy objectives were successful.

  17. Nevada Test Site, Nye County, Nevada. Final environmental impact statement

    International Nuclear Information System (INIS)

    1977-09-01

    This environmental statement for the Nevada Test Site (NTS) considers underground nuclear detonations with yields of one megaton or less, along with the preparations necessary for such detonations. The testing activities considered also include other continuing and intermittent activities, both nuclear and nonnuclear, which can best be conducted in the remote and controlled area of the Nevada Test Site. These activities are listed, with emphasis on weapons testing programs which do not remain static

  18. Nevada Test Site, Nye County, Nevada. Final environmental impact statement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-09-01

    This environmental statement for the Nevada Test Site (NTS) considers underground nuclear detonations with yields of one megaton or less, along with the preparations necessary for such detonations. The testing activities considered also include other continuing and intermittent activities, both nuclear and nonnuclear, which can best be conducted in the remote and controlled area of the Nevada Test Site. These activities are listed, with emphasis on weapons testing programs which do not remain static.

  19. New energy test procedures for refrigerators and other appliances; FINAL

    International Nuclear Information System (INIS)

    Meier, Alan; Ernebrant, Stefan; Kawamoto, Kaoru; Wihlborg, Mats

    1999-01-01

    Many innovations in refrigerator design rely on microprocessors, sensors, and algorithms to control automatic defrost, variable speed,and other features. Even though these features strongly influence energy consumption, the major energy test procedures presently test only a refrigerator's mechanical efficiency and ignore the ''software'' aspects. We describe a new test procedure where both ''hardware'' and ''software'' tests are fed into a dynamic simulation model. A wide range of conditions can be tested and simulated. This approach promotes international harmonization because the simulation model can also be programmed to estimate energy use for the ISO, DOE, or JIS test. The approach outlined for refrigerators can also be applied to other appliances

  20. Refinement, testing, and application of an Integrated Data Assimilation/Sounding System (IDASS) for the DOE/ARM Experimental Program. Final report for period September 20, 1990 - May 8, 1997

    Energy Technology Data Exchange (ETDEWEB)

    Parsons, David B.

    2002-04-09

    This report describes work done by NCAR under the ''Refinement, Testing, and Application of an Integrated Data Assimilation/Sounding System (IDASS) for the DOE/ARM Experimental Program''. It includes a discussion of the goals, findings and a list of 27 journal articles, 92 non-refereed papers and 30 other presentations not associated with a formal publication.

  1. Rehabilitation Counseling Information: Programmed Instruction for the Practitioner. Final Report.

    Science.gov (United States)

    Phelps, William R.

    This programmed instruction rehabilitation counseling information test attempts to cover six areas as follows: testing, psychological information, medical information, counseling concepts, history of rehabilitation, and counselor-agency functioning. The information may be utilized for research purposes and/or replicated by others. (Author)

  2. Photovoltaic subsystem marketing and distribution model: programming manual. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1982-07-01

    Complete documentation of the marketing and distribution (M and D) computer model is provided. The purpose is to estimate the costs of selling and transporting photovoltaic solar energy products from the manufacturer to the final customer. The model adjusts for the inflation and regional differences in marketing and distribution costs. The model consists of three major components: the marketing submodel, the distribution submodel, and the financial submodel. The computer program is explained including the input requirements, output reports, subprograms and operating environment. The program specifications discuss maintaining the validity of the data and potential improvements. An example for a photovoltaic concentrator collector demonstrates the application of the model.

  3. National energy peak leveling program (NEPLP). Final report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1977-12-01

    This three-volume report is responsive to the requirements of Contract E (04-3)-1152 to provide a detailed methodology, to include management, technology, and socio-economic aspects, of a voluntary community program of computer-assisted peak load leveling and energy conservation in commercial community facilities. The demonstration project established proof-of-concept in reducing the kW-demand peak by the unofficial goal of 10%, with concurrent kWh savings. This section of the three volume report is a final report appendix with information on the National Energy Peak Leveling Program (NEPLP).

  4. Medicare and Medicaid programs; advance directives--HCFA. Final rule.

    Science.gov (United States)

    1995-06-27

    This final rule responds to public comments on the March 6, 1992 interim final rule with comment period that amended the Medicare and Medicaid regulations governing provider agreements and contracts to establish requirements for States, hospitals, nursing facilities, skilled nursing facilities, providers of home health care or personal care services, hospice programs and managed care plans concerning advance directives. An advance directive is a written instruction, such as a living will or durable power of attorney for health care, recognized under State law, relating to the provision of health care when an individual's condition makes him or her unable to express his or her wishes. The intent of the advance directives provisions is to enhance an adult individual's control over medical treatment decisions. This rule confirms the interim final rule with several minor changes based on our review and consideration of public comments.

  5. Testing the initial-final mass relationship of white dwarfs

    International Nuclear Information System (INIS)

    Catalan, S; Isern, J; Garcia-Berro, E; Ribas, I

    2009-01-01

    In this contribution we revisit the initial-final mass relationship of white dwarfs, which links the mass of a white dwarf with that of its progenitor in the main-sequence. Although this function is of paramount importance to several fields in modern astrophysics, it is still not well constrained either from the theoretical or the observational points of view. We present here a revision of the present semi-empirical initial-final mass relationship using all the available data and including our recent results obtained from studying white dwarfs in common proper motion pairs. We have also analyzed the results obtained so far to provide some clues on the dependence of this relationship on metallicity. Finally, we have also performed an indirect test of the initial-final mass relationship by studying its effect on the luminosity function and on the mass distribution of white dwarfs.

  6. Review of tolerances at the Final Focus Test Beam

    International Nuclear Information System (INIS)

    Bulos, F.; Burke, D.; Helm, R.; Irwin, J.; Roy, G.; Yamamoto, N.

    1991-01-01

    The authors review the tolerances associated with the Final Focus Test Beam (FFTB). The authors have computed the acceptability window of the input beam for orbit jitter, emittance beta functions mismatch, incoming dispersion and coupling; tolerances on magnet alignment, strength and multipole content; and the initial tuneability capture of the line

  7. Review of tolerances at the Final Focus Test Beam

    International Nuclear Information System (INIS)

    Bulos, F.; Burke, D.; Helm, R.; Irwin, J.; Roy, G.; Yamamoto, N.

    1991-05-01

    We review the tolerances associated with the Final Focus Test Beam (FFTB). We have computed the acceptability window of the input beam for orbit jitter, emittance beta functions mismatch, incoming dispersion and coupling; tolerances on magnet alignment, strength and multipole content; and the initial tuneability capture of the line. 2 refs., 1 fig

  8. An innovative approach for testing bioinformatics programs using metamorphic testing

    Directory of Open Access Journals (Sweden)

    Liu Huai

    2009-01-01

    Full Text Available Abstract Background Recent advances in experimental and computational technologies have fueled the development of many sophisticated bioinformatics programs. The correctness of such programs is crucial as incorrectly computed results may lead to wrong biological conclusion or misguide downstream experimentation. Common software testing procedures involve executing the target program with a set of test inputs and then verifying the correctness of the test outputs. However, due to the complexity of many bioinformatics programs, it is often difficult to verify the correctness of the test outputs. Therefore our ability to perform systematic software testing is greatly hindered. Results We propose to use a novel software testing technique, metamorphic testing (MT, to test a range of bioinformatics programs. Instead of requiring a mechanism to verify whether an individual test output is correct, the MT technique verifies whether a pair of test outputs conform to a set of domain specific properties, called metamorphic relations (MRs, thus greatly increases the number and variety of test cases that can be applied. To demonstrate how MT is used in practice, we applied MT to test two open-source bioinformatics programs, namely GNLab and SeqMap. In particular we show that MT is simple to implement, and is effective in detecting faults in a real-life program and some artificially fault-seeded programs. Further, we discuss how MT can be applied to test programs from various domains of bioinformatics. Conclusion This paper describes the application of a simple, effective and automated technique to systematically test a range of bioinformatics programs. We show how MT can be implemented in practice through two real-life case studies. Since many bioinformatics programs, particularly those for large scale simulation and data analysis, are hard to test systematically, their developers may benefit from using MT as part of the testing strategy. Therefore our work

  9. Building-owners energy-education program. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1981-12-01

    The objectives of the program are to develop and test market a cogent education program aimed specifically at building owners to help them be more decisive and knowledgeable, and to motivate them to direct their managers and professionals to implement a rational plan for achieving energy conservation in their commercial office buildings and to establish a plan, sponsored by the Building Owners and Managers Association International (BOMA) to implement this educational program on a nation-wide basis. San Francisco, Chicago, and Atlanta were chosen for test marketing a model program. The procedure used in making the energy survey is described. Energy survey results of participating buildings in San Francisco, Chicago, and Atlanta are summarized. (MCW)

  10. Supercritical water oxidation data acquisition testing. Final report, Volume II

    International Nuclear Information System (INIS)

    1996-11-01

    Supercritical Water Oxidation (SCWO) technology holds great promise for treating mixed wastes, in an environmentally safe and efficient manner. In the spring of 1994 the US Department of Energy (DOE), Idaho Operations Office awarded Stone ampersand Webster Engineering Corporation, of Boston Massachusetts and its sub-contractor MODAR, Inc. of Natick Massachusetts a Supercritical Water Oxidation Data Acquisition Testing (SCWODAT) program. The SCWODAT program was contracted through a Cooperative Agreement that was co-funded by the US Department of Energy and the Strategic Environmental Research and Development Program. The SCWODAT testing scope outlined by the DOE in the original Cooperative Agreement and amendments thereto was initiated in June 1994 and successfully completed in December 1995. The SCWODAT program provided further information and operational data on the effectiveness of treating both simulated mixed waste and typical Navy hazardous waste using the MODAR SCWO technology

  11. International Piping Integrity Research Group (IPIRG) Program. Final report

    International Nuclear Information System (INIS)

    Wilkowski, G.; Schmidt, R.; Scott, P.

    1997-06-01

    This is the final report of the International Piping Integrity Research Group (IPIRG) Program. The IPIRG Program was an international group program managed by the U.S. Nuclear Regulatory Commission and funded by a consortium of organizations from nine nations: Canada, France, Italy, Japan, Sweden, Switzerland, Taiwan, the United Kingdom, and the United States. The program objective was to develop data needed to verify engineering methods for assessing the integrity of circumferentially-cracked nuclear power plant piping. The primary focus was an experimental task that investigated the behavior of circumferentially flawed piping systems subjected to high-rate loadings typical of seismic events. To accomplish these objectives a pipe system fabricated as an expansion loop with over 30 meters of 16-inch diameter pipe and five long radius elbows was constructed. Five dynamic, cyclic, flawed piping experiments were conducted using this facility. This report: (1) provides background information on leak-before-break and flaw evaluation procedures for piping, (2) summarizes technical results of the program, (3) gives a relatively detailed assessment of the results from the pipe fracture experiments and complementary analyses, and (4) summarizes advances in the state-of-the-art of pipe fracture technology resulting from the IPIRG program

  12. International Piping Integrity Research Group (IPIRG) Program. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Wilkowski, G.; Schmidt, R.; Scott, P. [and others

    1997-06-01

    This is the final report of the International Piping Integrity Research Group (IPIRG) Program. The IPIRG Program was an international group program managed by the U.S. Nuclear Regulatory Commission and funded by a consortium of organizations from nine nations: Canada, France, Italy, Japan, Sweden, Switzerland, Taiwan, the United Kingdom, and the United States. The program objective was to develop data needed to verify engineering methods for assessing the integrity of circumferentially-cracked nuclear power plant piping. The primary focus was an experimental task that investigated the behavior of circumferentially flawed piping systems subjected to high-rate loadings typical of seismic events. To accomplish these objectives a pipe system fabricated as an expansion loop with over 30 meters of 16-inch diameter pipe and five long radius elbows was constructed. Five dynamic, cyclic, flawed piping experiments were conducted using this facility. This report: (1) provides background information on leak-before-break and flaw evaluation procedures for piping, (2) summarizes technical results of the program, (3) gives a relatively detailed assessment of the results from the pipe fracture experiments and complementary analyses, and (4) summarizes advances in the state-of-the-art of pipe fracture technology resulting from the IPIRG program.

  13. Final Physics Report for the Engineering Test Reactor

    International Nuclear Information System (INIS)

    Wolfe, I. B.

    1956-01-01

    This report is a summary of the physics design work performed on the Engineering Test Reactor. The ETR presents computational difficulties not found in other reactors because of the large number of experimental holes in the core. The physics of the ETR depends strongly upon the contents of the in-core experimental facilities. In order to properly evaluate the reactor' taking into account the experiments in the core, multi-region, two-dimensional calculations are required. These calculations require the use of a large computer such as the Remington Rand Univac and are complex and expensive enough to warrant a five-stage program: 1. In the early stages of design, only preliminary two-dimensional calculations were performed .in order to obtain a rough idea of the general behavior of the reactor and its critical mass with tentative experiments in place. 2. A large amount of work was carried out in which the reactor was approximated as one with a uniform homogeneous core. With this model, detailed studies were carried out to investigate the feasibility and to obtain general design data on such points as the design and properties of the gray and black control rods, the design of the beryllium reflector, gamma and neutron heating, the use of burnable poisons, etc. In performing these calculations, use was made of the IBM 650 PROD code obtained from KAPL. 3. With stages 1 and 2 carried out, two-dimensional calculations of the core at start-up conditions were performed on the Univac computer. 4. Detailed two-dimensional calculations of the properties of the ETR with a proposed first set of experiments in place were carried out. 5. A series of nuclear tests were performed at the reactivity measurements facility at the MTR site in order to confirm the validity of the analytical techniques in physics analysis. In performing the two-dimensional Univac calculations, the MUG code developed by KAPL and the Cuthill code developed at the David Taylor Model Basin were utilized. In

  14. 47 CFR 73.713 - Program tests.

    Science.gov (United States)

    2010-10-01

    ... International Broadcast Stations § 73.713 Program tests. (a) Upon completion of construction of an international.... The Commission reserves the right to change the date of the beginning of such tests or to suspend or revoke the authority for program tests as and when such action may appear to be in the public interest...

  15. Chronic beryllium disease prevention program; worker safety and health program. Final rule.

    Science.gov (United States)

    2006-02-09

    The Department of Energy (DOE) is today publishing a final rule to implement the statutory mandate of section 3173 of the Bob Stump National Defense Authorization Act (NDAA) for Fiscal Year 2003 to establish worker safety and health regulations to govern contractor activities at DOE sites. This program codifies and enhances the worker protection program in operation when the NDAA was enacted.

  16. The PUMA test program and data analysis

    International Nuclear Information System (INIS)

    Han, J.T.; Morrison, D.L.

    1997-01-01

    The PUMA test program is sponsored by the U.S. Nuclear Regulatory Commission to provide data that are relevant to various Boiling Water Reactor phenomena. The author briefly describes the PUMA test program and facility, presents the objective of the program, provides data analysis for a large-break loss-of-coolant accident test, and compares the data with a RELAP5/MOD 3.1.2 calculation

  17. Collider Dipole Magnet test program from development through production

    International Nuclear Information System (INIS)

    Bailey, R.E.

    1991-01-01

    Verification of CDM performance, reliability, and magnet production processes will be accomplished during the development phase of the program. Key features of this program include thorough in process testing of magnet subassemblies, verification of the magnetic field quality, and demonstration of the CDM performance during the formal qualification program. Reliability demonstration of the CDM design includes component tests and an accelerated life test program. Prototype magnet phase will address achievement of magnet performance goals through a program of fabrications, test, analysis, redesign as required and procurement of modified parts for a second fabrication run. This process would be repeated again if necessary, and would conclude with a final design for the production magnets. Production process validation will address the effects that key production processes have upon magnet performance, using the magnets produced during the Preproduction phase

  18. Final design and performance of in situ testing in Grimsel

    International Nuclear Information System (INIS)

    Fuentes-Cantillana, J.L.; Garcia-SiNeriz, J.L.

    1998-01-01

    This report is focused on the design, engineering, and construction aspects of the in situ test carried out at the Grimsel underground laboratory in Switzerland. This reproduces the AGP-granite concept of ENRESA for HLW repositories in crystalline rock. Two heaters, similar in dimensions and weight to the canisters in the reference concept, have been placed in a horizontal drift with a 2.28-m diameter, a total test length of 17.4 m, and backfilled with a total of 115.7 † of highly-compacted bentonite blocks. The backfilled area has been closed with a concrete plug which is 2.7 m thick. More than 600 sensors have been installed in the test to monitor different parameters such as temperature, pressures, humidity, etc., within both the buffer material and the host rock. The installation was completed and commissioned in February 1997, and then the heating phase, which will last for at least 3 years, was started. During this period, the test will basically be operated in an automatic mode, controlled and monitored from Spain via modem. The report is the Final Report from AITEMIN for Phase 4 of the project and includes a description of the test configuration and layout; the design, engineering, and manufacturing aspects of the different test components and equipment; the emplacement operation; and the as built information regarding the final position of the main components and the sensors. (Author)

  19. The optics of the Final Focus Test Beam

    International Nuclear Information System (INIS)

    Irwin, J.; Brown, K.; Bulos, F.; Burke, D.; Helm, R.; Roy, G.; Ruth, R.; Yamamoto, N.; Oide, K.

    1991-05-01

    The Final Focus Test Beam (FFTB), currently under construction at the end of the SLAC Linac, is being built by an international collaboration as a test bed for ideas and methods required in the design and construction of final focus systems for next generation e + e - linear colliders. The FFTB lattice is based on the previously developed principle of using sextupole pairs in a dispersive region to compensate chromaticity. The linear lattice was optimized for length, and implementation of diagnostic procedures. The transformations between sextupole pairs (CCX and CCY) are exactly -I, the matrix for the intermediate transformer (BX) is exactly diagonal, and the dispersion function has zero slope at the sextupoles and is thus zero at the minimum of the β x function in the intermediate transformer. The introduction of sextupoles in final focus systems leads to the presence of additional optical aberrations, and synchrotron radiation in the dipoles also enlarges the final spot size. The important fourth-order optical aberrations which determine the main features of the design have been identified. Additional lower order aberrations arise in the implementation of these designs, since the real system is not the ideal design. We concentrate on these aberrations and describe strategies for their diagnosis and correction

  20. Final design of ITER port plug test facility

    Energy Technology Data Exchange (ETDEWEB)

    Cerisier, Thierry, E-mail: thierry.cerisier@yahoo.fr [ITER Organization, Route de Vinon-sur-Verdon, CS 90046, St Paul-lez-Durance Cedex, 13067 (France); Levesy, Bruno [ITER Organization, Route de Vinon-sur-Verdon, CS 90046, St Paul-lez-Durance Cedex, 13067 (France); Romannikov, Alexander [Institution “Project Center ITER”, Kurchatov sq. 1, Building 3, Moscow 123182 (Russian Federation); Rumyantsev, Yuri [JSC “Cryogenmash”, Moscow reg., Balashikha 143907 (Russian Federation); Cordier, Jean-Jacques; Dammann, Alexis [ITER Organization, Route de Vinon-sur-Verdon, CS 90046, St Paul-lez-Durance Cedex, 13067 (France); Minakov, Victor; Rosales, Natalya; Mitrofanova, Elena [JSC “Cryogenmash”, Moscow reg., Balashikha 143907 (Russian Federation); Portone, Sergey; Mironova, Ekaterina [Institution “Project Center ITER”, Kurchatov sq. 1, Building 3, Moscow 123182 (Russian Federation)

    2016-11-01

    Highlights: • We introduce the port plug test facility (purpose and status of the design). • We present the PPTF sub-systems. • We present the environmental and functional tests. • We present the occupational and nuclear safety functions. • We conclude on the achievements and next steps. - Abstract: To achieve the overall ITER machine availability target, the availability of diagnostics and heating port plugs shall be as high as 99.5%. To fulfill this requirement, it is mandatory to test the port plugs at operating temperature before installation on the machine and after refurbishment. The ITER port plug test facility (PPTF) is composed of several test stands that can be used to test the port plugs whereas at the end of manufacturing (in a non-nuclear environment), or after refurbishment in the ITER hot cell facility. The PPTF provides the possibility to perform environmental (leak tightness, vacuum and thermo-hydraulic performances) and functional tests (radio frequency acceptance tests, behavior of the plugs’ steering mechanism and calibration of diagnostics) on upper and equatorial port plugs. The final design of the port plug test facility is described. The configuration of the standalone test stands and the integration in the hot cell facility are presented.

  1. The optics of the Final Focus Test Beam

    International Nuclear Information System (INIS)

    Irwin, J.; Brown, K.; Bulos, F.; Burke, D.; Helm, R.; Roy, G.; Ruth, R.; Yamamoto, N.; Oide, K.

    1991-01-01

    The Final Focus Test Beam (FFTB), currently under construction at the end of the SLAC Linac, is being built by an international collaboration as a test bed for ideas and methods required in the design and construction of final focus systems for next generation e + e - linear colliders. The FFTB lattice shown is based on the previously developed principle of using sextupole pairs in a dispersive region to compensate chromaticity. The linear lattice was optimized for length, and implementation of diagnostic procedures. The transformations between sextupole pairs (CCX and CCY) are exactly -I, the matrix for the intermediate transformer (BX) is exactly diagonal, and the dispersion function has zero slope at the sextupoles and is thus zero at the minimum of the β x function in the intermediate transformer

  2. Final environmental statement for the geothermal leasing program

    Energy Technology Data Exchange (ETDEWEB)

    1973-12-31

    This second of the four volumes of the Geothermal Leasing Program final impact statement contains the individual environmental statements for the leasing of federally owned geothermal resources for development in three specific areas: Clear Lake-Geysers; Mono Lake-Long Valley; and Imperial Valley, all in California. It also includes a summary of the written comments received and departmental responses relative to the Draft Environmental Impact Statement issued in 1971; comments and responses on the Draft Environmental Impact Statement; consultation and coordination in the development of the proposal and in the preparation of the Draft Environmental Statement; and coordination in the review of the Draft Environmental Statement.

  3. Plasma lenses for SLAC Final Focus Test facility

    International Nuclear Information System (INIS)

    Betz, D.; Cline, D.; Joshi, C.; Rajagopalan, S.; Rosenzweig, J.; Su, J.J.; Williams, R.; Chen, P.; Gundersen, M.; Katsouleas, T.; Norem, J.

    1991-01-01

    A collaborative group of accelerator and plasma physicists and engineers has formed with an interest in exploring the use of plasma lenses to meet the needs of future colliders. Analytic and computational models of plasma lenses are briefly reviewed and several design examples for the SLAC Final Focus Test Beam are presented. The examples include discrete, thick, and adiabatic lenses. A potential plasma source with desirable lens characteristics is presented

  4. Near-term electric vehicle program: Phase I, final report

    Energy Technology Data Exchange (ETDEWEB)

    Rowlett, B. H.; Murry, R.

    1977-08-01

    A final report is given for an Energy Research and Development Administration effort aimed at a preliminary design of an energy-efficient electric commuter car. An electric-powered passenger vehicle using a regenerative power system was designed to meet the near-term ERDA electric automobile goals. The program objectives were to (1) study the parameters that affect vehicle performance, range, and cost; (2) design an entirely new electric vehicle that meets performance and economic requirements; and (3) define a program to develop this vehicle design for production in the early 1980's. The design and performance features of the preliminary (baseline) electric-powered passenger vehicle design are described, including the baseline power system, system performance, economic analysis, reliability and safety, alternate designs and options, development plan, and conclusions and recommendations. All aspects of the baseline design were defined in sufficient detail to verify performance expectations and system feasibility.

  5. Accelerated bridge paint test program.

    Science.gov (United States)

    2011-07-06

    The accelerated bridge paint (AB-Paint) program evaluated a new Sherwin-Williams two-coat, : fast-curing paint system. The system is comprised of an organic zinc-rich primer (SW Corothane I : Galvapac One-Pack Zinc-Rich Primer B65 G11) and a polyurea...

  6. Development of Final Running Test System for Digital Systems

    International Nuclear Information System (INIS)

    Lee, Kwang-Dae; Lee, Eui-Jong; Lim, Hee-Taek; Kim, Min-Seok

    2016-01-01

    In nuclear industry, the newly designed systems to upgrade are qualified to meet IEEE standards and the regulatory guidelines for their functions, performance and reliability requirements. Failure Mode and Effect Analysis, Fault Tree Analysis, and Hazard Analysis have been used to improve the reliability of the control system. To ensure the completeness of the software, the verification and validation processes are carried out during the development process. In spite of the many efforts depending on the analysis and procedures, there are limitations to improve the reliability. The lessons learned from the currently installed system failures show the incompleteness of the final integration test. The current point-to-point and logic-to-logic separate test procedures manually performed by the engineers can cause some procedures missed and have effects on the critical functions. The design processes of the digital systems are met in accordance with the international standards and regulatory guidelines. The lessons learned from the failures of the running digital systems showed the limitations of the current verification and validation efforts. The various improvements and attempts have been considered including the expert review processes and the completeness of the test. In this paper, the Final Running Test Method evaluating the completeness of the digital system using the control patterns and the Test System Architecture are proposed

  7. Development of Final Running Test System for Digital Systems

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Kwang-Dae; Lee, Eui-Jong; Lim, Hee-Taek; Kim, Min-Seok [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    In nuclear industry, the newly designed systems to upgrade are qualified to meet IEEE standards and the regulatory guidelines for their functions, performance and reliability requirements. Failure Mode and Effect Analysis, Fault Tree Analysis, and Hazard Analysis have been used to improve the reliability of the control system. To ensure the completeness of the software, the verification and validation processes are carried out during the development process. In spite of the many efforts depending on the analysis and procedures, there are limitations to improve the reliability. The lessons learned from the currently installed system failures show the incompleteness of the final integration test. The current point-to-point and logic-to-logic separate test procedures manually performed by the engineers can cause some procedures missed and have effects on the critical functions. The design processes of the digital systems are met in accordance with the international standards and regulatory guidelines. The lessons learned from the failures of the running digital systems showed the limitations of the current verification and validation efforts. The various improvements and attempts have been considered including the expert review processes and the completeness of the test. In this paper, the Final Running Test Method evaluating the completeness of the digital system using the control patterns and the Test System Architecture are proposed.

  8. Expanded studies of linear collider final focus systems at the Final Focus Test Beam

    International Nuclear Information System (INIS)

    Tenenbaum, P.G.

    1995-12-01

    In order to meet their luminosity goals, linear colliders operating in the center-of-mass energy range from 3,50 to 1,500 GeV will need to deliver beams which are as small as a few Manometers tall, with x:y aspect ratios as large as 100. The Final Focus Test Beam (FFTB) is a prototype for the final focus demanded by these colliders: its purpose is to provide demagnification equivalent to those in the future linear collider, which corresponds to a focused spot size in the FFTB of 1.7 microns (horizontal) by 60 manometers (vertical). In order to achieve the desired spot sizes, the FFTB beam optics must be tuned to eliminate aberrations and other errors, and to ensure that the optics conform to the desired final conditions and the measured initial conditions of the beam. Using a combination of incoming-beam diagnostics. beam-based local diagnostics, and global tuning algorithms, the FFTB beam size has been reduced to a stable final size of 1.7 microns by 70 manometers. In addition, the chromatic properties of the FFTB have been studied using two techniques and found to be acceptable. Descriptions of the hardware and techniques used in these studies are presented, along with results and suggestions for future research

  9. Expanded studies of linear collider final focus systems at the Final Focus Test Beam

    Energy Technology Data Exchange (ETDEWEB)

    Tenenbaum, Peter Gregory [Stanford Univ., CA (United States)

    1995-12-01

    In order to meet their luminosity goals, linear colliders operating in the center-of-mass energy range from 3,50 to 1,500 GeV will need to deliver beams which are as small as a few Manometers tall, with x:y aspect ratios as large as 100. The Final Focus Test Beam (FFTB) is a prototype for the final focus demanded by these colliders: its purpose is to provide demagnification equivalent to those in the future linear collider, which corresponds to a focused spot size in the FFTB of 1.7 microns (horizontal) by 60 manometers (vertical). In order to achieve the desired spot sizes, the FFTB beam optics must be tuned to eliminate aberrations and other errors, and to ensure that the optics conform to the desired final conditions and the measured initial conditions of the beam. Using a combination of incoming-beam diagnostics. beam-based local diagnostics, and global tuning algorithms, the FFTB beam size has been reduced to a stable final size of 1.7 microns by 70 manometers. In addition, the chromatic properties of the FFTB have been studied using two techniques and found to be acceptable. Descriptions of the hardware and techniques used in these studies are presented, along with results and suggestions for future research.

  10. 75 FR 50932 - Massachusetts: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2010-08-18

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental...-1990. FOR FURTHER INFORMATION CONTACT: Robin Biscaia, RCRA Waste Management Section, Office of Site... final [[Page 50933

  11. Hydrologic resources management program, FY 1998 progress report; FINAL

    International Nuclear Information System (INIS)

    Benedict, F.C.; Criss, R.E.; Davisson, M.L.; Eaton, G.F.; Hudson, G.B.; Kenneally, J.M.; Rose, T.P.; Smith, D.

    1999-01-01

    This report presents the results from FY 1998 technical studies conducted by Lawrence Livermore National Laboratory (LLNL) as part of the Hydrology and Radionuclide Migration Program (HRMP) and Underground Test Area (UGTA) project. The HRMP is sponsored by Defense Programs (DP) of the U.S. Department of Energy, Nevada Operations Office (DOE/NV), and supports DP operations at the Nevada Test Site (NTS) through studies of radiochemistry and resource management related to the defense programs mission. Other participating organizations include the Los Alamos National Laboratory (LANL), the United States Geological Survey (USGS), the Desert Research Institute (DRI) of the University of Nevada, the United States Environmental Protection Agency (EPA), and Bechtel-Nevada (BN). The UGTA project is an Environmental Management (EM) activity of DOE/NV that supports a Federal Facilities Agreement and Consent Order between the Department of Energy, the Department of Defense, and the State of Nevada. UGTA's primary function is to address the legacy release of hazardous constituents at the Nevada Test Site, the Tonopah Test Range, and off-Nevada Test Site underground nuclear testing areas. Participating contractors include LLNL (Earth and Environmental Sciences Directorate, Analytical and Nuclear Chemistry Division), LANL, DRI, USGS, BN, HSI-GeoTrans, and IT Corporation. The FY 1998 HRMP and UGTA annual progress report follows the organization and contents of our FY 1997 report (Smith et al., 1998), and includes our results from CY 1997-1998 technical studies of radionuclide migration and isotope hydrology at the Nevada Test Site. During FY 1998, LLNL continued its efforts under the HRMP to pursue a technical agenda relevant to the science-based stockpile stewardship program at DOE/NV. Support to UGTA in FY 1998 included efforts to quantitatively define the radionuclide source term residual from underground nuclear weapons testing and the derivative solution, or hydrologic source

  12. Stirling Space Engine Program. Volume 1; Final Report

    Science.gov (United States)

    Dhar, Manmohan

    1999-01-01

    The objective of this program was to develop the technology necessary for operating Stirling power converters in a space environment and to demonstrate this technology in full-scale engine tests. Hardware development focused on the Component Test Power Converter (CTPC), a single cylinder, 12.5-kWe engine. Design parameters for the CTPC were 150 bar operating pressure, 70 Hz frequency, and hot-and cold-end temperatures of 1050 K and 525 K, respectively. The CTPC was also designed for integration with an annular sodium heat pipe at the hot end, which incorporated a unique "Starfish" heater head that eliminated highly stressed brazed or weld joints exposed to liquid metal and used a shaped-tubed electrochemical milling process to achieve precise positional tolerances. Selection of materials that could withstand high operating temperatures with long life were another focus. Significant progress was made in the heater head (Udimet 700 and Inconel 718 and a sodium-filled heat pipe); the alternator (polyimide-coated wire with polyimide adhesive between turns and a polyimide-impregnated fiberglass overwrap and samarium cobalt magnets); and the hydrostatic gas bearings (carbon graphite and aluminum oxide for wear couple surfaces). Tests on the CTPC were performed in three phases: cold end testing (525 K), engine testing with slot radiant heaters, and integrated heat pipe engine system testing. Each test phase was successful, with the integrated engine system demonstrating a power level of 12.5 kWe and an overall efficiency of 22 percent in its maiden test. A 1500-hour endurance test was then successfully completed. These results indicate the significant achievements made by this program that demonstrate the viability of Stirling engine technology for space applications.

  13. The Yucca Mountain Project Prototype Testing Program

    International Nuclear Information System (INIS)

    1989-10-01

    The Yucca Mountain Project is conducting a Prototype Testing Program to ensure that the Exploratory Shaft Facility (ESF) tests can be completed in the time available and to develop instruments, equipment, and procedures so the ESF tests can collect reliable and representative site characterization data. This report summarizes the prototype tests and their status and location and emphasizes prototype ESF and surface tests, which are required in the early stages of the ESF site characterization tests. 14 figs

  14. Testing programs for the Multimission Modular Spacecraft

    Science.gov (United States)

    Greenwell, T. J.

    1978-01-01

    The Multimission Modular Spacecraft (MMS) provides a standard spacecraft bus to a user for a variety of space missions ranging from near-earth to synchronous orbits. The present paper describes the philosophy behind the MMS module test program and discusses the implementation of the test program. It is concluded that the MMS module test program provides an effective and comprehensive customer buy-off at the subsystem contractor's plant, is an optimum approach for checkout of the subsystems prior to use for on-orbit servicing in the Shuttle Cargo Bay, and is a cost-effective technique for environmental testing.

  15. Implementing and testing program PLOTTAB

    International Nuclear Information System (INIS)

    Cullen, D.E.; McLaughlin, P.K.

    1988-01-01

    Enclosed is a description of the magnetic tape or floppy diskette containing the PLOTTAB code package. In addition detailed information is provided on implementation and testing of this code. See part I for mainframe computers; part II for personal computers. These codes are documented in IAEA-NDS-82. (author)

  16. 78 FR 25678 - Georgia: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-05-02

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... of changes to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA... Gwendolyn Gleaton, Permits and State Programs Section, RCRA Programs and Materials Management Branch, RCRA...

  17. Actinide partitioning-transmutation program final report. III. Transmutation studies

    International Nuclear Information System (INIS)

    Wachter, J.W.; Croff, A.G.

    1980-07-01

    Transmutation of the long-lived nuclides contained in fuel cycle wastes has been suggested as a means of reducing the long-term toxicity of the wastes. A comprehensive program to evaluate the feasibility and incentives for recovering the actinides from wastes (partitioning) and transmuting them to short-lived or stable nuclides has been in progress for 3 years under the direction of Oak Ridge National Laboratory (ORNL). This report constitutes the final assessment of transmutation in support of this program. Included are (1) a summary of recent transmutation literature, (2) a generic evaluation of actinide transmutation in thermal, fast, and other transmutation devices, (3) a preliminary evaluation of 99 Tc and 129 I transmutation, and (4) a characterization of a pressurized-water-reactor fuel cycle with and without provisions for actinide recovery and transmutation for use in other parts of the ORNL program. The principal conclusion of the report is that actinide transmutation is feasible in both thermal and fast reactors, subject to demonstrating satisfactory fuel performance, with relatively little impact on the reactor. It would also appear that additional transmutation studies are unwarranted until a firm decision to proceed with actinide transmutation has been made by the responsible authorities

  18. Steam generator tube integrity program: Phase II, Final report

    Energy Technology Data Exchange (ETDEWEB)

    Kurtz, R.J.; Bickford, R.L.; Clark, R.A.; Morris, C.J.; Simonen, F.A.; Wheeler, K.R.

    1988-08-01

    The Steam Generator Tube Integrity Program (SGTIP) was a three phase program conducted for the US Nuclear Regulatory Commission (NRC) by Pacific Northwest Laboratory (PNL). The first phase involved burst and collapse testing of typical steam generator tubing with machined defects. The second phase of the SGTIP continued the integrity testing work of Phase I, but tube specimens were degraded by chemical means rather than machining methods. The third phase of the program used a removed-from-service steam generator as a test bed for investigating the reliability and effectiveness of in-service nondestructive eddy-current inspection methods and as a source of service degraded tubes for validating the Phase I and Phase II data on tube integrity. This report describes the results of Phase II of the SGTIP. The object of this effort included burst and collapse testing of chemically defected pressurized water reactor (PWR) steam generator tubing to validate empirical equations of remaining tube integrity developed during Phase I. Three types of defect geometries were investigated: stress corrosion cracking (SCC), uniform thinning and elliptical wastage. In addition, a review of the publicly available leak rate data for steam generator tubes with axial and circumferential SCC and a comparison with an analytical leak rate model is presented. Lastly, nondestructive eddy-current (EC) measurements to determine accuracy of defect depth sizing using conventional and alternate standards is described. To supplement the laboratory EC data and obtain an estimate of EC capability to detect and size SCC, a mini-round robin test utilizing several firms that routinely perform in-service inspections was conducted.

  19. Steam generator tube integrity program: Phase II, Final report

    International Nuclear Information System (INIS)

    Kurtz, R.J.; Bickford, R.L.; Clark, R.A.; Morris, C.J.; Simonen, F.A.; Wheeler, K.R.

    1988-08-01

    The Steam Generator Tube Integrity Program (SGTIP) was a three phase program conducted for the US Nuclear Regulatory Commission (NRC) by Pacific Northwest Laboratory (PNL). The first phase involved burst and collapse testing of typical steam generator tubing with machined defects. The second phase of the SGTIP continued the integrity testing work of Phase I, but tube specimens were degraded by chemical means rather than machining methods. The third phase of the program used a removed-from-service steam generator as a test bed for investigating the reliability and effectiveness of in-service nondestructive eddy-current inspection methods and as a source of service degraded tubes for validating the Phase I and Phase II data on tube integrity. This report describes the results of Phase II of the SGTIP. The object of this effort included burst and collapse testing of chemically defected pressurized water reactor (PWR) steam generator tubing to validate empirical equations of remaining tube integrity developed during Phase I. Three types of defect geometries were investigated: stress corrosion cracking (SCC), uniform thinning and elliptical wastage. In addition, a review of the publicly available leak rate data for steam generator tubes with axial and circumferential SCC and a comparison with an analytical leak rate model is presented. Lastly, nondestructive eddy-current (EC) measurements to determine accuracy of defect depth sizing using conventional and alternate standards is described. To supplement the laboratory EC data and obtain an estimate of EC capability to detect and size SCC, a mini-round robin test utilizing several firms that routinely perform in-service inspections was conducted

  20. 77 FR 11367 - Defense Federal Acquisition Regulation Supplement; Extension of the Test Program for Negotiation...

    Science.gov (United States)

    2012-02-24

    ...DoD is issuing a final rule amending the Defense Federal Acquisition Regulation Supplement to extend the program period for the DoD Test Program for Negotiation of Comprehensive Small Business Subcontracting Plans.

  1. The Final Focus Test Beam laser referene system

    International Nuclear Information System (INIS)

    Bressler, V.E.; Ruland, R.E.

    1993-05-01

    The original design for the SLAC linac included an alignment reference system with 270 diffraction gratings situated along the 3000 meter linac. These gratings have provided SLAC with a global reference line repeatable to within 200 micro meters. For the Final Focus Test Beam, this laser system has been extended and 13 new diffraction gratings have been installed. Improvements targets and the availability of new instruments allows us to evaluate the performance of the laser reference system at the 510 micro meter level. An explanation of the system and the results of our evaluation are presented

  2. A Dynamic Alignment System for the Final Focus Test Beam

    International Nuclear Information System (INIS)

    Ruland, R.E.; Bressler, V.E.; Fischer, G.; Plouffe, D.; SLAC

    2005-01-01

    The Final Focus Test Beam (FFTB) was conceived as a technological stepping stone on the way to the next linear collider. Nowhere is this more evident than with the alignment subsystems. Alignment tolerances for components prior to beam turn are almost an order of magnitude smaller than for previous projects at SLAC. Position monitoring systems which operate independent of the beam are employed to monitor motions of the components locally and globally with unprecedented precision. An overview of the FFTB alignment system is presented herein

  3. 2004 Power marketing program final EIS - final environmental impact statement. Volume 2 - appendices

    International Nuclear Information System (INIS)

    1997-02-01

    This volume contains appendices to the Final Environmental Impact Statement (FEIS) for the Power Marketing Program proposal of the Western Area Power Administration. The FEIS identified peaking power scheduling as the environmentally preferred alternative, and presented the analysis of alternatives and environmental impacts. Sixteen appendices to the FEIS are included in this document. The appendices are: Statutory and Legal Framework; Sierra Nevada Region Customer Groups and Economic Regions; Renewable Technology Cost Information Matrix; Hydrological Assumptions; Recreation Resources; Archaeological and Historical Resources; Incremental Power Resources; Air Quality Regulatory Structure; Energy Generation; Stage Contents Relationships for Regulating Reservoirs; Power Costs; Socioeconomic Impacts; Projected Air Resource Impacts; Land use, Water Quality, and Solid Waste Impact Factors; Draft Environmental Impact Statement Comments and Responses, and Contractor Disclosure Statements. 21 figs., 24 tabs

  4. Final argument relating to the Canadian nuclear power program

    International Nuclear Information System (INIS)

    Robertson, J.A.L.

    1978-05-01

    This report is the second brief, and one of a number of documents, submitted by Atomic Energy of Canada Limited (AECL) to the Ontario Royal Commission on Electric Power Planning. It is intended to update the original brief (AECL--5800) with respect to those matters that emerged during the course of the hearings and which had not been fully anticipated in that brief, as well as to summarize the AECL position on the various issues. To enable it to qualify as a ''final argument'' it contains only evidence or material that has been presented to the Royal Commission and is provided with marginal notations identifying the source of each section. It is AECL's position that the Canadian nuclear power program provides a safe, proven and efficient means of making a needed contribution to electricity supply, while strengthening the economy through the deployment of indigenous technology and resources. (author)

  5. MHD diffuser model test program

    Energy Technology Data Exchange (ETDEWEB)

    Idzorek, J J

    1976-07-01

    Experimental results of the aerodynamic performance of seven candidate diffusers are presented to assist in determining their suitability for joining an MHD channel to a steam generator at minimum spacing. The three dimensional diffusers varied in area ratio from 2 to 3.8 and wall half angle from 2 to 5 degrees. The program consisted of five phases: (1) tailoring a diffuser inlet nozzle to a 15 percent blockage; (2) comparison of isolated diffusers at enthalpy ratios 0.5 to 1.0 with respect to separation characteristics and pressure recovery coefficients; (3) recording the optimum diffuser exit flow distribution; (4) recording the internal flow distribution within the steam generator when attached to the diffuser; and (5) observing isolated diffuser exhaust dynamic characteristics. The 2 and 2-1/3 degree half angle rectangular diffusers showed recovery coefficients equal to 0.48 with no evidence of flow separation or instability. Diffusion at angles greater than these produced flow instabilities and with angles greater than 3 degrees random flow separation and reattachment.

  6. MHD diffuser model test program

    International Nuclear Information System (INIS)

    Idzorek, J.J.

    1976-07-01

    Experimental results of the aerodynamic performance of seven candidate diffusers are presented to assist in determining their suitability for joining an MHD channel to a steam generator at minimum spacing. The three dimensional diffusers varied in area ratio from 2 to 3.8 and wall half angle from 2 to 5 degrees. The program consisted of five phases: (1) tailoring a diffuser inlet nozzle to a 15 percent blockage; (2) comparison of isolated diffusers at enthalpy ratios 0.5 to 1.0 with respect to separation characteristics and pressure recovery coefficients; (3) recording the optimum diffuser exit flow distribution; (4) recording the internal flow distribution within the steam generator when attached to the diffuser; and (5) observing isolated diffuser exhaust dynamic characteristics. The 2 and 2-1/3 degree half angle rectangular diffusers showed recovery coefficients equal to 0.48 with no evidence of flow separation or instability. Diffusion at angles greater than these produced flow instabilities and with angles greater than 3 degrees random flow separation and reattachment

  7. Pecan Street Grid Demonstration Program. Final technology performance report

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2015-02-10

    This document represents the final Regional Demonstration Project Technical Performance Report (TPR) for Pecan Street Inc.’s (Pecan Street) Smart Grid Demonstration Program, DE-OE-0000219. Pecan Street is a 501(c)(3) smart grid/clean energy research and development organization headquartered at The University of Texas at Austin (UT). Pecan Street worked in collaboration with Austin Energy, UT, Environmental Defense Fund (EDF), the City of Austin, the Austin Chamber of Commerce and selected consultants, contractors, and vendors to take a more detailed look at the energy load of residential and small commercial properties while the power industry is undergoing modernization. The Pecan Street Smart Grid Demonstration Program signed-up over 1,000 participants who are sharing their home or businesses’s electricity consumption data with the project via green button protocols, smart meters, and/or a home energy monitoring system (HEMS). Pecan Street completed the installation of HEMS in 750 homes and 25 commercial properties. The program provided incentives to increase the installed base of roof-top solar photovoltaic (PV) systems, plug-in electric vehicles with Level 2 charging, and smart appliances. Over 200 participants within a one square mile area took advantage of Austin Energy and Pecan Street’s joint PV incentive program and installed roof-top PV as part of this project. Of these homes, 69 purchased or leased an electric vehicle through Pecan Street’s PV rebate program and received a Level 2 charger from Pecan Street. Pecan Street studied the impacts of these technologies along with a variety of consumer behavior interventions, including pricing models, real-time feedback on energy use, incentive programs, and messaging, as well as the corresponding impacts on Austin Energy’s distribution assets.The primary demonstration site was the Mueller community in Austin, Texas. The Mueller development, located less than three miles from the Texas State Capitol

  8. In-situ thermal testing program strategy

    International Nuclear Information System (INIS)

    1995-06-01

    In the past year the Yucca Mountain Site Characterization Project has implemented a new Program Approach to the licensing process. The Program Approach suggests a step-wise approach to licensing in which the early phases will require less site information than previously planned and necessitate a lesser degree of confidence in the longer-term performance of the repository. Under the Program Approach, the thermal test program is divided into two principal phases: (1) short-term in situ tests (in the 1996 to 2000 time period) and laboratory thermal tests to obtain preclosure information, parameters, and data along with bounding information for postclosure performance; and (2) longer-term in situ tests to obtain additional data regarding postclosure performance. This effort necessitates a rethinking of the testing program because the amount of information needed for the initial licensing phase is less than previously planned. This document proposes a revised and consolidated in situ thermal test program (including supporting laboratory tests) that is structured to meet the needs of the Program Approach. A customer-supplier model is used to define the Project data needs. These data needs, along with other requirements, were then used to define a set of conceptual experiments that will provide the required data within the constraints of the Program Approach schedule. The conceptual thermal tests presented in this document represent a consolidation and update of previously defined tests that should result in a more efficient use of Project resources. This document focuses on defining the requirements and tests needed to satisfy the goal of a successful license application in 2001, should the site be found suitable

  9. AGR-2 Irradiation Test Final As-Run Report

    Energy Technology Data Exchange (ETDEWEB)

    Collin, Blaise P. [Idaho National Lab. (INL), Idaho Falls, ID (United States). VHTR Program

    2014-08-01

    This document presents the as-run analysis of the AGR-2 irradiation experiment. AGR-2 is the second of the planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the U.S. Department of Energy as part of the Very High Temperature Reactor (VHTR) Technology Development Office (TDO) program. The objectives of the AGR-2 experiment are to: 1. Irradiate UCO (uranium oxycarbide) and UO2 (uranium dioxide) fuel produced in a large coater. Fuel attributes are based on results obtained from the AGR-1 test and other project activities. 2. Provide irradiated fuel samples for post-irradiation experiment (PIE) and safety testing. 3. Support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. The primary objective of the test was to irradiate both UCO and UO2 TRISO (tristructural isotropic) fuel produced from prototypic scale equipment to obtain normal operation and accident condition fuel performance data. The UCO compacts were subjected to a range of burnups and temperatures typical of anticipated prismatic reactor service conditions in three capsules. The test train also includes compacts containing UO2 particles produced independently by the United States, South Africa, and France in three separate capsules. The range of burnups and temperatures in these capsules were typical of anticipated pebble bed reactor service conditions. The results discussed in this report pertain only to U.S.-produced fuel.

  10. AGR-2 Irradiation Test Final As-Run Report

    Energy Technology Data Exchange (ETDEWEB)

    Collin, Blaise P. [Idaho National Lab. (INL), Idaho Falls, ID (United States). VHTR Program

    2014-08-01

    This document presents the as-run analysis of the AGR-2 irradiation experiment. AGR-2 is the second of the planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the U.S. Department of Energy as part of the Very High Temperature Reactor (VHTR) Technical Development Office (TDO) program. The objectives of the AGR-2 experiment are to: (a) Irradiate UCO (uranium oxycarbide) and UO2 (uranium dioxide) fuel produced in a large coater. Fuel attributes are based on results obtained from the AGR-1 test and other project activities. (b) Provide irradiated fuel samples for post-irradiation experiment (PIE) and safety testing. (c) Support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. The primary objective of the test was to irradiate both UCO and UO2 TRISO (tri-structural isotropic) fuel produced from prototypic scale equipment to obtain normal operation and accident condition fuel performance data. The UCO compacts were subjected to a range of burnups and temperatures typical of anticipated prismatic reactor service conditions in three capsules. The test train also includes compacts containing UO2 particles produced independently by the United States, South Africa, and France in three separate capsules. The range of burnups and temperatures in these capsules were typical of anticipated pebble bed reactor service conditions. The results discussed in this report pertain only to U.S. produced fuel.

  11. CERTS Microgrid Laboratory Test Bed - PIER Final Project Report

    Energy Technology Data Exchange (ETDEWEB)

    Eto, Joseph H.; Eto, Joseph H.; Lasseter, Robert; Schenkman, Ben; Klapp, Dave; Linton, Ed; Hurtado, Hector; Roy, Jean; Lewis, Nancy Jo; Stevens, John; Volkommer, Harry

    2008-07-25

    The objective of the CERTS Microgrid Laboratory Test Bed project was to enhance the ease of integrating small energy sources into a microgrid. The project accomplished this objective by developing and demonstrating three advanced techniques, collectively referred to as the CERTS Microgrid concept, that significantly reduce the level of custom field engineering needed to operate microgrids consisting of small generating sources. The techniques comprising the CERTS Microgrid concept are: 1) a method for effecting automatic and seamless transitions between grid-connected and islanded modes of operation; 2) an approach to electrical protection within the microgrid that does not depend on high fault currents; and 3) a method for microgrid control that achieves voltage and frequency stability under islanded conditions without requiring high-speed communications. The techniques were demonstrated at a full-scale test bed built near Columbus, Ohio and operated by American Electric Power. The testing fully confirmed earlier research that had been conducted initially through analytical simulations, then through laboratory emulations, and finally through factory acceptance testing of individual microgrid components. The islanding and resychronization method met all Institute of Electrical and Electronics Engineers 1547 and power quality requirements. The electrical protections system was able to distinguish between normal and faulted operation. The controls were found to be robust and under all conditions, including difficult motor starts. The results from these test are expected to lead to additional testing of enhancements to the basic techniques at the test bed to improve the business case for microgrid technologies, as well to field demonstrations involving microgrids that involve one or mroe of the CERTS Microgrid concepts.

  12. 78 FR 29117 - After Final Consideration Pilot Program 2.0

    Science.gov (United States)

    2013-05-17

    ...] After Final Consideration Pilot Program 2.0 AGENCY: United States Patent and Trademark Office, Commerce... Final Consideration Pilot Program (AFCP) to create the After Final Consideration Pilot Program 2.0 (AFCP....0 to consider the response. If the examiner's consideration of a proper AFCP 2.0 request and...

  13. Wireless Roadside Inspection Proof of Concept Test Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Capps, Gary J [ORNL; Franzese, Oscar [ORNL; Knee, Helmut E [ORNL; Plate, Randall S [ORNL; Lascurain, Mary Beth [ORNL

    2009-03-01

    The U.S. Department of Transportation (DOT) FMCSA commissioned the Wireless Roadside Inspection (WRI) Program to validate technologies and methodologies that can improve safety through inspections using wireless technologies that convey real-time identification of commercial vehicles, drivers, and carriers, as well as information about the condition of the vehicles and their drivers. It is hypothesized that these inspections will: -- Increase safety -- Decrease the number of unsafe commercial vehicles on the road; -- Increase efficiency -- Speed up the inspection process, enabling more inspections to occur, at least on par with the number of weight inspections; -- Improve effectiveness -- Reduce the probability of drivers bypassing CMV inspection stations and increase the likelihood that fleets will attempt to meet the safety regulations; and -- Benefit industry -- Reduce fleet costs, provide good return-on-investment, minimize wait times, and level the playing field. The WRI Program is defined in three phases which are: Phase 1: Proof of Concept Test (POC) Testing of commercially available off-the-shelf (COTS) or near-COTS technology to validate the wireless inspection concept. Phase 2: Pilot Test Safety technology maturation and back office system integration Phase 3: Field Operational Test Multi-vehicle testing over a multi-state instrumented corridor This report focuses on Phase 1 efforts that were initiated in March, 2006. Technical efforts dealt with the ability of a Universal Wireless Inspection System (UWIS) to collect driver, vehicle, and carrier information; format a Safety Data Message Set from this information; and wirelessly transmit a Safety Data Message Set to a roadside receiver unit or mobile enforcement vehicle.

  14. The NRU blowdown test facility commissioning program

    Energy Technology Data Exchange (ETDEWEB)

    Walsworth, J A; Zanatta, R J; Yamazaki, A R; Semeniuk, D D; Wong, W; Dickson, L W; Ferris, C E; Burton, D H [Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs.

    1990-12-31

    A major experimental program has been established at the Chalk River Nuclear Laboratories (CRL) that will provide essential data on the thermal and mechanical behaviour of nuclear fuel under abnormal reactor operating conditions and on the transient release, transport and deposition of fission product activity from severely degraded fuel. A number of severe fuel damage (SFD) experiments will be conducted within the Blowdown Test Facility (BTF) at CRL. A series of experiments are being conducted to commission this new facility prior to the SFD program. This paper describes the features and the commissioning program for the BTF. A development and testing program is described for critical components used on the reactor test section. In-reactor commissioning with a fuel assembly simulator commenced in 1989 June and preliminary results are given. The paper also outlines plans for future all-effects, in-reactor tests of CANDU-designed fuel. (author). 11 refs., 3 tabs., 7 figs.

  15. Programmed Death-Ligand 1 Immunohistochemistry Testing

    DEFF Research Database (Denmark)

    Büttner, Reinhard; Gosney, John R; Skov, Birgit Guldhammer

    2017-01-01

    Purpose Three programmed death-1/programmed death-ligand 1 (PD-L1) inhibitors are currently approved for treatment of non-small-cell lung cancer (NSCLC). Treatment with pembrolizumab in NSCLC requires PD-L1 immunohistochemistry (IHC) testing. Nivolumab and atezolizumab are approved without PD-L1...

  16. Aluminized film, seam sealing tests and observations. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-16

    The purpose of this work was to investigate various seam sealing techniques, reinforcing methods, fitting installations, seam tolerances and geometric configurations pertinent to an aluminized plastic laminate. The program seeks a successful fabricating method for producing low-diffusion, cylindrical, spar liners to contain pressurized GH{sub 2} and GO{sub 2}. The test plan included: (1) seaming techniques on metallized Mylar film; (2) ``double patches`` for end fittings; (3) stainless steel bulkhead fitting assembly with seals; (4) minimum run tolerance on linear shear seam; (5) peel seam vs. inverted seal seam fabrication.

  17. Program Helps Design Tests Of Developmental Software

    Science.gov (United States)

    Hops, Jonathan

    1994-01-01

    Computer program called "A Formal Test Representation Language and Tool for Functional Test Designs" (TRL) provides automatic software tool and formal language used to implement category-partition method and produce specification of test cases in testing phase of development of software. Category-partition method useful in defining input, outputs, and purpose of test-design phase of development and combines benefits of choosing normal cases having error-exposing properties. Traceability maintained quite easily by creating test design for each objective in test plan. Effort to transform test cases into procedures simplified by use of automatic software tool to create cases based on test design. Method enables rapid elimination of undesired test cases from consideration and facilitates review of test designs by peer groups. Written in C language.

  18. Modular Electric Vehicle Program (MEVP). Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-03-01

    The Modular Electric Vehicle Program (MEVP) was an EV propulsion system development program in which the technical effort was contracted by DOE to Ford Motor Company. The General Electric Company was a major subcontractor to Ford for the development of the electric subsystem. Sundstrand Power Systems was also a subcontractor to Ford, providing a modified gas turbine engine APU for emissions and performance testing as well as a preliminary design and producibility study for a Gas Turbine-APU for potential use in hybrid/electric vehicles. The four-year research and development effort was cost-shared between Ford, General Electric, Sundstrand Power Systems and DOE. The contract was awarded in response to Ford`s unsolicited proposal. The program objective was to bring electric vehicle propulsion system technology closer to commercialization by developing subsystem components which can be produced from a common design and accommodate a wide range of vehicles; i.e., modularize the components. This concept would enable industry to introduce electric vehicles into the marketplace sooner than would be accomplished via traditional designs in that the economies of mass production could be realized across a spectrum of product offerings. This would eliminate the need to dedicate the design and capital investment to a limited volume product offering which would increase consumer cost and/or lengthen the time required to realize a return on the investment.

  19. Innovative improvements of thermal response tests - Final report

    Energy Technology Data Exchange (ETDEWEB)

    Poppei, J.; Schwarz, R. [AF-Colenco Ltd, Baden (Switzerland); Peron, H.; Silvani, C; Steinmann, G.; Laloui, L. [Swiss Federal Institute of Technology, Laboratoire de Mecanique des Sols, Lausanne (Switzerland); Wagner, R.; Lochbuehler, T.; Rohner, E. [Geowatt AG, Zuerich (Switzerland)

    2008-12-15

    This illustrated final report for Swiss Federal Office of Energy (SFOE) takes a look at innovative improvements to thermal response tests that are used to investigate the thermo-physical properties of the ground for the purpose of dimensioning borehole heat exchangers. Recent technical developments in the borehole investigation tools area provide a promising prerequisite for improved estimates of thermal conductivity. A mini-module developed at the Swiss Federal Institute of Technology EPFL which is suitable for fast and flexible thermal response testing is discussed as is a wireless miniature data logger for continuous temperature recordings in borehole heat exchangers up to a depth of 350 m. This allows high-resolution vertical temperature profiling in boreholes. International state-of-the-art methods are reviewed. The adaptations to the analytical methods necessary for the effective application of these tools are discussed and numerical methods available are looked at. The testing of the methods developed and their results are discussed, as is the influence of ground-water flow.

  20. Final focus test beam alignment: A draft proposal

    International Nuclear Information System (INIS)

    Fischer, G.E.; Ruland, R.E.

    1989-03-01

    The Final Focus Test Beam is a transport line designed to transmit 50 GeV electron beams of SLC emittance (3 x 10 -10 radian-meters) straight through the central arm of the Beam Switchyard (BSY C line) with a final focus point out in the Research Yard but relatively near the end of the switchyard tunnel. The hardware, methods and procedures outlined in this proposal are dedicated to measuring the placement of mechanical objects with respect to certain defined geometric axes. We wish to emphasize that the very difficult problems of locating the effective magnetic axes of focusing elements, the effective electrical center of beam position monitors and even the effective axis of the incident beam relative to mechanical reference surfaces is outside the scope of this work. Further, this proposal is restricted to the act of measurement and does not consider the vital task of on-line mechanical repositioning of elements that will, in likelihood, be called upon during operation of the system. 16 refs., 16 figs., 4 tabs

  1. The advanced test reactor strategic evaluation program

    International Nuclear Information System (INIS)

    Buescher, B.J.

    1989-01-01

    Since the Chernobly accident, the safety of test reactors and irradiation facilities has been critically evaluated from the public's point of view. A systematic evaluation of all safety, environmental, and operational issues must be made in an integrated manner to prioritize actions to maximize benefits while minimizing costs. Such a proactive program has been initiated at the Advanced Test Reactor (ATR). This program, called the Strategic Evaluation Program (STEP), is being conducted for the ATR to provide integrated safety and operational reviews of the reactor against the standards applied to licensed commercial power reactors. This has taken into consideration the lessons learned by the US Nuclear Regulatory Commission (NRC) in its Systematic Evaluation Program (SEP) and the follow-on effort known as the Integrated Safety Assessment Program (ISAP). The SEP was initiated by the NRC to review the designs of older operating nuclear power plants to confirm and document their safety. The ATR STEP objectives are discussed

  2. 77 FR 47302 - South Dakota: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-08-08

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... EPA proposed to authorize South Dakota's State Hazardous waste management Program revisions published... to the hazardous waste program revisions submitted by South Dakota. The Agency published a Proposed...

  3. 77 FR 15273 - Oklahoma: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2012-03-15

    ...: Final Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental... hazardous waste management program. We authorized the following revisions: Oklahoma received authorization... its program revision in accordance with 40 CFR 271.21. The Oklahoma Hazardous Waste Management Act...

  4. Periodical test program in depth revision

    International Nuclear Information System (INIS)

    Feltin, C.; Zermizoglou, R.

    1987-11-01

    Inspection visits made to different sites during 1980 and 1981 evidenced the need to extend and define more precisely the periodical tests performed on safety related systems; thus Electricite de France was requested by the Safety Authorities to re-examine the periodical test program for all safety related systems. This paper presents the methodology adopted by Electricite de France in order to perform an exhaustive analysis of the periodical test program for the 900 and 1300 MWe plants, and the organization set up at the IPSN at one hand and Electricite de France on the other hand for the purpose of elaborating a periodical test program which would be ratified by the Safety Authorities

  5. Recommended well drilling and testing program

    International Nuclear Information System (INIS)

    Long, J.; Wilson, C.

    1978-07-01

    A well drilling and testing program is recommended by Lawrence Berkeley Laboratory to identify the hydrology of deep basalts in the Pasco Basin. The ultimate objective of this program is to assist in determining the feasibility of locating a nuclear waste repository on the Hanford Reservation. The recommended program has been staged for maximum effectiveness. In the first stage, six wells have been identified for drilling and testing which, when coupled with existing wells, will provide sufficient data for a preliminary overview of basin hydrology and a preliminary determination of the hydrologic suitability of the deep basalt for a repository site. The rate at which the first stage wells are drilled and tested will depend upon the date at which a preliminary determination of site suitability is required. It was assumed that a preliminary determination of suitability would be required in 1980, in which case all six first stage wells would be drilled in FY 1979. If the results of the first stage analysis are favorable for repository siting, tentative repository sites can be identified and a second stage hydrology program can be implemented to provide the necessary details of the flow system. To accomplish this stage, a number of deep wells would be required at locations both inside and outside the basin, with specific sites to be identified as the work progresses to obtain maximum utility of existing data. A program is recommended for testing in each new well and for completion of testing in each existing well. Recommended tests include borehole geophysics, pressure and permeability testing, geochemical sampling, tracer testing, hydrofracturing and borehole fracture logging. The entire data collection program is oriented toward providing the information required to establish and verify an accurate numerical model of the Pasco Basin

  6. Design, construction and testing of a DC bioeffects test enclosure for small animals. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Frazier, M J; Preache, M M

    1980-11-01

    This final report describes both the engineering development of a DC bioeffects test enclosure for small laboratory animals, and the biological protocol for the use of such enclosures in the testing of animals to determine possible biological effects of the environment associated with HVDC transmission lines. The test enclosure which has been designed is a modular unit, which will house up to eight rat-sized animals in individual compartments. Multiple test enclosures can be used to test larger numbers of animals. A prototype test enclosure has been fabricated and tested to characterize its electrical performance characteristics. The test enclosure provides a simulation of the dominant environment associated with HVDC transmission lines; namely, a static electric field and an ion current density. A biological experimental design has been developed for assessing the effects of the dominant components of the HVDC transmission line environment.

  7. The plane strain tests in the PROMETRA program

    International Nuclear Information System (INIS)

    Cazalis, B.; Desquines, J.; Carassou, S.; Le Jolu, T.; Bernaudat, C.

    2016-01-01

    A fuel cladding mechanical test, performed under conditions of plane strain deformation in the transverse direction of tube axis, was originally developed at Pennsylvania State University. It was decided to implement this original test within the PROMETRA program using the same experimental procedure and its optimization for a ring mechanical testing on plane strain conditions (PST tests) in hot cells laboratory. This paper presents a detailed description and an interpretation of the Plane Strain Tensile (PST) tests performed in the framework of the PROMETRA program on fresh and irradiated claddings. At first, the context of the PST tests is situated and the specificities of these tests implemented at CEA are justified. Indeed, a significant adjustment of the original experimental procedure is carried out in order to test the irradiated fuel cladding in the best possible conditions. Then, the tests results on fresh Zircaloy-4 and on irradiated Zircaloy-4, M5™ and ZIRLO ® specimens are gathered. The main analyses in support of these tests, such as metallographies, fractographic examinations and finite element simulations are detailed. Finally, a synthesis of the interpretation of the tests is proposed. The PST test seems only representative of plane strain fracture conditions when the test material is very ductile (fresh or high temperature or low hydride material like M5TM). However, it provides a relevant representation of the RIA rupture initiation which is observed in irradiated cladding resulting from hydride rim damage due to the strong irradiation of a fuel rod. - Highlights: • A plane strain mechanical test performed on fuel rod claddings is described. • The tests are performed in the framework of the French PROMETRA program. • Fresh Zircaloy-4 and irradiated Zircaloy-4, M5 and ZIRLO specimens are tested. • The main analyses in support of these tests are detailed. • A synthesis of the interpretation of the PST tests is proposed.

  8. The plane strain tests in the PROMETRA program

    Energy Technology Data Exchange (ETDEWEB)

    Cazalis, B., E-mail: bernard.cazalis@irsn.fr [Institut de Radioprotection et de Sûreté Nucléaire, IRSN/PSN-RES, F-13115 Saint-Paul Lez Durance BP3 (France); Desquines, J. [Institut de Radioprotection et de Sûreté Nucléaire, IRSN/PSN-RES, F-13115 Saint-Paul Lez Durance BP3 (France); Carassou, S.; Le Jolu, T. [Commissariat à l' Energie Atomique, CEA/DEN/DMN, F- 91191 Gif-sur-Yvette (France); Bernaudat, C. [Electricité de France, EDF/SEPTEN, F-69628 Villeurbanne (France)

    2016-04-15

    A fuel cladding mechanical test, performed under conditions of plane strain deformation in the transverse direction of tube axis, was originally developed at Pennsylvania State University. It was decided to implement this original test within the PROMETRA program using the same experimental procedure and its optimization for a ring mechanical testing on plane strain conditions (PST tests) in hot cells laboratory. This paper presents a detailed description and an interpretation of the Plane Strain Tensile (PST) tests performed in the framework of the PROMETRA program on fresh and irradiated claddings. At first, the context of the PST tests is situated and the specificities of these tests implemented at CEA are justified. Indeed, a significant adjustment of the original experimental procedure is carried out in order to test the irradiated fuel cladding in the best possible conditions. Then, the tests results on fresh Zircaloy-4 and on irradiated Zircaloy-4, M5™ and ZIRLO{sup ®} specimens are gathered. The main analyses in support of these tests, such as metallographies, fractographic examinations and finite element simulations are detailed. Finally, a synthesis of the interpretation of the tests is proposed. The PST test seems only representative of plane strain fracture conditions when the test material is very ductile (fresh or high temperature or low hydride material like M5TM). However, it provides a relevant representation of the RIA rupture initiation which is observed in irradiated cladding resulting from hydride rim damage due to the strong irradiation of a fuel rod. - Highlights: • A plane strain mechanical test performed on fuel rod claddings is described. • The tests are performed in the framework of the French PROMETRA program. • Fresh Zircaloy-4 and irradiated Zircaloy-4, M5 and ZIRLO specimens are tested. • The main analyses in support of these tests are detailed. • A synthesis of the interpretation of the PST tests is proposed.

  9. Engine testing of ceramic cam-roller followers. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Kalish, Y. [Detroit Diesel Corp., MI (United States)

    1992-04-01

    For several years, DDC has been developing monolithic ceramic heat engine components. One of the components, developed for an application in our state-of-the-art on-highway, heavy-duty diesel engine, the Series 60, is a silicon nitride cam-roller follower. Prior to starting this program, each valve train component in the Series 60 was considered for conversion to a ceramic material. Many advantages and disadvantages (benefits and risks) were considered. From this effort, one component was selected, the cam-roller follower. Using a system design approach, a ceramic cam-roller follower offered functional improvement at a reasonable cost. The purpose of the project was to inspect and test 100 domestically produced silicon nitride cam-roller followers built to the requirements of the DDC series 60 engine.

  10. Final state effects in liquid 4He: An experimental test

    International Nuclear Information System (INIS)

    Sokol, P.E.; Silver, R.N.; Sosnick, T.R.; Snow, W.M.

    1989-01-01

    Inelastic neutron scattering at high momentum transfers can provide direct information on the atomic momentum distribution n(p) when the Impulse Approximation (IA) is valid. In isotropic systems, the scattering in the IA is directly proportional to the longitudinal momentum distribution which is a function of a single scaling variable Y /triple bond/ (M/Q)(ω /minus/ ω/sub r/), where M is the mass of the scatterer, Q is the momentum transfer, and ω/sub r/ = Q 2 /2M is the recoiled energy. However, the experimentally attainable Q's are not large enough to reach the IA limit. Deviations from the IA due to final state scattering by neighboring atoms, known as final state effects, will distort the observed scattering from the IA prediction. Thus, an understanding of deviations from the IA is essential to accurate determination of n(p). Liquid helium provides an excellent testing ground for studying FSE in a dense, strongly interacting system for two reasons. First, theoretical calculations of the momentum distributions are available in both the normal liquid, and superfluid phases. These calculations are believed to be quite accurate, since they agree well with several other measured properties of the liquid. In addition, n(p) in the superfluid exhibits a very sharp feature, the Bose condensate peak, which should be very sensitive to FSE. Comparison of the predicted scattering obtained from the theoretical n(p) using the IA to the experimentally observed scattering can be used to study deviations due to FSE. 14 refs., 7 figs

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-07-01

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

  12. Quality assurance in the nuclear test program

    International Nuclear Information System (INIS)

    Shearer, J.N.

    1979-01-01

    In February 1979 Test Program laid the ground work for a new quality assurance structure. The new approach was based on the findings and recommendations of the Ad Hoc QA Program Review panel, which are summarized in this report. The new structure places the responsibility for quality assurance in the hands of the line organizations, both in the programmatic and functional elements of the LLL matrix

  13. A Comprehensive Child Development Program; Title XX, Final Report.

    Science.gov (United States)

    Whatley, Juanita T.

    This booklet describes the Comprehensive Child Day Care Program for the Atlanta Public School System, a Title XX Program. This program provided day care services for children of clients in various categories. The program goals for 1975-76 were geared toward providing comprehensive day care to encompass social services to the family and…

  14. GTS Duratek, phase I Hanford low-level waste melter tests: Final report

    International Nuclear Information System (INIS)

    Eaton, W.C.

    1995-01-01

    A multiphase program was initiated in 1994 to test commercially available melter technologies for the vitrification of the low-level waste (LLW) stream from defense waste stored in underground tanks at the Hanford Site in southeastern Washington State. Phase 1 of the melter demonstration tests using simulated LLW was completed during fiscal year 1995. This document is the final report on testing performed by GTS Duratek Inc. in Columbia, Maryland. GTS Duratek (one of the seven vendors selected) was chosen to demonstrate Joule heated melter technology under WHC subcontract number MMI-SVV-384215. The report contains description of the tests, observations, test data and some analysis of the data as it pertains to application of this technology for LLW vitrification. The document also contains summaries of the melter offgas reports issued as separate documents for the 100 kg melter (WHC-SD-WM-VI-028) and for the 1000 kg melter (WHC-SD-WM-VI-029)

  15. Programs for Testing Processor-in-Memory Computing Systems

    Science.gov (United States)

    Katz, Daniel S.

    2006-01-01

    The Multithreaded Microbenchmarks for Processor-In-Memory (PIM) Compilers, Simulators, and Hardware are computer programs arranged in a series for use in testing the performances of PIM computing systems, including compilers, simulators, and hardware. The programs at the beginning of the series test basic functionality; the programs at subsequent positions in the series test increasingly complex functionality. The programs are intended to be used while designing a PIM system, and can be used to verify that compilers, simulators, and hardware work correctly. The programs can also be used to enable designers of these system components to examine tradeoffs in implementation. Finally, these programs can be run on non-PIM hardware (either single-threaded or multithreaded) using the POSIX pthreads standard to verify that the benchmarks themselves operate correctly. [POSIX (Portable Operating System Interface for UNIX) is a set of standards that define how programs and operating systems interact with each other. pthreads is a library of pre-emptive thread routines that comply with one of the POSIX standards.

  16. AGR 3/4 Irradiation Test Final As Run Report

    Energy Technology Data Exchange (ETDEWEB)

    Collin, Blaise P. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-06-01

    Several fuel and material irradiation experiments have been planned for the Idaho National Laboratory Advanced Reactor Technologies Technology Development Office Advanced Gas Reactor Fuel Development and Qualification Program (referred to as the INL ART TDO/AGR fuel program hereafter), which supports the development and qualification of tristructural-isotropic (TRISO) coated particle fuel for use in HTGRs. The goals of these experiments are to provide irradiation performance data to support fuel process development, qualify fuel for normal operating conditions, support development and validation of fuel performance and fission product transport models and codes, and provide irradiated fuel and materials for post irradiation examination and safety testing (INL 05/2015). AGR-3/4 combined the third and fourth in this series of planned experiments to test TRISO coated low enriched uranium (LEU) oxycarbide fuel. This combined experiment was intended to support the refinement of fission product transport models and to assess the effects of sweep gas impurities on fuel performance and fission product transport by irradiating designed-to-fail fuel particles and by measuring subsequent fission metal transport in fuel-compact matrix material and fuel-element graphite. The AGR 3/4 fuel test was successful in irradiating the fuel compacts to the burnup and fast fluence target ranges, considering the experiment was terminated short of its initial 400 EFPD target (Collin 2015). Out of the 48 AGR-3/4 compacts, 42 achieved the specified burnup of at least 6% fissions per initial heavy-metal atom (FIMA). Three capsules had a maximum fuel compact average burnup < 10% FIMA, one more than originally specified, and the maximum fuel compact average burnup was <19% FIMA for the remaining capsules, as specified. Fast neutron fluence fell in the expected range of 1.0 to 5.5×1025 n/m2 (E >0.18 MeV) for all compacts. In addition, the AGR-3/4 experiment was globally successful in keeping the

  17. Tritium systems test assembly quality assurance program

    International Nuclear Information System (INIS)

    Kerstiens, F.L.; Wilhelm, R.C.

    1986-07-01

    A quality assurance program should establish the planned and systematic actions necessary to provide adequate confidence that fusion facilities and their subsystems will perform satisfactorily in service. The Tritium Systems Test Assembly (TSTA) Quality Assurance Program has been designed to assure that the designs, tests, data, and interpretive reports developed at TSTA are valid, accurate, and consistent with formally specified procedures and reviews. The quality consideration in all TSTA activities is directed toward the early detection of quality problems, coupled with timely and positive disposition and corrective action

  18. Fast Flux Test Facility final safety analysis report. Amendment 72

    Energy Technology Data Exchange (ETDEWEB)

    Gantt, D. A.

    1992-08-01

    This document provides the Final Safety Analysis Report (FSAR) Amendment 72 for incorporation into the Fast Flux Test Facility (FFTF) FSAR set. This amendment change incorporates Engineering Change Notices issued subsequent to Amendment 71 and approved for incorporation before June 24, 1992. These include changes in: Chapter 2, Site Characteristics; Chapter 3, Design Criteria Structures, Equipment, and Systems; Chapter 5B, Reactor Coolant System; Chapter 7, Instrumentation and Control Systems; Chapter 8, Electrical Systems - The description of the Class 1E, 125 Vdc systems is updated for the higher capacity of the newly installed, replacement batteries; Chapter 9, Auxiliary Systems - The description of the inert cell NASA systems is corrected to list the correct number of spare sample points; Chapter 11, Reactor Refueling System; Chapter 12, Radiation Protection and Waste Management; Chapter 13, Conduct of Operations; Chapter 16, Quality Assurance; Chapter 17, Technical Specifications; Chapter 19, FFTF Fire Specifications for Fire Detection, Alarm, and Protection Systems; Chapter 20, FFTF Criticality Specifications; and Appendix B, Primary Piping Integrity Evaluation.

  19. In-situ test programs related to design and construction of high-level nuclear waste (HLW) deep geologic repositories. Appendices. Final report (Task 2), June 1981-November 1982

    International Nuclear Information System (INIS)

    Roberds, W.; Bauhof, F.; Gonano, L.

    1983-03-01

    The media and sites considered include: (1) basalt at Hanford, Washington; (2) tuff at Yucca Mountain, Nevada Test Site; (3) domal salt at specific Gulf Coast sites; (4) bedded salt at an unspecified site; and (5) granite at an unspecified site. A licensing perspective is outlined and a defensible rationale developed and utilized for the test selection process. This rationale essentially consists of: establishing the information needs for construction authorization; assessing the relevant capabilities of available tests; and matching the capabilities of specific tests to the perceived information needs. The information needs at any time consist of the additional information (if any) needed in order to predict satisfactory repository system performance with the required level of confidence, and thus are a function of: the significance of the repository engineered components and site characteristics to system performance; the currently available information, which may be supplemented with time; and the acceptable level of confidence in satisfactory performance for each licensing step. Determination of the acceptable levels of confidence and the significance of repository system components is outside the scope of this report. Suitable assumptions have thus been made regarding the development of information needs for construction authorization by the time of initial site characterization reports submittals. Tests which are available and respond to the perceived media/site specific information needs, either by simulation or assessment of site characteristics, are identified and their capabilities assessed. Specific in situ tests are investigated and described in detail. Research and development which might be effective in improving tests capabilities have been recommended

  20. 76 FR 37021 - Louisiana: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2011-06-24

    ...: Final Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental... implement its base Hazardous Waste Management Program. We granted authorization for changes to their program... opportunity to apply for final authorization to operate all aspects of their hazardous waste management...

  1. Pre-study for the development of R and D-program for the plant DEPRA (demonstration and testing of technologies for wastewater and sludge treatment). Final report; Voruntersuchung zur Ausarbeitung der F und E-Konzeption der DEPRA. Abschlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Raebiger, N.

    2002-07-01

    The purpose of the planned demonstration and testing plant (DEPRA) in Bremerhaven is to have a possibility to demonstrate and test new or further developed wastewater and sludge treatments in industrial scale. With that DEPRA will contribute to transfer attained results of research and development as soon as possible in to practice. The plant DEPRA will provide extensive possibilities of process control of different stages of wastewater and sludge treatment as well as the operation of additional process stages. The demonstration and testing plant should be open for research institutes and commercial users in Germany as well as for European countries in order to offer a possibility for projects concerning water purification. The aim of this study was to compile the framework of research projects for DEPRA. This report indicates trends of development for purification of municipal and industrial wastewater and sludge treatment whereas the potential of innovation for short, middle and long time implementation is considered. (orig.)

  2. The WIPP research and development test program

    International Nuclear Information System (INIS)

    Tyler, L.D.

    1985-01-01

    The WIPP (Waste Isolation Pilot Plant) is a DOE RandD Facility for the purpose of developing the technology needed for the safe disposal of the United States defense-related radioactive waste. The in-situ test program is defined for the thermal-structural interactions, plugging and sealing, and waste package interactions in a salt environment. An integrated series of large-scale underground tests address the issues of both systems and long-term isolation performance of a repository

  3. Cooperative field test program for wind systems

    Energy Technology Data Exchange (ETDEWEB)

    Bollmeier, W.S. II; Dodge, D.M.

    1992-03-01

    The objectives of the Federal Wind Energy Program, managed by the US Department of Energy (DOE), are (1) to assist industry and utilities in achieving a multi-regional US market penetration of wind systems, and (2) to establish the United States as the world leader in the development of advanced wind turbine technology. In 1984, the program conducted a series of planning workshops with representatives from the wind energy industry to obtain input on the Five-Year Research Plan then being prepared by DOE. One specific suggestion that came out of these meetings was that the federal program should conduct cooperative research tests with industry to enhance the technology transfer process. It was also felt that the active involvement of industry in DOE-funded research would improve the state of the art of wind turbine technology. DOE established the Cooperative Field Test Program (CFTP) in response to that suggestion. This program was one of the first in DOE to feature joint industry-government research test teams working toward common objectives.

  4. Assessment of the Fusion Energy Sciences Program. Final Report

    International Nuclear Information System (INIS)

    2001-01-01

    An assessment of the Office of Fusion Energy Sciences (OFES) program with guidance for future program strategy. The overall objective of this study is to prepare an independent assessment of the scientific quality of the Office of Fusion Energy Sciences program at the Department of Energy. The Fusion Science Assessment Committee (FuSAC) has been appointed to conduct this study

  5. Community Solar Program Final Report for Austin Energy

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2013-02-10

    Austin Energy seeks to expand its portfolio of renewable programs with an innovative community solar program. The program provides an opportunity for Austin Energy's customers, who are unable or uninterested in installing solar on their own premises, to purchase solar power.

  6. Advanced Certification Program for Computer Graphic Specialists. Final Performance Report.

    Science.gov (United States)

    Parkland Coll., Champaign, IL.

    A pioneer program in computer graphics was implemented at Parkland College (Illinois) to meet the demand for specialized technicians to visualize data generated on high performance computers. In summer 1989, 23 students were accepted into the pilot program. Courses included C programming, calculus and analytic geometry, computer graphics, and…

  7. Middle East Studies Teacher Training Program. Final Report.

    Science.gov (United States)

    Sefein, Naim A.

    This guide presents a teacher training program in Middle Eastern studies and procedures for program implementation. Details concerning program announcement, participant selection, and travel accommodations are included. Participants attended an orientation and registration workshop and an intensive academic workshop before flying to Egypt for the…

  8. 47 CFR 73.1620 - Program tests.

    Science.gov (United States)

    2010-10-01

    ... integration of ownership and management and diversification of the media of mass communciation contained in... 47 Telecommunication 4 2010-10-01 2010-10-01 false Program tests. 73.1620 Section 73.1620 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) BROADCAST RADIO SERVICES RADIO BROADCAST SERVICES...

  9. Qualitative pre-test of Energy Star advertising : final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-01-01

    Natural Resources Canada launched a print advertising campaign and one 30-second television commercial to promote the Energy Star symbol and to acquaint the public with the program that identifies energy efficient products that reduce energy use, save money and reduce greenhouse gas emissions that contribute to climate change. The Communications Branch of Natural Resources Canada wanted to pre-test the television and print ads. Each print ad focused on a particular product category, including home comfort, appliances, electronics and office equipment. The qualitative research methodology was used in the pre-testing because it is the best learning tool for understanding the range and depth of reactions toward a subject at any given time. The findings were not quantifiable because they are not representative of the population at large. Ten focus groups were surveyed in January 2003 in 5 Canadian centres with a total of 83 participants aged 18 to 54. The target groups included people who were informed about climate change issues as well as those who were note. Participants were questioned about the Energy Star Product. Findings were consistent across all 5 locations. There was some general awareness of EnerGuide on appliances in all groups, but generally a low awareness of the Energy Star symbol. Most people did not place energy efficiency as a high priority when purchasing appliances. This report presented the main findings of attitudes towards climate change, Kyoto and energy efficiency. The reaction to the television and print ads was also included along with opinions regarding their main weaknesses and strengths. Some recommendations for improvement were also included. Samples of the print advertisements were included in both English and French. tabs., figs.

  10. Integrated Data Collection Analysis (IDCA) Program - Final Review September 12, 2012 at DHS

    Energy Technology Data Exchange (ETDEWEB)

    Sandstrom, Mary M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Brown, Geoffrey W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Warner, Kirstin F. [Naval Surface Warfare Center (NSWC), Indian Head, MD (United States). Indian Head Division; Phillips, Jason J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Shelley, Timothy J. [Air Force Research Lab. (AFRL), Tyndall AFB, FL (United States); Reyes, Jose A. [Applied Research Associates, Tyndall AFB, FL (United States); Hsu, Peter C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Reynolds, John G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2012-11-26

    The Integrated Data Collection Analysis (IDCA) program conducted a final program review at the Department of Homeland Security on September 12, 2012. The review was focused on the results of the program over the complete performance period. A summary presentation delineating the accomplished tasks started the meeting, followed by technical presentations on various issues that arose during the performance period. The presentations were completed with a statistical evaluation of the testing results from all the participants in the IDCA Proficiency Test study. The meeting closed with a discussion of potential sources of funding for continuing work to resolve some of these technical issues. This effort, funded by the Department of Homeland Security (DHS), put the issues of safe handling of these materials in perspective with standard military explosives. The study added Small-Scale Safety and Thermal (SSST) testing results for a broad suite of different HMEs to the literature, and suggested new guidelines and methods to develop safe handling practices for HMEs. Each participating testing laboratory used identical test materials and preparation methods wherever possible. Note, however, the test procedures differ among the laboratories. The results were compared among the laboratories and then compared to historical data from various sources. The testing performers involved were Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Naval Surface Warfare Center, Indian Head Division (NSWC IHD), Sandia National Laboratories (SNL), and Air Force Research Laboratory, Tyndall AFB (AFRL/RXQL). These tests were conducted as a proficiency study in order to establish some consistency in test protocols, procedures, and experiments and to compare results when these testing variables cannot be made consistent.

  11. WSEAT Shock Testing Margin Assessment Using Energy Spectra Final Report.

    Energy Technology Data Exchange (ETDEWEB)

    Sisemore, Carl; Babuska, Vit; Booher, Jason

    2018-02-01

    Several programs at Sandia National Laboratories have adopted energy spectra as a metric to relate the severity of mechanical insults to structural capacity. The purpose being to gain insight into the system's capability, reliability, and to quantify the ultimate margin between the normal operating envelope and the likely system failure point -- a system margin assessment. The fundamental concern with the use of energy metrics was that the applicability domain and implementation details were not completely defined for many problems of interest. The goal of this WSEAT project was to examine that domain of applicability and work out the necessary implementation details. The goal of this project was to provide experimental validation for the energy spectra based methods in the context of margin assessment as they relate to shock environments. The extensive test results concluded that failure predictions using energy methods did not agree with failure predictions using S-N data. As a result, a modification to the energy methods was developed following the form of Basquin's equation to incorporate the power law exponent for fatigue damage. This update to the energy-based framework brings the energy based metrics into agreement with experimental data and historical S-N data.

  12. Final test results for the ground operations demonstration unit for liquid hydrogen

    Science.gov (United States)

    Notardonato, W. U.; Swanger, A. M.; Fesmire, J. E.; Jumper, K. M.; Johnson, W. L.; Tomsik, T. M.

    2017-12-01

    Described herein is a comprehensive project-a large-scale test of an integrated refrigeration and storage system called the Ground Operations and Demonstration Unit for Liquid Hydrogen (GODU LH2), sponsored by the Advanced Exploration Systems Program and constructed at Kennedy Space Center. A commercial cryogenic refrigerator interfaced with a 125,000 l liquid hydrogen tank and auxiliary systems in a manner that enabled control of the propellant state by extracting heat via a closed loop Brayton cycle refrigerator coupled to a novel internal heat exchanger. Three primary objectives were demonstrating zero-loss storage and transfer, gaseous liquefaction, and propellant densification. Testing was performed at three different liquid hydrogen fill-levels. Data were collected on tank pressure, internal tank temperature profiles, mass flow in and out of the system, and refrigeration system performance. All test objectives were successfully achieved during approximately two years of testing. A summary of the final results is presented in this paper.

  13. NRC valve performance test program - check valve testing

    International Nuclear Information System (INIS)

    Jeanmougin, N.M.

    1987-01-01

    The Valve Performance Test Program addresses the current requirements for testing of pressure isolation valves (PIVs) in light water reactors. Leak rate monitoring is the current method used by operating commercial power plants to survey the condition of their PIVs. ETEC testing of three check valves (4-inch, 6-inch, and 12-inch nominal diameters) indicates that leak rate testing is not a reliable method for detecting impending valve failure. Acoustic emission monitoring of check valves shows promise as a method of detecting loosened internals damage. Future efforts will focus on evaluation of acoustic emission monitoring as a technique for determining check valve condition. Three gate valves also will be tested to evaluate whether the check valve results are applicable to gate type PIVs

  14. Final Technical Report_Clean Energy Program_SLC-SELF

    Energy Technology Data Exchange (ETDEWEB)

    Henderson, Glenn; Coward, Doug

    2014-01-22

    This is the Final Technical Report for DOE's Energy Efficiency and Conservation Block Grant, Award No. DE-EE0003813, submitted by St. Lucie County, FL (prime recipient) and the Solar and Energy Loan Fund (SELF), the program's third-party administrator. SELF is a 501(c)(3) and a certified Community Development Financial Institution (CDFI). SELF is a community-based lending organization that operates the Clean Energy Loan Program, which focuses on improving the overall quality of life of underserved populations in Florida with an emphasis on home energy improvements and cost-effective renewable energy alternatives. SELF was launched in 2010 through the creation of the non-profit organization and with a $2.9 million Energy Efficiency and Conservation Block (EECBG) grant from the U.S. Department of Energy (DOE). SELF has its main office and headquarters in St. Lucie County, in the region known as the Treasure Coast in East-Central Florida. St. Lucie County received funding to create SELF as an independent non-profit institution, outside the control of local government. This was important for SELF to create its identity as an integral part of the business community and to help in its quest to become a Community Development Financial Institution (CDFI). This goal was accomplished in 2013, allowing SELF to focus on its mission to increase energy savings while serving markets that have struggled to find affordable financial assistance. These homeowners are most impacted by high energy costs. Energy costs are a disproportionate percentage of household expenses for low to moderate income (LMI) households. Electricity costs have been steadily rising in Florida by nearly 5% per year. Housing in LMI neighborhoods often includes older inefficient structures that further exacerbate the problem. Despite the many available clean energy solutions, most LMI property owners do not have the disposable income or equity in their homes necessary to afford the high upfront cost

  15. Production circulator fabrication and testing for core flow test loop. Final report, Phase III

    Energy Technology Data Exchange (ETDEWEB)

    1981-05-01

    The performance testing of two production helium circulators utilizing gas film lubrication is described. These two centrifugal-type circulators plus an identical circulator prototype will be arranged in series to provide the helium flow requirements for the Core Flow Test Loop which is part of the Gas-Cooled Fast Breeder Reactor Program (GCFR) at the Oak Ridge National Laboratory. This report presents the results of the Phase III performance and supplemental tests, which were carried out by MTI during the period of December 18, 1980 through March 19, 1981. Specific test procedures are outlined and described, as are individual tests for measuring the performance of the circulators. Test data and run descriptions are presented.

  16. Production circulator fabrication and testing for core flow test loop. Final report, Phase III

    International Nuclear Information System (INIS)

    1981-05-01

    The performance testing of two production helium circulators utilizing gas film lubrication is described. These two centrifugal-type circulators plus an identical circulator prototype will be arranged in series to provide the helium flow requirements for the Core Flow Test Loop which is part of the Gas-Cooled Fast Breeder Reactor Program (GCFR) at the Oak Ridge National Laboratory. This report presents the results of the Phase III performance and supplemental tests, which were carried out by MTI during the period of December 18, 1980 through March 19, 1981. Specific test procedures are outlined and described, as are individual tests for measuring the performance of the circulators. Test data and run descriptions are presented

  17. The High Level Vibration Test Program

    International Nuclear Information System (INIS)

    Hofmayer, C.H.; Curreri, J.R.; Park, Y.J.; Kato, W.Y.; Kawakami, S.

    1989-01-01

    As part of cooperative agreements between the United States and Japan, tests have been performed on the seismic vibration table at the Tadotsu Engineering Laboratory of Nuclear Power Engineering Test Center (NUPEC) in Japan. The objective of the test program was to use the NUPEC vibration table to drive large diameter nuclear power piping to substantial plastic strain with an earthquake excitation and to compare the results with state-of-the-art analysis of the problem. The test model was designed by modifying the 1/2.5 scale model of the PWR primary coolant loop. Elastic and inelastic seismic response behavior of the test model was measured in a number of test runs with an increasing excitation input level up to the limit of the vibration table. In the maximum input condition, large dynamic plastic strains were obtained in the piping. Crack initiation was detected following the second maximum excitation run. The test model was subjected to a maximum acceleration well beyond what nuclear power plants are designed to withstand. This paper describes the overall plan, input motion development, test procedure, test results and comparisons with pre-test analysis. 4 refs., 16 figs., 2 tabs

  18. The High Level Vibration Test program

    International Nuclear Information System (INIS)

    Hofmayer, C.H.; Curreri, J.R.; Park, Y.J.; Kato, W.Y.; Kawakami, S.

    1990-01-01

    As part of cooperative agreements between the United States and Japan, tests have been performed on the seismic vibration table at the Tadotsu Engineering Laboratory of Nuclear Power Engineering Test Center (NUPEC) in Japan. The objective of the test program was to use the NUPEC vibration table to drive large diameter nuclear power piping to substantial plastic strain with an earthquake excitation and to compare the results with state-of-the-art analysis of the problem. The test model was designed by modifying the 1/2.5 scale model of the pressurized water reactor primary coolant loop. Elastic and inelastic seismic response behavior of the test model was measured in a number of test runs with an increasing excitation input level up to the limit of the vibration table. In the maximum input condition, large dynamic plastic strains were obtained in the piping. Crack initiation was detected following the second maximum excitation run. The test model was subjected to a maximum acceleration well beyond what nuclear power plants are designed to withstand. This paper describes the overall plan, input motion development, test procedure, test results and comparisons with pre-test analysis

  19. 1/3-scale model testing program

    International Nuclear Information System (INIS)

    Yoshimura, H.R.; Attaway, S.W.; Bronowski, D.R.; Uncapher, W.L.; Huerta, M.; Abbott, D.G.

    1989-01-01

    This paper describes the drop testing of a one-third scale model transport cask system. Two casks were supplied by Transnuclear, Inc. (TN) to demonstrate dual purpose shipping/storage casks. These casks will be used to ship spent fuel from DOEs West Valley demonstration project in New York to the Idaho National Engineering Laboratory (INEL) for long term spent fuel dry storage demonstration. As part of the certification process, one-third scale model tests were performed to obtain experimental data. Two 9-m (30-ft) drop tests were conducted on a mass model of the cask body and scaled balsa and redwood filled impact limiters. In the first test, the cask system was tested in an end-on configuration. In the second test, the system was tested in a slap-down configuration where the axis of the cask was oriented at a 10 degree angle with the horizontal. Slap-down occurs for shallow angle drops where the primary impact at one end of the cask is followed by a secondary impact at the other end. The objectives of the testing program were to (1) obtain deceleration and displacement information for the cask and impact limiter system, (2) obtain dynamic force-displacement data for the impact limiters, (3) verify the integrity of the impact limiter retention system, and (4) examine the crush behavior of the limiters. This paper describes both test results in terms of measured deceleration, post test deformation measurements, and the general structural response of the system

  20. Highly Insulating Windows Volume Purchase Program Final Report

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-04-01

    This report documents the development, execution outcomes and lessons learned of the Highly Insulating Windows Volume Purchase (WVP) Program carried out over a three-year period from 2009 through 2012. The primary goals of the program were met: 1) reduce the incremental cost of highly insulating windows compared to ENERGY STAR windows; and 2) raise the public and potential buyers’ awareness of highly insulating windows and their benefits. A key outcome of the program is that the 2013 ENERGY STAR Most Efficient criteria for primary residential windows were adopted from the technical specifications set forth in the WVP program.

  1. 76 FR 18624 - Research, Technical Assistance and Training Programs: Notice of Final Circular

    Science.gov (United States)

    2011-04-04

    ... to FTA Circular 6100.1D, Research and Technical Assistance Training Program: Application Instructions... DEPARTMENT OF TRANSPORTATION Federal Transit Administration Research, Technical Assistance and Training Programs: Notice of Final Circular AGENCY: Federal Transit Administration (FTA), DOT. ACTION...

  2. Renewable Fuel Pathways II Final Rule to Identify Additional Fuel Pathways under Renewable Fuel Standard Program

    Science.gov (United States)

    This final rule describes EPA’s evaluation of biofuels derived from biogas fuel pathways under the RFS program and other minor amendments related to survey requirements associated with ULSD program and misfueling mitigation regulations for E15.

  3. Plutonium Immobilization Program cold pour tests

    International Nuclear Information System (INIS)

    Hovis, G.L.; Stokes, M.W.; Smith, M.E.; Wong, J.W.

    1999-01-01

    The Plutonium Immobilization Program (PIP) is a joint venture between the Savannah River Site, Lawrence Livermore National Laboratory, Argonne National Laboratory, and Pacific Northwest National Laboratory to carry out the disposition of excess weapons-grade plutonium. This program uses the can-in-canister (CIC) approach. CIC involves encapsulating plutonium in ceramic forms (or pucks), placing the pucks in sealed stainless steel cans, placing the cans in long cylindrical magazines, latching the magazines to racks inside Defense Waste Processing Facility (DWPF) canisters, and filling the DWPF canisters with high-level waste glass. This process puts the plutonium in a stable form and makes it attractive for reuse. At present, the DWPF pours glass into empty canisters. In the CIC approach, the addition of a stainless steel rack, magazines, cans, and ceramic pucks to the canisters introduces a new set of design and operational challenges: All of the hardware installed in the canisters must maintain structural integrity at elevated (molten-glass) temperatures. This suggests that a robust design is needed. However, the amount of material added to the DWPF canister must be minimized to prevent premature glass cooling and excessive voiding caused by a large internal thermal mass. High metal temperatures, minimizing thermal mass, and glass flow paths are examples of the types of technical considerations of the equipment design process. To determine the effectiveness of the design in terms of structural integrity and glass-flow characteristics, full-scale testing will be conducted. A cold (nonradioactive) pour test program is planned to assist in the development and verification of a baseline design for the immobilization canister to be used in the PIP process. The baseline design resulting from the cold pour test program and CIC equipment development program will provide input to Title 1 design for second-stage immobilization. The cold pour tests will be conducted in two

  4. Nevada Test Site Radiation Protection Program

    Energy Technology Data Exchange (ETDEWEB)

    Radiological Control Managers' Council, Nevada Test Site

    2007-08-09

    Title 10 Code of Federal Regulations (CFR) 835, 'Occupational Radiation Protection', establishes radiation protection standards, limits, and program requirements for protecting individuals from ionizing radiation resulting from the conduct of U.S. Department of Energy (DOE) activities. 10 CFR 835.101(a) mandates that DOE activities be conducted in compliance with a documented Radiation Protection Program (RPP) as approved by DOE. This document promulgates the RPP for the Nevada Test Site (NTS), related (onsite or offsite) DOE National Nuclear Security Administration Nevada Site Office (NNSA/NSO) operations, and environmental restoration offsite projects.

  5. Program grants for black lung clinics--PHS. Final rule.

    Science.gov (United States)

    1985-02-27

    The Public Health Service hereby revises the regulations governing the grants program for black lung clinics established under section 427(a) of the Federal Mine Safety and Health Act of 1977. The revision is in keeping with the Department of Health and Human Services' desire to remove as many programmatic burdens and restrictions from grantees as possible, while maintaining program integrity.

  6. Group Use and Other Aspects of Programmed Instruction. Final Report.

    Science.gov (United States)

    Crist, Robert L.

    The use of group approval as a social reinforcer and related methods in group presentation of programed instruction were investigated in a series of studies. The efficacy of programed instructional materials is frequently limited by their inability to command and maintain adequate attention and motivation. To consider social reinforcement effects…

  7. Camp Verde Adult Reading Program. Final Performance Report.

    Science.gov (United States)

    Maynard, David A.

    This document begins with a four-page performance report describing how the Camp Verde Adult Reading Program site was relocated to the Community Center Complex, and the Town Council contracted directly with the Friends of the Camp Verde Library to provide for the requirements of the program. The U.S. Department of Education grant allowed the…

  8. Final report for the Pre-Freshman Enrichment Program (PREP)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    This project reflected cooperation across the disciplines in the physical sciences, engineering, mathematics and computer science. The University of the Pacific served as the center for this pre-college program. The idea was to use this link as a pilot program.

  9. Hood River Production Program Review, Final Report 1991-2001.

    Energy Technology Data Exchange (ETDEWEB)

    Underwood, Keith; Chapman, Colin; Ackerman, Nicklaus

    2003-12-01

    This document provides a comprehensive review of Bonneville Power Administration (BPA) funded activities within the Hood River Basin from 1991 to 2001. These activities, known as the Hood River Production Program (HRPP), are intended to mitigate for fish losses related to operation of federal dams in the Columbia River Basin, and to contribute to recovery of endangered and/or threatened salmon and steelhead, as directed by Nation Oceanic and Atmospheric Administration - Fisheries (NOAA Fisheries). The Environmental Impact Statement (EIS) for the HRPP, which authorized BPA to fund salmon and steelhead enhancement activities in the Hood River Basin, was completed in 1996 (BPA 1996). The EIS specified seven years of monitoring and evaluation (1996-2002) after program implementation to determine if program actions needed modification to meet program objectives. The EIS also called for a program review after 2002, that review is reported here.

  10. MFTF-B PACE tests and final cost report

    International Nuclear Information System (INIS)

    Krause, K.H.; Kozman, T.A.; Smith, J.L.; Horan, R.J.

    1986-10-01

    The Mirror Fusion Test Facility (MFTF-B) construction project was successfully completed in February 1986, with the conclusion of the Plant and Capital Equipment (PACE) Tests. This series of tests, starting in September 1985 and running through February 1986, demonstrated the overall machine capabilities and special facilities accomplishments for the Mirror Fusion Test Facility Project

  11. 76 FR 6594 - Florida: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2011-02-07

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... of the changes to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA... and State Programs Section, RCRA Programs and Materials Management Branch, RCRA Division, U.S...

  12. 77 FR 60963 - Tennessee: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-10-05

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... of the changes to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA... Johnson, Permits and State Programs Section, RCRA Programs and Materials Management Branch, RCRA Division...

  13. PG&E WaveConnect Program Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Brendan P. Dooher; Edward Cheslak; Robert Booth; Doug Davy; Annette Faraglia; Ian Caliendo; Gina Morimoto; Douglas Herman

    2011-12-01

    The PG&E WaveConnect project was intended to demonstrate the technical and economic viability of wave power in the open ocean adjacent to PG&E's service territory. WaveConnect was conceived as a multi-stage development process leading to long-term megawatt-scale wave power production. The first-stage tasks consisted of site selection, permitting, pilot plant design, and assessment of technology and commercial readiness. The second stage would have included development of infrastructure, undersea cabling, and deployment of wave energy conversion devices (WECs). In the third stage, the most promising WEC devices would have been deployed in larger quantities and connected to the grid. This report documents the findings of Stage One. Site Selection: After studying the wave energy potential, grid interconnection and other project infrastructure along the California coast, PG&E selected two sites: one near Eureka, called the Humboldt WaveConnect (HWC) project, and another near Vandenberg Air Force Base, called the Central Coast WaveConnect project (CCWC). Permitting: FERC issued PG&E preliminary permits for HWC in 2008 and for CCWC in 2010. PG&E chose to use FERC's Pilot Project Licensing Process, which was intended to streamline licensing to allow relatively quick and easy installation, operation, and environmental testing for pilot projects. Permitting, however, proved to be complicated, time-consuming and expensive, mainly because of the uncertain impacts of WEC devices. PG&E learned that even under the PPLP the project would still require a full analysis under CEQA, including an EIR, as well as Monitoring and Adaptive Management Programs and other requirements that had significant cost and scheduling implications. A majority of efforts were expended on permitting activities. Pilot Plant Design: PG&E prepared a conceptual design for a 5-MW pilot test facility at the Humboldt site, which consisted of an off-shore deployment area where WECs of different

  14. Effectiveness of Oregon's teen licensing program : final report.

    Science.gov (United States)

    2008-06-01

    Significant changes in Oregons teen licensing laws went into effect on March 1, 2000. The new laws expanded the provisional driving license program which had been in effect since October 1989 and established a graduated driver licensing (GDL) prog...

  15. CERT tribal internship program. Final intern report: Karen Sandoval, 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    The purpose of the project was to: create a working relationship between CERT and Colorado State University (CSU); involve and create relationships among individuals and departments at CSU; empower Native communities to run their own affairs; establish programs for the benefit of Tribes; and create Native American Program Development Office at CSU. The intern lists the following as the project results: revised a Native American Program Development document; confirmation from 45 departments across campus for Summit attendance [Tribal Human Resource Development Summit]; created initial invitee list from CSU departments and colleges; and informed CERT and CSU staff of results. Much of the response from the campus community has been positive and enthusiastic. They are ready to develop new Native American programs on campus, but need the awareness of what they can do to be respectful of Tribal needs.

  16. A pavement management research program for Oregon highways : final report.

    Science.gov (United States)

    1989-12-01

    An extensive program was developed to measure pavement deflection skid resistance, and rideability throughout Oregon. The data from those "objective" measures were then evaluated for correlations with observed pavement distress and traffic factors. :...

  17. Health Education Assistance Loan (HEAL) Program. Final rule.

    Science.gov (United States)

    2017-11-15

    On July 1, 2014, the HEAL Program was transferred from the U.S. Department of Health and Human Services (HHS) to the U.S. Department of Education (the Department). To reflect this transfer and to facilitate the servicing of all HEAL loans that are currently held by the Department, the Secretary adds the HEAL Program regulations to the Department's chapter in the Code of Federal Regulations (CFR).

  18. 78 FR 70255 - West Virginia: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-11-25

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R03-RCRA-2013-0571; FRL-9903-07-Region 3] West Virginia: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY... final authorization of revisions to its hazardous waste program under the Resource Conservation and...

  19. 77 FR 15966 - Ohio: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2012-03-19

    ... Hazardous Waste Management Program Revision AGENCY: Environmental Protection Agency (EPA). ACTION: Final..., 1989 (54 FR 27170) to implement the RCRA hazardous waste management program. We granted authorization... Combustors; Final Rule, Checklist 198, February 14, 2002 (67 FR 6968); Hazardous Waste Management System...

  20. Final environmental statement, Liquid Metal Fast Breeder Reactor Program. Volume 1

    International Nuclear Information System (INIS)

    1975-12-01

    Information is presented under the following section headings: LMFBR program options and their compatibility with the major issues affecting commercial development, Proposed Final Environmental Statement for the LMFBR program, December 1974, WASH-1535, supplemental material, and material relating to Proposed Final Environmental Statement review

  1. 78 FR 68161 - Greenhouse Gas Reporting Program: Final Amendments and Confidentiality Determinations for...

    Science.gov (United States)

    2013-11-13

    ... 98 Greenhouse Gas Reporting Program: Final Amendments and Confidentiality Determinations for...-HQ-OAR-2011-0028; FRL-9845-6] RIN 2060-AR61 Greenhouse Gas Reporting Program: Final Amendments and... monitoring methodologies for electronics manufacturers covered by the Greenhouse Gas Reporting Rule. These...

  2. Achilles tests finally nail PWR fuel clad ballooning fears

    International Nuclear Information System (INIS)

    Dore, P.; McMinn, K.

    1992-01-01

    A conclusive series of experiments carried out by AEA Reactor Services at its Achilles rig in the UK has finally allayed fears that fuel clad ballooning is a major safety problem for Sizewell B, Britain's first Pressurized Water Reactor. The experiments are described in this article. (author)

  3. African Social Studies Program-1, 1988-89. Final Report. A Master's Degree Program for African Social Studies Leaders.

    Science.gov (United States)

    Indiana Univ., Bloomington.

    This paper presents the final report on a project that brought African social studies education leaders to Indiana University (Bloomington) to take part in a Master's Degree program. The report contains a brief history of the program, a description of the program, a discussion of issues relating to acculturation, an evaluation, a list of…

  4. Buildings energy management program workshop design. Final report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-12-01

    This document describes activities undertaken by Honeywell's Energy Resources Center for design and development of the format, content, and materials that were used in conducting 129 one-day energy management workshops for specific commercial business audiences. The Building Energy Management Workshop Program was part of a National Workshop Program that was intended to increase awareness of energy-related issues and to encourage energy-conservation actions on the part of commercial and industrial sectors. The total effort included executive conferences for chief executive officers and other senior management personnel; industrial energy-conservation workshops directed at plant management and engineering personnel; vanpooling workshops designed to inform and encourage business in implementing a vanpooling program for employees; and the building energy-management workshops specifically developed for managers, owners, and operators of office and retail facilities, restaurants, and supermarkets. The total program spanned nearly two years and reached approximately 2,500 participants from all parts of the U.S. A detailed followup evaluation is still being conducted to determine the impact of this program in terms of conservation action undertaken by workshop participants.

  5. Final priority; Rehabilitation Services Administration--Assistive Technology Alternative Financing Program. Final priority.

    Science.gov (United States)

    2014-08-14

    The Assistant Secretary for Special Education and Rehabilitative Services announces a priority under the Assistive Technology Alternative Financing Program administered by the Rehabilitation Services Administration (RSA). The Assistant Secretary may use this priority for competitions in fiscal year (FY) 2014 and later years. This priority is designed to ensure that the Department funds high-quality assistive technology (AT) alternative financing programs (AFPs) that meet rigorous standards in order to enable individuals with disabilities to access and acquire assistive technology devices and services necessary to achieve education, community living, and employment goals.

  6. Overview and status of the SIMMER testing program

    International Nuclear Information System (INIS)

    Scott, J.H.

    1979-01-01

    Los Alamos Scientific Laboratory has undertaken an extensive experiment analysis program to test the results of SIMMER Liquid Metal Fast Breeder Reactor (LMFBR) accident calculations. Initially, we will test the postdisassembly work-energy partition problem. The SIMMER-calculated order-of-magnitude reduction of available kinetic energy following a severe hypothetical core-disruptive accident (HCDA) can be attributed to (1) purely fluid-dynamic effects; and (2) rate-controlled effects, such as phase transitions and heat transfer. We have chosen to test separately each class of mitigator. In this paper we review the experiments initially chosen for testing of each class of mitigator and report on the status of the analyses. We enumerate several problems in SIMMER that experiment analysis has disclosed. Finally, needs for future experiments are discussed

  7. Family Violence Prevention and Services Programs. Final rule.

    Science.gov (United States)

    2016-11-02

    This rule will better prevent and protect survivors of family violence, domestic violence, and dating violence, by clarifying that all survivors must have access to services and programs funded under the Family Violence Prevention and Services Act. More specifically, the rule enhances accessibility and non-discrimination provisions, clarifies confidentiality rules, promotes coordination among community-based organizations, State Domestic Violence Coalitions, States, and Tribes, as well as incorporates new discretionary grant programs. Furthermore, the rule updates existing regulations to reflect statutory changes made to the Family Violence Prevention and Services Act, and updates procedures for soliciting and awarding grants. The rule also increases clarity and reduces potential confusion over statutory and regulatory standards. The rule codifies standards already used by the program in the Funding Opportunity Announcements and awards, in technical assistance, in reporting requirements, and in sub-regulatory guidance.

  8. SWEEP - Save Water and Energy Education Program; FINAL

    International Nuclear Information System (INIS)

    Sullivan, Gregory P; Elliott, Douglas B; Hillman, Tim C; Hadley, Adam; Ledbetter, Marc R; Payson, David R

    2001-01-01

    The objective of this study was to develop, monitor, analyze, and report on an integrated resource-conservation program highlighting efficient residential appliances and fixtures. The sites of study were 50 homes in two water-constrained communities located in Oregon. The program was designed to maximize water savings to these communities and to serve as a model for other communities seeking an integrated approach to energy and water resource efficiency. The program included the installation and in-place evaluation of energy- and water-efficient devices including the following: horizontal axis clothes washers (and the matching clothes dryers), resource-efficient dishwashers, an innovative dual flush low-flow toilet, low-flow showerheads, and faucet aerators. The significance of this activity lies in its integrated approach and unique metering evaluation of individual end-use, aggregated residential total use, and system-wide energy and water benefits

  9. Industrial cogeneration optimization program. Final report, September 1979

    Energy Technology Data Exchange (ETDEWEB)

    Davis, Jerry; McWhinney, Jr., Robert T.

    1980-01-01

    This study program is part of the DOE Integrated Industry Cogeneration Program to optimize, evaluate, and demonstrate cogeneration systems, with direct participation of the industries most affected. One objective is to characterize five major energy-intensive industries with respect to their energy-use profiles. The industries are: petroleum refining and related industries, textile mill products, paper and allied products, chemicals and allied products, and food and kindred products. Another objective is to select optimum cogeneration systems for site-specific reference case plants in terms of maximum energy savings subject to given return on investment hurdle rates. Analyses were made that define the range of optimal cogeneration systems for each reference-case plant considering technology applicability, economic factors, and energy savings by type of fuel. This study also provides guidance to other parts of the program through information developed with regard to component development requirements, institutional and regulatory barriers, as well as fuel use and environmental considerations. (MCW)

  10. Hawaii alternative fuels utilization program. Phase 3, final report

    Energy Technology Data Exchange (ETDEWEB)

    Kinoshita, C.M.; Staackmann, M.

    1996-08-01

    The Hawaii Alternative Fuels Utilization Program originated as a five-year grant awarded by the US Department of Energy (USDOE) to the Hawaii Natural Energy Institute (HNEI) of the University of Hawaii at Manoa. The overall program included research and demonstration efforts aimed at encouraging and sustaining the use of alternative (i.e., substitutes for gasoline and diesel) ground transportation fuels in Hawaii. Originally, research aimed at overcoming technical impediments to the widespread adoption of alternative fuels was an important facet of this program. Demonstration activities centered on the use of methanol-based fuels in alternative fuel vehicles (AFVs). In the present phase, operations were expanded to include flexible fuel vehicles (FFVs) which can operate on M85 or regular unleaded gasoline or any combination of these two fuels. Additional demonstration work was accomplished in attempting to involve other elements of Hawaii in the promotion and use of alcohol fuels for ground transportation in Hawaii.

  11. Program and Abstracts, Boron Americas IX Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Feakes, Debra A.

    2006-08-09

    The Scientific and Technical Information (STI) submitted includes the final report and a collection of abstracts for the Ninth Boron in the Americas Conference which was held May 19-22, 2004, in San Marcos, Texas. The topics covered in the abstracts include: Application in Medicine, Application in Organic Synthesis and Catalysis, Boranes and Carboranes, Materials and Polymers, Metallaboranes and Metallacarboranes, Organoboron Compounds, Synthesis and Catalysis, and Theoretical Studies. Attendees represented researchers from government, industry, and academia.

  12. Accelerated Leach Test(s) Program. Annual report

    International Nuclear Information System (INIS)

    Dougherty, D.R.; Fuhrmann, M.; Colombo, P.

    1985-09-01

    This report summarizes the work performed for the Accelerated Leach Test(s) Program at Brookhaven National Laboratory in Fiscal Year 1985 under the sponsorship of the US Department of Energy's Low-Level Waste Management Program (LLWMP). Programmatic activities were concentrated in three areas, as listed and described in the following paragraphs. (1) A literature survey of reported leaching mechanisms, available mathematical models and factors that affect leaching of LLW forms has been compiled. Mechanisms which have been identified include diffusion, dissolution, ion exchange, corrosion and surface effects. Available mathematical models are based on diffusion as the predominant mechanism. Although numerous factors that affect leaching have been identified, they have been conveniently categorized as factors related to the entire leaching system, to the leachant or to the waste form. A report has been published on the results of this literature survey. (2) A computerized data base of LLW leaching data and mathematical models is being developed. The data are being used for model evaluation by curve fitting and statistical analysis according to standard procedures of statistical quality control. (3) Long-term tests on portland cement, bitumen and vinyl ester-styrene (VES) polymer waste forms are underway which are designed to identify and evaluate factors that accelerate leaching without changing the mechanisms. Results on the effect of temperature on leachability indicate that the leach rates of cement and VES waste forms increase with increasing temperature, whereas, the leach rate of bitumen is little affected

  13. The $2000 Electric Powertrain Option-1 Program. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-06-01

    This report describes the tasks accomplished as part of Northrop Grumman's TRP $2000 Electric Powertrain Option-1 program. Northrop Grumman has strived to achieve technology advances and development considered as high priority to the success of future electric vehicles. Northrop Grumman has achieved the intent of the program by taking several steps toward reducing the cost of the electric vehicle powertrain, demonstrating technologies in the form of hardware and introducing enhancements into production that are consistent with the needs of the market.

  14. Spent fuel sabotage aerosol test program :FY 2005-06 testing and aerosol data summary

    International Nuclear Information System (INIS)

    Gregson, Michael Warren; Brockmann, John E.; Nolte, O.; Loiseau, O.; Koch, W.; Molecke, Martin Alan; Autrusson, Bruno; Pretzsch, Gunter Guido; Billone, M. C.; Lucero, Daniel A.; Burtseva, T.; Brucher, W; Steyskal, Michele D.

    2006-01-01

    This multinational, multi-phase spent fuel sabotage test program is quantifying the aerosol particles produced when the products of a high energy density device (HEDD) interact with and explosively particulate test rodlets that contain pellets of either surrogate materials or actual spent fuel. This program has been underway for several years. This program provides source-term data that are relevant to some sabotage scenarios in relation to spent fuel transport and storage casks, and associated risk assessments. This document focuses on an updated description of the test program and test components for all work and plans made, or revised, primarily during FY 2005 and about the first two-thirds of FY 2006. It also serves as a program status report as of the end of May 2006. We provide details on the significant findings on aerosol results and observations from the recently completed Phase 2 surrogate material tests using cerium oxide ceramic pellets in test rodlets plus non-radioactive fission product dopants. Results include: respirable fractions produced; amounts, nuclide content, and produced particle size distributions and morphology; status on determination of the spent fuel ratio, SFR (the ratio of respirable particles from real spent fuel/respirables from surrogate spent fuel, measured under closely matched test conditions, in a contained test chamber); and, measurements of enhanced volatile fission product species sorption onto respirable particles. We discuss progress and results for the first three, recently performed Phase 3 tests using depleted uranium oxide, DUO 2 , test rodlets. We will also review the status of preparations and the final Phase 4 tests in this program, using short rodlets containing actual spent fuel from U.S. PWR reactors, with both high- and lower-burnup fuel. These data plus testing results and design are tailored to support and guide, follow-on computer modeling of aerosol dispersal hazards and radiological consequence assessments

  15. How My Program Passed the Turing Test

    Science.gov (United States)

    Humphrys, Mark

    In 1989, the author put an ELIZA-like chatbot on the Internet. The conversations this program had can be seen - depending on how one defines the rules (and how seriously one takes the idea of the test itself) - as a passing of the Turing Test. This is the first time this event has been properly written. This chatbot succeeded due to profanity, relentless aggression, prurient queries about the user, and implying that they were a liar when they responded. The element of surprise was also crucial. Most chatbots exist in an environment where people expectto find some bots among the humans. Not this one. What was also novel was the onlineelement. This was certainly one of the first AI programs online. It seems to have been the first (a) AI real-time chat program, which (b) had the element of surprise, and (c) was on the Internet. We conclude with some speculation that the future of all of AI is on the Internet, and a description of the "World- Wide-Mind" project that aims to bring this about.

  16. College of Lake County National Workplace Literacy Program. Final Report.

    Science.gov (United States)

    Gee, Mary Kay

    The College of Lake County's 3-year National Workplace Literacy Program (1994-1997) contributed to economic development by meeting companies' changing educational and production needs as they fluctuated and met new challenges for global marketing and improvement. It assessed 883 employees at 8 business sites with customized assessment tools and…

  17. Hawaii Integrated Biofuels Research Program: Final Subcontract Report, Phase III

    Energy Technology Data Exchange (ETDEWEB)

    1992-05-01

    This report is a compilation of studies done to develop an integrated set of strategies for the production of energy from renewable resources in Hawaii. Because of the close coordination between this program and other ongoing DOE research, the work will have broad-based applicability to the entire United States.

  18. Implementing an Indigenous Community Education Program: A Final Report.

    Science.gov (United States)

    Bialek, Hilton; Nabokov, Peter

    Four rural communities in northern Maine were the setting for a pilot program in Indian adult education that featured a new kind of instructional model. Developed by the Human Resources Research Organization (HumRRO), it featured peer instruction, strict performance orientation, and insistance on mastery of certain skills. A HumRRO representative…

  19. Seismic safety margins research program. Phase I final report - Overview

    International Nuclear Information System (INIS)

    Smith, P.D.; Dong, R.G.; Bernreuter, D.L.; Bohn, M.P.; Chuang, T.Y.; Cummings, G.E.; Johnson, J.J.; Mensing, R.W.; Wells, J.E.

    1981-04-01

    The Seismic Safety Margins Research Program (SSMRP) is a multiyear, multiphase program whose overall objective is to develop improved methods for seismic safety assessments of nuclear power plants, using a probabilistic computational procedure. The program is being carried out at the Lawrence Livermore National Laboratory and is sponsored by the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. Phase I of the SSMRP was successfully completed in January 1981: A probabilistic computational procedure for the seismic risk assessment of nuclear power plants has been developed and demonstrated. The methodology is implemented by three computer programs: HAZARD, which assesses the seismic hazard at a given site, SMACS, which computes in-structure and subsystem seismic responses, and SEISIM, which calculates system failure probabilities and radioactive release probabilities, given (1) the response results of SMACS, (2) a set of event trees, (3) a family of fault trees, (4) a set of structural and component fragility descriptions, and (5) a curve describing the local seismic hazard. The practicality of this methodology was demonstrated by computing preliminary release probabilities for Unit 1 of the Zion Nuclear Power Plant north of Chicago, Illinois. Studies have begun aimed at quantifying the sources of uncertainty in these computations. Numerous side studies were undertaken to examine modeling alternatives, sources of error, and available analysis techniques. Extensive sets of data were amassed and evaluated as part of projects to establish seismic input parameters and to produce the fragility curves. (author)

  20. Final Report Inspection of Aged/Degraded Containments Program.

    Energy Technology Data Exchange (ETDEWEB)

    Naus, Dan J [ORNL; Ellingwood, B R [Georgia Institute of Technology; Oland, C Barry [ORNL

    2005-09-01

    The Inspection of Aged/Degraded Containments Program had primary objectives of (1) understanding the significant factors relating corrosion occurrence, efficacy of inspection, and structural capacity reduction of steel containments and liners of reinforced concrete containments; (2) providing the United States Nuclear Regulatory Commission (USNRC) reviewers a means of establishing current structural capacity margins or estimating future residual structural capacity margins for steel containments, and concrete containments as limited by liner integrity; (3) providing recommendations, as appropriate, on information to be requested of licensees for guidance that could be utilized by USNRC reviewers in assessing the seriousness of reported incidences of containment degradation; and (4) providing technical assistance to the USNRC (as requested) related to concrete technology. Primary program accomplishments have included development of a degradation assessment methodology; reviews of techniques and methods for inspection and repair of containment metallic pressure boundaries; evaluation of high-frequency acoustic imaging, magnetostrictive sensor, electromagnetic acoustic transducer, and multimode guided plate wave technologies for inspection of inaccessible regions of containment metallic pressure boundaries; development of a continuum damage mechanics-based approach for structural deterioration; establishment of a methodology for reliability-based condition assessments of steel containments and liners; and fragility assessments of steel containments with localized corrosion. In addition, data and information assembled under this program has been transferred to the technical community through review meetings and briefings, national and international conference participation, technical committee involvement, and publications of reports and journal articles. Appendix A provides a listing of program reports, papers, and publications; and Appendix B contains a listing of

  1. Supercritical water oxidation data acquisition testing. Final report, Volume I

    International Nuclear Information System (INIS)

    1996-11-01

    This report discusses the phase one testing of a data acquisition system for a supercritical water waste oxidation system. The system is designed to destroy a wide range of organic materials in mixed wastes. The design and testing of the MODAR Oxidizer is discussed. An analysis of the optimized runs is included

  2. Accelerated corrosion test for metal drainage pipes : final report.

    Science.gov (United States)

    1987-06-01

    This study represents an attempt to develop an accelerated test which would assist the highway engineer in evaluating the usefulness of a new type of coated steel culvert. The test method was to be short in duration (in the order of days), and the re...

  3. Final Environmental Impact Statement (EIS) for the Space Nuclear Thermal Propulsion (SNTP) program

    Science.gov (United States)

    1991-09-01

    A program has been proposed to develop the technology and demonstrate the feasibility of a high-temperature particle bed reactor (PBR) propulsion system to be used to power an advanced second stage nuclear rocket engine. The purpose of this Final Environmental Impact Statement (FEIS) is to assess the potential environmental impacts of component development and testing, construction of ground test facilities, and ground testing. Major issues and goals of the program include the achievement and control of predicted nuclear power levels; the development of materials that can withstand the extremely high operating temperatures and hydrogen flow environments; and the reliable control of cryogenic hydrogen and hot gaseous hydrogen propellant. The testing process is designed to minimize radiation exposure to the environment. Environmental impact and mitigation planning are included for the following areas of concern: (1) Population and economy; (2) Land use and infrastructure; (3) Noise; (4) Cultural resources; (5) Safety (non-nuclear); (6) Waste; (7) Topography; (8) Geology; (9) Seismic activity; (10) Water resources; (11) Meteorology/Air quality; (12) Biological resources; (13) Radiological normal operations; (14) Radiological accidents; (15) Soils; and (16) Wildlife habitats.

  4. Pretreatment Engineering Platform Phase 1 Final Test Report

    International Nuclear Information System (INIS)

    Kurath, Dean E.; Hanson, Brady D.; Minette, Michael J.; Baldwin, David L.; Rapko, Brian M.; Mahoney, Lenna A.; Schonewill, Philip P.; Daniel, Richard C.; Eslinger, Paul W.; Huckaby, James L.; Billing, Justin M.; Sundar, Parameshwaran S.; Josephson, Gary B.; Toth, James J.; Yokuda, Satoru T.; Baer, Ellen B.K.; Barnes, Steven M.; Golovich, Elizabeth C.; Rassat, Scot D.; Brown, Christopher F.; Geeting, John G.H.; Sevigny, Gary J.; Casella, Amanda J.; Bontha, Jagannadha R.; Aaberg, Rosanne L.; Aker, Pamela M.; Guzman-Leong, Consuelo E.; Kimura, Marcia L.; Sundaram, S.K.; Pires, Richard P.; Wells, Beric E.; Bredt, Ofelia P.

    2009-01-01

    Pacific Northwest National Laboratory (PNNL) was tasked by Bechtel National Inc. (BNI) on the River Protection Project, Hanford Tank Waste Treatment and Immobilization Plant (RPP-WTP) project to conduct testing to demonstrate the performance of the WTP Pretreatment Facility (PTF) leaching and ultrafiltration processes at an engineering-scale. In addition to the demonstration, the testing was to address specific technical issues identified in Issue Response Plan for Implementation of External Flowsheet Review Team (EFRT) Recommendations - M12, Undemonstrated Leaching Processes. Testing was conducted in a 1/4.5-scale mock-up of the PTF ultrafiltration system, the Pretreatment Engineering Platform (PEP). Parallel laboratory testing was conducted in various PNNL laboratories to allow direct comparison of process performance at an engineering-scale and a laboratory-scale. This report presents and discusses the results of those tests.

  5. Pretreatment Engineering Platform Phase 1 Final Test Report

    Energy Technology Data Exchange (ETDEWEB)

    Kurath, Dean E.; Hanson, Brady D.; Minette, Michael J.; Baldwin, David L.; Rapko, Brian M.; Mahoney, Lenna A.; Schonewill, Philip P.; Daniel, Richard C.; Eslinger, Paul W.; Huckaby, James L.; Billing, Justin M.; Sundar, Parameshwaran S.; Josephson, Gary B.; Toth, James J.; Yokuda, Satoru T.; Baer, Ellen BK; Barnes, Steven M.; Golovich, Elizabeth C.; Rassat, Scot D.; Brown, Christopher F.; Geeting, John GH; Sevigny, Gary J.; Casella, Amanda J.; Bontha, Jagannadha R.; Aaberg, Rosanne L.; Aker, Pamela M.; Guzman-Leong, Consuelo E.; Kimura, Marcia L.; Sundaram, S. K.; Pires, Richard P.; Wells, Beric E.; Bredt, Ofelia P.

    2009-12-23

    Pacific Northwest National Laboratory (PNNL) was tasked by Bechtel National Inc. (BNI) on the River Protection Project, Hanford Tank Waste Treatment and Immobilization Plant (RPP-WTP) project to conduct testing to demonstrate the performance of the WTP Pretreatment Facility (PTF) leaching and ultrafiltration processes at an engineering-scale. In addition to the demonstration, the testing was to address specific technical issues identified in Issue Response Plan for Implementation of External Flowsheet Review Team (EFRT) Recommendations - M12, Undemonstrated Leaching Processes.( ) Testing was conducted in a 1/4.5-scale mock-up of the PTF ultrafiltration system, the Pretreatment Engineering Platform (PEP). Parallel laboratory testing was conducted in various PNNL laboratories to allow direct comparison of process performance at an engineering-scale and a laboratory-scale. This report presents and discusses the results of those tests.

  6. Small Town Energy Program (STEP) Final Report revised

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, Charles (Chuck) T.

    2014-01-02

    University Park, Maryland (“UP”) is a small town of 2,540 residents, 919 homes, 2 churches, 1 school, 1 town hall, and 1 breakthrough community energy efficiency initiative: the Small Town Energy Program (“STEP”). STEP was developed with a mission to “create a model community energy transformation program that serves as a roadmap for other small towns across the U.S.” STEP first launched in January 2011 in UP and expanded in July 2012 to the neighboring communities of Hyattsville, Riverdale Park, and College Heights Estates, MD. STEP, which concluded in July 2013, was generously supported by a grant from the U.S. Department of Energy (DOE). The STEP model was designed for replication in other resource-constrained small towns similar to University Park - a sector largely neglected to date in federal and state energy efficiency programs. STEP provided a full suite of activities for replication, including: energy audits and retrofits for residential buildings, financial incentives, a community-based social marketing backbone and local community delivery partners. STEP also included the highly innovative use of an “Energy Coach” who worked one-on-one with clients throughout the program. Please see www.smalltownenergy.org for more information. In less than three years, STEP achieved the following results in University Park: • 30% of community households participated voluntarily in STEP; • 25% of homes received a Home Performance with ENERGY STAR assessment; • 16% of households made energy efficiency improvements to their home; • 64% of households proceeded with an upgrade after their assessment; • 9 Full Time Equivalent jobs were created or retained, and 39 contractors worked on STEP over the course of the project. Estimated Energy Savings - Program Totals kWh Electricity 204,407 Therms Natural Gas 24,800 Gallons of Oil 2,581 Total Estimated MMBTU Saved (Source Energy) 5,474 Total Estimated Annual Energy Cost Savings $61,343 STEP clients who

  7. Technical bases for the DWPF testing program

    International Nuclear Information System (INIS)

    Plodinec, M.J.

    1990-01-01

    The Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS) will be the first production facility in the United States for the immobilization of high-level nuclear waste. Production of DWPF canistered wasteforms will begin prior to repository licensing, so decisions on facility startup will have to be made before the final decisions on repository design are made. The Department of Energy's Office of Civilian Radioactive Waste Management (RW) has addressed this discrepancy by defining a Waste Acceptance Process. This process provides assurance that the borosilicate-glass wasteform, in a stainless-steel canister, produced by the DWPF will be acceptable for permanent storage in a federal repository. As part of this process, detailed technical specifications have been developed for the DWPF product. SRS has developed detailed strategies for demonstrating compliance with each of the Waste Acceptance Process specifications. An important part of the compliance is the testing which will be carried out in the DWPF. In this paper, the bases for each of the tests to be performed in the DWPF to establish compliance with the specifications are described, and the tests are detailed. The results of initial tests relating to characterization of sealed canisters are reported

  8. [Advanced accelerator R and D program]. Final report

    International Nuclear Information System (INIS)

    1997-01-01

    This proposal requests funding for a 3-year renewal of the DOE advanced accelerator R and D (AARD) program at Texas A and M University. The program to date has focused on the development of the gigatron, a compact high-efficiency microwave driver for future linear colliders. The author reports results and progress in that project, and plans to bring it to a milestone and conclusion by mid-1995. He proposes to initiate a second project, the development of a new technology for ultra-high field superconducting magnets for future hadron colliders. This project builds upon two magnet designs which he has introduced during the past year, which have the potential for a dramatic extension of the achievable field strength for both dipoles and quadrupoles

  9. Final Report: Center for Programming Models for Scalable Parallel Computing

    Energy Technology Data Exchange (ETDEWEB)

    Mellor-Crummey, John [William Marsh Rice University

    2011-09-13

    As part of the Center for Programming Models for Scalable Parallel Computing, Rice University collaborated with project partners in the design, development and deployment of language, compiler, and runtime support for parallel programming models to support application development for the “leadership-class” computer systems at DOE national laboratories. Work over the course of this project has focused on the design, implementation, and evaluation of a second-generation version of Coarray Fortran. Research and development efforts of the project have focused on the CAF 2.0 language, compiler, runtime system, and supporting infrastructure. This has involved working with the teams that provide infrastructure for CAF that we rely on, implementing new language and runtime features, producing an open source compiler that enabled us to evaluate our ideas, and evaluating our design and implementation through the use of benchmarks. The report details the research, development, findings, and conclusions from this work.

  10. Vocational Rehabilitation and Employment program--self-employment. Final rule.

    Science.gov (United States)

    2010-01-20

    This document amends the vocational rehabilitation and employment regulations of the Department of Veterans Affairs (VA) concerning self-employment for individuals with qualifying disabilities. We are making changes to conform VA's regulations for self-employment programs for veterans, and for servicemembers awaiting discharge, to statutory provisions, including provisions limiting eligibility for certain supplies, equipment, stock, and license fees to individuals with the most severe service-connected disabilities. We are also making related changes in VA's regulations affecting eligibility for such assistance for certain veterans' children with birth defects in self-employment programs. In addition, we are amending our regulations regarding the approval authority for self-employment plans to make certain requirements less restrictive and less burdensome, to remove a vague and overly broad requirement, to make changes to reflect longstanding VA policy, and to make nonsubstantive clarifying changes.

  11. New Mexico statewide geothermal energy program. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    Icerman, L.; Parker, S.K. (ed.)

    1988-04-01

    This report summarizes the results of geothermal energy resource assessment work conducted by the New Mexico Statewide Geothermal Energy Program during the period September 7, 1984, through February 29, 1988, under the sponsorship of the US Dept. of Energy and the State of New Mexico Research and Development Institute. The research program was administered by the New Mexico Research and Development Institute and was conducted by professional staff members at New Mexico State University and Lightning Dock Geothermal, Inc. The report is divided into four chapters, which correspond to the principal tasks delineated in the above grant. This work extends the knowledge of the geothermal energy resource base in southern New Mexico with the potential for commercial applications.

  12. Fatique Resistant, Energy Efficient Welding Program, Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Egland, Keith; Ludewig, Howard

    2006-05-25

    The program scope was to affect the heat input and the resultant weld bead geometry by synchronizing robotic weave cycles with desired pulsed waveform shapes to develop process parameters relationships and optimized pulsed gas metal arc welding processes for welding fatique-critical structures of steel, high strength steel, and aluminum. Quality would be addressed by developing intelligent methods of weld measurement that accurately predict weld bead geometry from process information. This program was severely underfunded, and eventually terminated. The scope was redirected to investigate tandem narrow groove welding of steel butt joints during the one year of partial funding. A torch was designed and configured to perform a design of experiments of steel butt weld joints that validated the feasability of the process. An initial cost model estimated a 60% cost savings over conventional groove welding by eliminating the joint preparation and reducing the weld volume needed.

  13. URSULA2 computer program. Volume 3. User's manual. Final report

    International Nuclear Information System (INIS)

    Singhal, A.K.

    1980-01-01

    This report is intended to provide documentation for the users of the URSULA2 code so that they can appreciate its important features such as: code structure, flow chart, grid notations, coding style, usage of secondary storage and its interconnection with the input preparation program (Reference H3201/4). Subroutines and subprograms have been divided into four functional groups. The functions of all subroutines have been explained with particular emphasis on the control subroutine (MAIN) and the data input subroutine (BLOCK DATA). Computations for the flow situations similar to the reference case can be performed simply by making alterations in BLOCK DATA. Separate guides for the preparation of input data and for the interpretation of program output have been provided. Furthermore, two appendices; one for the URSULA2 listing and the second for the glossary of FORTRAN variables, are included to make this report self-sufficient

  14. The NIRA computer program package (photonuclear data center). Final report

    International Nuclear Information System (INIS)

    Vander Molen, H.J.; Gerstenberg, H.M.

    1976-02-01

    The Photonuclear Data Center's NIRA library of programs, executable from mass storage on the National Bureau of Standard's central computer facility, is described. Detailed instructions are given (with examples) for the use of the library to analyze, evaluate, synthesize, and produce for publication camera-ready tabular and graphical presentations of digital photonuclear reaction cross-section data. NIRA is the acronym for Nuclear Information Research Associate

  15. TFE design package final report, TFE Verification Program

    International Nuclear Information System (INIS)

    1994-06-01

    The program objective is to demonstrate the technology readiness of a TFE suitable for use as the basic element in a thermionic reactor with electric power output in the 0.5 to 5.0 MW(e) range, and a full-power life of 7 years. A TFE for a megawatt class system is described. Only six cells are considered for simplicity; a megawatt class TFE would have many more cells, the exact number dependent on optimization trade studies

  16. Final Creech Air Force Base Capital Improvements Program Environmental Assessment

    Science.gov (United States)

    2013-11-01

    acts as a shell to softer, more vulnerable soils below. Lenses of caliche (sediment cemented together with sodium salts) and clay are also known to be...requirements. Contact Air Quality Program Manager YES Page 2 WATER QUALITY 99 CES/CEIEC, 652-2834 Any process that discharges to sanitary or industrial... Sanitary Wastewater Will the project result in the discharge of any sanitary wastewaters (e.g., wastewater from sinks, showers, toilets, etc)? A

  17. Multiyear Program Plan for the High Temperature Materials Laboratory; FINAL

    International Nuclear Information System (INIS)

    Arvid E. Pasto

    2000-01-01

    Recently, the U.S. Department of Energy's (DOE) Office of Heavy Vehicle Technologies (OHVT) prepared a Technology Roadmap describing the challenges facing development of higher fuel efficiency, less polluting sport utility vehicles, vans, and commercial trucks. Based on this roadmap, a multiyear program plan (MYPP) was also developed, in which approaches to solving the numerous challenges are enumerated. Additional planning has been performed by DOE and national laboratory staff, on approaches to solving the numerous challenges faced by heavy vehicle system improvements. Workshops and planning documents have been developed concerning advanced aerodynamics, frictional and other parasitic losses, and thermal management. Similarly, the Heavy Vehicle Propulsion Materials Program has developed its own multiyear program plan. The High Temperature Materials Laboratory, a major user facility sponsored by OHVT, has now developed its program plan, described herein. Information was gathered via participation in the development of OHVT's overall Technology Roadmap and MYPP, through personal contacts within the materials-user community, and from attendance at conferences and expositions. Major materials issues for the heavy vehicle industry currently center on trying to increase efficiency of (diesel) engines while at the same time reducing emissions (particularly NO(sub x) and particulates). These requirements dictate the use of increasingly stronger, higher-temperature capable and more corrosion-resistant materials of construction, as well as advanced catalysts, particulate traps, and other pollution-control devices. Exhaust gas recirculation (EGR) is a technique which will certainly be applied to diesel engines in the near future, and its use represents a formidable challenge, as will be described later. Energy-efficient, low cost materials processing methods and surface treatments to improve wear, fracture, and corrosion resistance are also required

  18. Final results of the Maryland WIC Food for Life Program.

    Science.gov (United States)

    Havas, Stephen; Anliker, Jean; Greenberg, Deborah; Block, Gladys; Block, Torin; Blik, Cheryl; Langenberg, Patricia; DiClemente, Carlo

    2003-11-01

    The few randomized community trials in middle-income populations that tried to modify multiple dietary risk factors for cancer only demonstrated small changes. This trial sought to decrease the percent of calories derived from fat and to increase fruit, vegetable, and fiber intake among low-income women served by the Special Supplemental Nutrition Program for Women, Infants, and Children (WIC) in Maryland. We conducted six-month intervention programs for 1055 women at ten WIC sites; 1011 women served as controls. Intervention participants were invited to five interactive nutrition sessions and were sent written materials. Controls received usual care. Women were surveyed at baseline, two months post intervention, and one year later. All analyses conducted used an intention-to-treat paradigm. Mean differences (intervention-control) in change from baseline were for percent calories from fat -1.62 +/- 0.33% (P fruits and vegetables 0.40 +/- 0.11 servings (P = 0.0003), and for fiber intake 1.01 +/- 0.31 grams (P = 0.001). These differences in change were related in a dose-response relationship to the number of sessions women attended and remained significant one year post-intervention for the first two outcomes. Multiple dietary improvements can be achieved in a low-income population with an effective, multi-faceted intervention program. The changes in this trial exceeded those in previous community trials conducted in higher SES populations.

  19. CERT tribal internship program. Final intern report: Maria Perez, 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    Historically, American Indian Tribes have lacked sufficient numbers of trained, technical personnel from their communities to serve their communities; tribal expertise in the fields of science, business and engineering being extremely rare and programs to encourage these disciplines almost non-existent. Subsequently, Tribes have made crucial decisions about their land and other facets of Tribal existence based upon outside technical expertise, such as that provided by the United States government and/or private industries. These outside expert opinions rarely took into account the traditional and cultural values of the Tribes being advised. The purpose of this internship was twofold: Create and maintain a working relationship between CERT and Colorado State University (CSU) to plan for the Summit on Tribal human resource development; and Evaluate and engage in current efforts to strengthen the Tribal Resource Institute in Business, Engineering and Science (TRIBES) program. The intern lists the following as the project results: Positive interactions and productive meetings between CERT and CSU; Gathered information from Tribes; CERT database structure modification; Experience as facilitator in participating methods; Preliminary job descriptions for staff of future TRIBES programs; and Additions for the intern`s personal database of professional contacts and resources.

  20. Systems Analysis of NASA Aviation Safety Program: Final Report

    Science.gov (United States)

    Jones, Sharon M.; Reveley, Mary S.; Withrow, Colleen A.; Evans, Joni K.; Barr, Lawrence; Leone, Karen

    2013-01-01

    A three-month study (February to April 2010) of the NASA Aviation Safety (AvSafe) program was conducted. This study comprised three components: (1) a statistical analysis of currently available civilian subsonic aircraft data from the National Transportation Safety Board (NTSB), the Federal Aviation Administration (FAA), and the Aviation Safety Information Analysis and Sharing (ASIAS) system to identify any significant or overlooked aviation safety issues; (2) a high-level qualitative identification of future safety risks, with an assessment of the potential impact of the NASA AvSafe research on the National Airspace System (NAS) based on these risks; and (3) a detailed, top-down analysis of the NASA AvSafe program using an established and peer-reviewed systems analysis methodology. The statistical analysis identified the top aviation "tall poles" based on NTSB accident and FAA incident data from 1997 to 2006. A separate examination of medical helicopter accidents in the United States was also conducted. Multiple external sources were used to develop a compilation of ten "tall poles" in future safety issues/risks. The top-down analysis of the AvSafe was conducted by using a modification of the Gibson methodology. Of the 17 challenging safety issues that were identified, 11 were directly addressed by the AvSafe program research portfolio.

  1. The joint EC/EPA mid-Connecticut test program

    International Nuclear Information System (INIS)

    Kilgroe, J.D.; Brna, T.G.

    1991-01-01

    In early 1989, Environment Canada and the U.S. Environmental Protection Agency sponsored a comprehensive test program on a refuse-derived fuel (RDF) unit of the Mid-Connecticut facility in Hartford. The program, conducted in cooperation with the Connecticut Resource Recovery Authority (CRRA), the facility's operator, included characterization and performance test phases. The results of the characterization tests were used in defining both the combustion and flue gas cleaning system operating conditions for the performance tests. The results of the performance tests are emphasized in this paper and are summarized in three parts. First, the combustion tests results will be addressed and related to good combustion practice for RDF combustors. Then, the performance of the lime spray dryer absorber/fabric filter system in controlling acid gas (hydrogen chloride, sulfur dioxide), trace organic [polychlorinated dibenzodioxin (PCDD) and polychlorinated dibenzofuran (PCDF)], trace metal [arsenic (as), cadmium (Cd), chromium (Cr), lead (Pb), mercury (Hg), nickel (Ni), and zinc (Zn)], and particulate matter (PM) emissions will be discussed. Finally, the results of ash/residue analyses will be presented

  2. SMART operational field test evaluation : dispatchers survey report : final report

    Science.gov (United States)

    1997-06-01

    The Suburban Mobility Authority for Regional Transportation (SMART) has installed an automaticscheduling and dispatch system (ASD) in Southeast Michigan in accordance with their plans toimplement ITS as a site for an operational field test. The purpo...

  3. SMART operational field test evaluation : scheduler survey report : final report

    Science.gov (United States)

    1997-06-01

    The Suburban Mobility Authority for Regional Transportation (SMART) has installed an automatic scheduling and dispatch system (ASD) in Southeast Michigan in accordance with their plans to implement ITS as a site for an operational field test. The pur...

  4. Better Buildings Neighborhood Program: BetterBuildings Lowell Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Heslin, Thomas

    2014-01-31

    The City of Lowell set four goals at the beginning of the Better Buildings Neighborhood Program: 1. Improve the Downtown Historic Park District’s Carbon Footprint 2. Develop a sustainable and replicable model for energy efficiency in historic buildings 3. Create and retain jobs 4. Promote multi-stakeholder partnerships The City of Lowell, MA was awarded $5 million in May 2010 to conduct energy efficiency retrofits within the downtown National Historical Park (NHP). The City’s target was to complete retrofits in 200,000 square feet of commercial space and create 280 jobs, while adhering to the strict historical preservation regulations that govern the NHP. The development of a model for energy efficiency in historic buildings was successfully accomplished. BetterBuildings Lowell’s success in energy efficiency in historic buildings was due to the simplicity of the program. We relied strongly on the replacement of antiquated HVAC systems and air sealing and a handful of talented energy auditors and contractors. BetterBuildings Lowell was unique for the Better Buildings Neighborhood Program because it was the only program that focused solely on commercial properties. BetterBuildings Lowell did target multi-family properties, which were reported as commercial, but the majority of the building types and uses were commercial. Property types targeted were restaurants, office buildings, museums, sections of larger buildings, mixed use buildings, and multifamily buildings. This unique fabric of building type and use allows for a deeper understanding to how different properties use energy. Because of the National Historical Park designation of downtown Lowell, being able to implement energy efficiency projects within a highly regulated historical district also provided valuable research and precedent proving energy efficiency projects can be successfully completed in historical districts and historical buildings. Our program was very successful in working with the local

  5. 76 FR 6594 - North Carolina: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2011-02-07

    ... Carolina: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act... Section, RCRA Programs and Materials Management Branch, RCRA Division, U.S. Environmental Protection...

  6. 77 FR 61326 - Indiana: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2012-10-09

    ...: Final Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental... RCRA hazardous waste management program. We granted authorization for changes to their program on... 202. Hazardous Waste Management July 30, 2003; 68 329 IAC 3.1-6-2(16); System; Identification and FR...

  7. 77 FR 30512 - Native American Career and Technical Education Program; Final Waivers and Extension of Project...

    Science.gov (United States)

    2012-05-23

    ... DEPARTMENT OF EDUCATION Native American Career and Technical Education Program; Final Waivers and... American Career and Technical Education Program Catalog of Federal Domestic Assistance (CFDA) Number: 84... and Technical Education Program (NACTEP), the Secretary waives 34 CFR 75.250 and 75.261(c)(2) in order...

  8. 76 FR 23795 - Low-Power Television and Translator Upgrade Program: Notice of Final Closing Date

    Science.gov (United States)

    2011-04-28

    .... 110418247-1247-01] Low-Power Television and Translator Upgrade Program: Notice of Final Closing Date AGENCY... receipt of applications for the Low-Power Television and Translator Upgrade Program (Upgrade Program) will... Rules to Establish Rules for Digital Low Power Television, Television Translator, and Television Booster...

  9. 77 FR 60919 - Tennessee: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-10-05

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental..., Division of Solid Waste Management, 5th Floor, L & C Tower, 401 Church Street, Nashville, Tennessee 37243... RCRA hazardous waste management program. We granted authorization for changes to Tennessee's program on...

  10. 78 FR 45208 - Children's Health Insurance Program (CHIP); Final Allotments to States, the District of Columbia...

    Science.gov (United States)

    2013-07-26

    ... 0938-AR79 Children's Health Insurance Program (CHIP); Final Allotments to States, the District of... and expand health insurance coverage to uninsured, low-income children under the Children's Health...). States may implement the Children's Health Insurance Program (CHIP) through a separate state program...

  11. Cast Metals Coalition Technology Transfer and Program Management Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Gwyn, Mike

    2009-03-31

    The Cast Metals Coalition (CMC) partnership program was funded to ensure that the results of the Department of Energy's (DOE) metalcasting research and development (R&D) projects are successfully deployed into industry. Specifically, the CMC program coordinated the transfer and deployment of energy saving technologies and process improvements developed under separately funded DOE programs and projects into industry. The transition of these technologies and process improvements is a critical step in the path to realizing actual energy savings. At full deployment, DOE funded metalcasting R&D results are projected to save 55% of the energy used by the industry in 1998. This closely aligns with DOE's current goal of driving a 25% reduction in industrial energy intensity by 2017. In addition to benefiting DOE, these energy savings provide metalcasters with a significant economic advantage. Deployment of already completed R&D project results and those still underway is estimated to return over 500% of the original DOE and industry investment. Energy savings estimates through December 2008 from the Energy-Saving Melting and Revert Reduction Technology (E-SMARRT) portfolio of projects alone are 12 x 1012 BTUs, with a projection of over 50 x 1012 BTUs ten years after program completion. These energy savings and process improvements have been made possible through the unique collaborative structure of the CMC partnership. The CMC team consists of DOE's Office of Industrial Technology, the three leading metalcasting technical societies in the U.S: the American Foundry Society; the North American Die Casting Association; and the Steel Founders Society of America; and the Advanced Technology Institute (ATI), a recognized leader in distributed technology management. CMC provides collaborative leadership to a complex industry composed of approximately 2,100 companies, 80% of which employ less than 100 people, and only 4% of which employ more than 250 people

  12. CERT tribal internship program. Final intern report: Manuel Steele, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    The purpose of this internship was to facilitate transfer of advancements in renewable energy to Native American lands for economic and educational benefits and to assist in evaluation of proposals submitted for government funding under Title 26 Indian Energy Resources Program. Specific objectives were to examine specific cost factors stated by each Tribe for economic assessment of each proposal; assess environmental impacts of proposed scope of work presented by each Tribe; monitor existing grants for disbursement of requested funds; and provide Tribal governments with a fair and impartial review of grant proposals for funding by the Department of Energy.

  13. National energy peak leveling program (NEPLP). Final report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1977-12-01

    This multisectioned three-Volume report is responsive to the requirements of Contract E (04-3)-1152 to provide a detailed methodology, to include management, technology, and socio-economic aspects, of a voluntary community program of computer-assisted peak load leveling and energy conservation in commercial community facilities. The demonstration project established proof-of-concept in reducing the kW-demand peak by the unofficial goal of 10%, with concurrent kWh savings. This section of volume III contains appendixes of information on load shedding determination, analysis, socio-economic study, contractual cross references, and definitions.

  14. National energy peak leveling program (NEPLP). Final report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1977-12-01

    This three-volume report is responsive to the requirements of contract E (04-3)-1152 to provide a detailed methodology, to include management, technology, and socio-economic aspects, of a voluntary community program for computer-assisted peak load leveling and energy conservation in commercial community facilities. The demonstration project established proof-of-concept in reducing the kW-demand peak by the unofficial goal of 10%, with concurrent kWh savings. The report consists of the following three volumes: Volume I: management overview; Volume II: methodology and technology; and Volume III; appendices.

  15. Significant achievements in the planetary geology program. Final report

    International Nuclear Information System (INIS)

    Head, J.W.

    1978-12-01

    Developments reported at a meeting of principal investigators for NASA's planetology geology program are summarized. Topics covered include the following: constraints on solar system formation; asteriods, comets, and satellites; constraints on planetary interiors; volatiles and regoliths; instrument development techniques; planetary cartography; geological and geochemical constraints on planetary evolution; fluvial processes and channel formation; volcanic processes; Eolian processes; radar studies of planetary surfaces; cratering as a process, landform, and dating method; and the Tharsis region of Mars. Activities at a planetary geology field conference on Eolian processes are reported and techniques recommended for the presentation and analysis of crater size-frequency data are included

  16. Continued research, development and test of SOFC Technology. Final report

    Energy Technology Data Exchange (ETDEWEB)

    2008-09-15

    The aim of the project was to further develop the SOFC cell and stack technology and drive down manufacturing costs in order to accomplish the performance and economic targets set forward in the SOFC road map, which has been developed in collaboration with the national Danish SOFC Strategy group. The project was divided into four parts. Part 1, Continued cell development covered the successful development of larger cells with a 500 cm2 footprint. Part 2, Cell manufacturing covered the production of 9.859 equivalents (12x12 cm2 standard cells) that were used in the stacks for demonstration projects (EFP 33033-0050)and for in-house research, development and testing in this project. Part 3, Continued stack development covered the successful test of a 3 kW{sub e} stack as well as the planning of a >8.000 hours stack test with new stack technology. The >8.000 hours test that started after the end date for this project will last for 12 months and be reported in the PSO 2008-1-010049 project. Part 4, Stack manufacturing covered a number of small stacks for in-house research, development and testing. (auther)

  17. Human performance in nondestructive inspections and functional tests: Final report

    International Nuclear Information System (INIS)

    Harris, D.H.

    1988-10-01

    Human performance plays a vital role in the inspections and tests conducted to assure the physical integrity of nuclear power plants. Even when technically-sophisticated equipment is employed, the outcome is highly dependent on human control actions, calibrations, observations, analyses, and interpretations. The principal consequences of inadequate performance are missed or falsely-reported defects. However, the cost-avoidance that stems from addressing potential risks promptly, and the increasing costs likely with aging plants, emphasize that timeliness and efficiency are important inspection-performance considerations also. Human performance issues were studied in a sample of inspections and tests regularly conducted in nuclear power plants. These tasks, selected by an industry advisory panel, were: eddy-current inspection of steam-generator tubes; ultrasonic inspection of pipe welds; inservice testing of pumps and valves; and functional testing of shock suppressors. Information was obtained for the study from industry and plant procedural documents; training materials; research reports and related documents; interviews with training specialists, inspectors, supervisory personnel, and equipment designers; and first-hand observations of task performance. Eleven recommendations are developed for improving human performance on nondestructive inspections and functional tests. Two recommendations were for the more-effective application of existing knowledge; nine recommendations were for research projects that should be undertaken to assure continuing improvements in human performance on these tasks. 25 refs., 9 figs., 1 tab

  18. Leach testing of Idaho Chemical Processing Plant final waste forms

    International Nuclear Information System (INIS)

    Schuman, R.P.

    1980-01-01

    A number of pellets and highly durable glasses prepared from nonradioactive-simulated high-level wasste calcines have been leach tested. The leach tests are patterned on the IAEA standard test and the proposed Materials Characterization Center tests. Most tests are made with static distilled water at 25, 70, 95, 250, and 350 0 C and in refluxing distilled water, Soxhlet, at 95 0 C. Leach rates are determined by analyzing the leachate by instrumental activation analysis or spectrochemical analysis and from weight loss. Leaches are run on glass using cast and core drilled cylinders, broken pieces and coarse ground material. Sample form has a considerable effect on leach rates; solid pieces gave higher leach rates than ground glass when expressed in g/cm 2 /day. Cesium, molybdenum and weight loss leach rates of cast glass cylinders in distilled water varied from -7 g/cm 7 /day at 25 0 C to approx. 10 -3 g/cm 2 /day at 250 0 C. The leach rates in static distilled water at 95 0 C were considerably lower than those in refluxing distilled water, Soxhlet, at the same temperature. Even at 25 0 C, sodium, cesium, and molybdenum readily leached from the porous pellets, but the pellets showed no visible attack, even at 250 0 C

  19. Validation Testing for Automated Solubility Measurement Equipment Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Lachut, J. S. [Washington River Protection Solutions LLC, Richland, WA (United States)

    2016-01-11

    Laboratory tests have been completed to test the validity of automated solubility measurement equipment using sodium nitrate and sodium chloride solutions (see test plan WRPS-1404441, “Validation Testing for Automated Solubility Measurement Equipment”). The sodium nitrate solution results were within 2-3% of the reference values, so the experiment is considered successful using the turbidity meter. The sodium chloride test was done by sight, as the turbidity meter did not work well using sodium chloride. For example, the “clear” turbidity reading was 53 FNU at 80 °C, 107 FNU at 55 °C, and 151 FNU at 20 °C. The sodium chloride did not work because it is granular and large; as the solution was stirred, the granules stayed to the outside of the reactor and just above the stir bar level, having little impact on the turbidity meter readings as the meter was aimed at the center of the solution. Also, the turbidity meter depth has an impact. The salt tends to remain near the stir bar level. If the meter is deeper in the slurry, it will read higher turbidity, and if the meter is raised higher in the slurry, it will read lower turbidity (possibly near zero) because it reads the “clear” part of the slurry. The sodium chloride solution results, as measured by sight rather than by turbidity instrument readings, were within 5-6% of the reference values.

  20. Space Nuclear Thermal Propulsion Test Facilities Subpanel. Final report

    International Nuclear Information System (INIS)

    Allen, G.C.; Warren, J.W.; Martinell, J.; Clark, J.S.; Perkins, D.

    1993-04-01

    On 20 Jul. 1989, in commemoration of the 20th anniversary of the Apollo 11 lunar landing, President George Bush proclaimed his vision for manned space exploration. He stated, 'First for the coming decade, for the 1990's, Space Station Freedom, the next critical step in our space endeavors. And next, for the new century, back to the Moon. Back to the future. And this time, back to stay. And then, a journey into tomorrow, a journey to another planet, a manned mission to Mars.' On 2 Nov. 1989, the President approved a national space policy reaffirming the long range goal of the civil space program: to 'expand human presence and activity beyond Earth orbit into the solar system.' And on 11 May 1990, he specified the goal of landing Astronauts on Mars by 2019, the 50th anniversary of man's first steps on the Moon. To safely and ever permanently venture beyond near Earth environment as charged by the President, mankind must bring to bear extensive new technologies. These include heavy lift launch capability from Earth to low-Earth orbit, automated space rendezvous and docking of large masses, zero gravity countermeasures, and closed loop life support systems. One technology enhancing, and perhaps enabling, the piloted Mars missions is nuclear propulsion, with great benefits over chemical propulsion. Asserting the potential benefits of nuclear propulsion, NASA has sponsored workshops in Nuclear Electric Propulsion and Nuclear Thermal Propulsion and has initiated a tri-agency planning process to ensure that appropriate resources are engaged to meet this exciting technical challenge. At the core of this planning process, NASA, DOE, and DOD established six Nuclear Propulsion Technical Panels in 1991 to provide groundwork for a possible tri-agency Nuclear Propulsion Program and to address the President's vision by advocating an aggressive program in nuclear propulsion. To this end the Nuclear Electric Propulsion Technology Panel has focused it energies

  1. Mirror Fusion Test Facility data compression study. Final report

    International Nuclear Information System (INIS)

    1979-11-01

    This report is organized as follows. Discussions are given of three of the most important data compression methods that have been developed and studied over the years: coding, transforms, and redundancy reduction. (A brief discussion of how to combine and synthesize these ideas, and others, into a system is given). Specific ideas for compressing MFTF diagnostics and control data are developed. Listings and instructions for using FORTRAN programs that were compiled on the Livermore MFTF computers during the course of the study are also given

  2. Final Environmental assessment for the Uranium Lease Management Program

    International Nuclear Information System (INIS)

    1995-07-01

    The US Department of Energy (DOE) has prepared a programmatic environmental assessment (EA) of the proposed action to continue leasing withdrawn lands and DOE-owned patented claims for the exploration and production of uranium and vanadium ores. The Domestic Uranium Program regulation, codified at Title 10, Part 760.1, of the US Code of Federal Regulations (CFR), gives DOE the flexibility to continue leasing these lands under the Uranium Lease Management Program (ULMP) if the agency determines that it is in its best interest to do so. A key element in determining what is in DOE's ''best interest'' is the assessment of the environmental impacts that may be attributable to lease tract operations and associated activities. On the basis of the information and analyses presented in the EA for the ULMP, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment, as defined in the National Environmental Policy Act (NEPA) of 1969 (42 United States Code 4321 et seq.), as amended.Therefore, preparation of an environmental impact statement is not required for the ULMP,and DOE is issuing this Finding, of No Significant Impact (FONSI)

  3. Final task force report on the Agreement State Program

    International Nuclear Information System (INIS)

    1977-12-01

    Section 274 of the Atomic Energy Act provides a statutory means by which the U.S. Nuclear Regulatory Commission may relinquish to the States a part of its regulatory authority over the use of source material, by-product material, and small quantities of special nuclear material. The Commission is required to retain regulatory authority over the licensing of nuclear facilities, exports and imports of nuclear materials and facilities, larger quantities of special nuclear material, and activities conducted by other Federal agencies which are not exempted by the Act. This study analyzes the NRC Agreement State Program to determine: whether the NRC should aggressively promote Agreement State status; whether the NRC should relinquish additional responsibility to the States and if so, which responsibilities and under what circumstances, and conversely if NRC should reassert authority in any areas; to what extent the NRC should continue to oversee State performance; and whether changes in the statute or regulations are desirable or required. At present, there are 25 states that have not opted for agreement status. Appendix A contains a discussion of the legislative history of Section 274, a report on the current status of the program, Agreement State review procedures, the full text of Section 274, a list of Agreement States, dates of agreements, number of licenses, a list of non-Agreement States, and numbers of NRC licenses in these States. Appendix B analyzes states' comments

  4. An innovative educational program for residential energy efficiency. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Laquatra, J.; Chi, P.S.K.

    1996-09-01

    Recognizing the importance of energy conservation, under sponsorship of the US Department of Energy, Cornell University conducted a research and demonstration project entitled An Innovative Educational Program for Residential Energy Efficiency. The research project examined the amount of residential energy that can be saved through changes in behavior and practices of household members. To encourage these changes, a workshop was offered to randomly-selected households in New York State. Two surveys were administered to household participants (Survey 1 and Survey 2, Appendix A) and a control group; and a manual was developed to convey many easy but effective ways to make a house more energy efficient (see Residential Manual, Appendix B). Implementing methods of energy efficiency will help reduce this country`s dependence on foreign energy sources and will also reduce the amount of money that is lost on inefficient energy use. Because Cornell Cooperative Extension operates as a component of the land-grant university system throughout the US, the results of this research project have been used to develop a program that can be implemented by the Cooperative Extension Service nationwide. The specific goals and objectives for this project will be outlined, the population and sample for the research will be described, and the instruments utilized for the survey will be explained. A description of the workshop and manual will also be discussed. This report will end with a summary of the results from this project and any observed changes and/or recommendations for future surveys pertaining to energy efficiency.

  5. Final Environmental assessment for the Uranium Lease Management Program

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    The US Department of Energy (DOE) has prepared a programmatic environmental assessment (EA) of the proposed action to continue leasing withdrawn lands and DOE-owned patented claims for the exploration and production of uranium and vanadium ores. The Domestic Uranium Program regulation, codified at Title 10, Part 760.1, of the US Code of Federal Regulations (CFR), gives DOE the flexibility to continue leasing these lands under the Uranium Lease Management Program (ULMP) if the agency determines that it is in its best interest to do so. A key element in determining what is in DOE`s ``best interest`` is the assessment of the environmental impacts that may be attributable to lease tract operations and associated activities. On the basis of the information and analyses presented in the EA for the ULMP, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment, as defined in the National Environmental Policy Act (NEPA) of 1969 (42 United States Code 4321 et seq.), as amended.Therefore, preparation of an environmental impact statement is not required for the ULMP,and DOE is issuing this Finding, of No Significant Impact (FONSI).

  6. Advanced Concept Exploration for Fast Ignition Science Program, Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Stephens, Richard Burnite [General Atomics; McLean, Harry M. [Lawrence Livermore National Laboratory; Theobald, Wolfgang [Laboratory for Laser Energetics; Akli, Kramer U. [The Ohio State University; Beg, Farhat N. [University of California, San Diego; Sentoku, Yasuhiko [University of Nevada, Reno; Schumacher, Douglass W. [The Ohio State University; Wei, Mingsheng [General Atomics

    2013-09-04

    The Fast Ignition (FI) Concept for Inertial Confinement Fusion (ICF) has the potential to provide a significant advance in the technical attractiveness of Inertial Fusion Energy reactors. FI differs from conventional “central hot spot” (CHS) target ignition by decoupling compression from heating: using a laser (or heavy ion beam or Z pinch) drive pulse (10’s of nanoseconds) to create a dense fuel and a second, much shorter (~10 picoseconds) high intensity pulse to ignite a small volume within the dense fuel. The physics of fast ignition process was the focus of our Advanced Concept Exploration (ACE) program. Ignition depends critically on two major issues involving Relativistic High Energy Density (RHED) physics: The laser-induced creation of fast electrons and their propagation in high-density plasmas. Our program has developed new experimental platforms, diagnostic packages, computer modeling analyses, and taken advantage of the increasing energy available at laser facilities to advance understanding of the fundamental physics underlying these issues. Our program had three thrust areas: • Understand the production and characteristics of fast electrons resulting from FI relevant laser-plasma interactions and their dependence on laser prepulse and laser pulse length. • Investigate the subsequent fast electron transport in solid and through hot (FI-relevant) plasmas. • Conduct and understand integrated core-heating experiments by comparison to simulations. Over the whole period of this project (three years for this contract), we have greatly advanced our fundamental understanding of the underlying properties in all three areas: • Comprehensive studies on fast electron source characteristics have shown that they are controlled by the laser intensity distribution and the topology and plasma density gradient. Laser pre-pulse induced pre-plasma in front of a solid surface results in increased stand-off distances from the electron origin to the high density

  7. Programs for Children with Specific Learning Disabilities. P.L. 91-230, Title VI-G Formal Final Evaluation. (Statistical Analysis of Data).

    Science.gov (United States)

    Murphy, Philip J.

    The paper reports the final evaluation of a program for approximately 143 learning disabled (LD) students (grades 6-to-12) from six school districts. A number of test instruments were used to evaluate student progress during the program, including the Wide Range Achievement Test (WRAT), the Durrell Analysis of Reading Difficulty, and the…

  8. 78 FR 75961 - Energy Conservation Program: Test Procedures for Electric Motors

    Science.gov (United States)

    2013-12-13

    ... Conservation Program: Test Procedures for Electric Motors; Final Rule #0;#0;Federal Register / Vol. 78 , No... Procedures for Electric Motors AGENCY: Office of Energy Efficiency and Renewable Energy, Department of Energy... procedures for electric motors to allow currently unregulated motors to be tested by clarifying the test...

  9. 100 GHz, 1 MW, CW gyrotron study program. Final report

    International Nuclear Information System (INIS)

    Felch, K.; Bier, R.; Caplan, M.; Jory, H.

    1983-09-01

    The results of a study program to investigate the feasibility of various approaches in designing a 100 GHz, 1 MW CW gyrotron are presented. A summary is given of the possible configurations for a high average power, high frequency gyrotron, including an historical survey of experimental results which are relevant to the various approaches. A set of basic scaling considerations which enable qualitative comparisons between particular gyrotron interaction circuits is presented. These calculations are important in understanding the role of various electron beam and circuit parameters in achieving a viable gyrotron design. Following these scaling exercises, a series of design calculations is presented for a possible approach in achieving 100 GHz, 1 MW CW. These calculations include analyses of the electron gun and interaction circuit parts of the gyrotron, and a general analysis of other aspects of a high average power, high frequency gyrotron. Scalability of important aspects of the design to other frequencies is also discussed, as well as key technology issues

  10. Gore-Mbeki Binational Commission integrated housing program. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

    This report documents the work done under Grant DE-FG36-97GO10209, Innovative Renewable Energy Technology Transfer Program. PEER Consultants, PC, and its subcontractor, PEER Africa (Pty.) Ltd., received an $88,000.00 grant to plan and build two energy efficient homes in the black township of Gugulethu in Cape Town, South Africa. These demonstration homes were given to the people of South Africa as a gesture of goodwill by the US government as part of the Gore-Mbeki Binational Commission (BNC) agreements and cooperation. The BNC is the term used to describe the agreement to work together by the US and the South African governments for economic development of South Africa in the areas of energy, commerce, agriculture, housing, and transportation. The BNC was formed in 1995. This project under the auspices of the BNC started in September 1996. The DOE-funded portion was performed between January 11, 1997 and February 28, 1997.

  11. Power plant system assessment. Final report. SP-100 Program

    International Nuclear Information System (INIS)

    Anderson, R.V.; Atkins, D.F.; Bost, D.S.

    1983-01-01

    The purpose of this assessment was to provide system-level insights into 100-kWe-class space reactor electric systems. Using these insights, Rockwell was to select and perform conceptual design studies on a ''most attractive'' system that met the preliminary design goals and requirements of the SP-100 Program. About 4 of the 6 months were used in the selection process. The remaining 2 months were used for the system conceptual design studies. Rockwell completed these studies at the end of FY 1983. This report summarizes the results of the power plant system assessment and describes our choice for the most attractive system - the Rockwell SR-100G System (Space Reactor, 100 kWe, Growth) - a lithium-cooled UN-fueled fast reactor/Brayton turboelectric converter system

  12. VHTR engineering design study: intermediate heat exchanger program. Final report

    International Nuclear Information System (INIS)

    1976-11-01

    The work reported is the result of a follow-on program to earlier Very High Temperature Reactor (VHTR) studies. The primary use of the VHTR is to provide heat for various industrial processes, such as hydrocarbon reforming and coal gasification. For many processes the use of an intermediate heat transfer barrier between the reactor coolant and the process is desirable; for some processes it is mandatory. Various intermediate heat exchanger (IHX) concepts for the VHTR were investigated with respect to safety, cost, and engineering design considerations. The reference processes chosen were steam-hydrocarbon reforming, with emphasis on the chemical heat pipe, and steam gasification of coal. The study investigates the critically important area of heat transfer between the reactor coolant, helium, and the various chemical processes

  13. Jersey City energy conservation demonstration program. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Newbold, R.F.

    1978-08-01

    The Aerospace Corporation, the City Government, and the Board of Education of Jersey City have conducted a group of energy-conservation experiments to explore a number of conservation techniques believed to offer quick payback and to be of wide applicability. Experiments include the updating and/or rehabilitation of the energy-consuming features of old buildings and installation of devices designed to minimize energy losses caused by human error or laxity. Specific examples include: upgrading of the deteriorated and inefficient steam-distribution system of the city hall (originally constructed in 1894); an extensive program of reducing infiltration in an old school building; use of several timing devices in connection with heating, ventilation, and lighting systems to encourage energy-conservation practices; retrofit of school classrooms with high-pressure sodium lamps; and demonstration of practical and cost-effective ways of increasing the efficiency of conventional steam boilers. The report presents: the nature of the selected experiments; technical, human, and organizational factors that proved significant in performing and evaluating the experiments; discussions of observations and lessons learned; and general recommendations for an extended program of energy conservation in local governments. It is emphasized that, in retrofit of existing buildings, the unexpected is commonplace; and the habits and attitudes of building occupants are elements of the system that must always be taken into account. This report shows the benefits of energy saving, cost saving, and added comfort that may be attained by retrofitting old buildings, noting typical complications that arise. The effectiveness of the conservation methods is presented in terms of costs relative to effective payback periods calculated from results of their application in Jersey City.

  14. Energy-related inventions program invention 637. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-31

    The final technical report for the Pegasus plow, a stalk and root embedding apparatus, describes progress from the development stage to the product support stage. The US Department of Agriculture - Agriculture Research Service (ARS) is now in the second year of a three year study comparing the Pegasus to conventional tillage. So far, no downside has been with the Pegasus and the following benefits have been documented: (1) Energy savings of 65.0 kilowatt hours per hectare over conventional tillage. This is when the Pegasus plow is used to bury whole stalks, and represents a 70% savings over conventional tillage (92.5 kilowatt hours per hectare). (2) Four to seven fewer passes of tillage, depending on the particular situation. This represents a substantial time savings to farmers. (3) So far, no differences in cotton yields. Recent cotton boll counts in one study indicate a higher yield potential with the Pegasus. (4) No disease problems. (5) Significantly higher levels of organic matter in the soil. A hypothesis of the study is that whole stalk burial may reduce plant disease problems. This hypothesis has not yet been proven. (6) Significantly higher levels of nitrate nitrogen. Total nitrogen and ammonia nitrogen trended higher but were not significantly different. This shows that whole stalk burial does not adversely affect the nitrogen cycle in the soil and may actually improve it. The marketing support stage of the project is also described in the report.

  15. NMSBA: Aken Technologies Final Report: Toxicity Testing of Liquidoff

    Energy Technology Data Exchange (ETDEWEB)

    Ruffing, Anne [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jensen, Travis [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Strickland, Lucas [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-02-01

    To determine the effect of Liquidoff on bacteria, three bacterial strains were tested: Escherichia coli DH5α, Synechococcus sp. PCC 7002, and Synechococcus elongatus PCC 7942. E. coli DH5α is a Gram-negative, aerobic bacterium that is often found in normal gut flora and is commonly used the laboratory due to its fast growth rate. Synechococcus sp. PCC 7002 and S. elongatus PCC 7942 are Gram-negative, aquatic, autophototrophic cyanobacteria. Synechococcus sp. PCC 7002 is a marine cyanobacterium isolated from ‘fish pens’ on Magueyes Island, Puerto Rico in 1962, while S. elongatus PCC 7942 is a freshwater cyanobacterium. It should be noted that no Gram-positive bacterium was tested in this study.

  16. Final Test Report: Hexavalent Chrome Free Coatings for Electronics Electromagnetic Interference (EMI) Shielding Effectiveness (SE)

    Science.gov (United States)

    Kessel, Kurt R.

    2016-01-01

    The test results for Salt Spray Resistance, Static Heat and Humidity and Marine Environment can be found in Sections 3.1.3.3, 3.1.4.3 and 3.1.5.3 respectively. In summary, both the Metalast TCP and SurTec 650 Type 2 conversion coatings perform very similar to the incumbent Type 1 conversion coating against both 6061 and 5052 aluminum under all three test conditions. Significant prior work was performed to select the aluminum and conversion coating included within this test cycle; Reference - NASA GSDO Program Hexavalent Chrome Alternatives Final Pretreatments Test Report Task Order: NNH12AA45D September 01, 2013. As illustrated in the data, the 6061 aluminum panels SLIGHTLY out-performed the 5052 aluminum panels. Individual shielding effectiveness graphs for each panel are included within Appendix C and D. One other notable effect found during review of the data is that the Test Panels exposed to B117 Salt Fog reduced in shielding effectiveness significantly more than the Marine Environment Test Panels. The shielding effectiveness of the Marine Test Panels was approximately 20dB higher than the Test Panels that underwent B117 Salt Fog Exposure. The intent of this evaluation was not to maximize shielding effectiveness values. The same Parker Chomerics Cho-Seal 6503 gasket material was used for all panels with aluminum and conversion coating variants. A typical EMI gasket design for corrosive environments would be done quite differently. The intent was to execute a test that would provide the best possible evaluation of different aluminum materials and conversion coatings in corrosive environments. The test program achieved this intent. The fact that the two aluminums and two Type II conversion coatings performed similar to the incumbent Type 1 conversion coating is a positive outcome. It was desired to have an outcome that further differentiation the performance of two aluminum types and two conversion coating types but this could not be extracted by the test

  17. TRIGA high wt -% LEU fuel development program. Final report

    International Nuclear Information System (INIS)

    West, G.B.

    1980-07-01

    The principal purpose of this work was to investigate the characteristics of TRIGA fuel where the contained U-235 was in a relatively high weight percent (wt %) of LEU (low enriched uranium - enrichment of less than 20%) rather than a relatively low weight percent of HEU (high enriched uranium). Fuel with up to 45 wt % U was fabricated and found to be acceptable after metallurgical examinations, fission product retention tests and physical property examinations. Design and safety analysis studies also indicated acceptable prompt negative temperature coefficient and core lifetime characteristics for these fuels

  18. Ferrocyanide Safety Program cyanide speciation studies. Final report

    International Nuclear Information System (INIS)

    Bryan, S.A.; Pool, K.H.; Bryan, S.L.

    1995-07-01

    This report summarizes Pacific Northwest Laboratory's fiscal year (FY) 1995 progress toward developing and implementing methods to identify and quantify cyanide species in ferrocyanide tank waste. This work was conducted for Westinghouse Hanfbrd Company's (WHC's) Ferrocyanide Safety Program. Currently, there are 18 high-level waste storage tanks at the US Department of Energy's Hanford Site that are on a Ferrocyanide Tank Watchlist because they contain an estimated 1000 g-moles or more of precipitated ferrocyanide. In the presence of oxidizing material such as sodium nitrate or nitrite, ferrocyanide can be made to react exothermally by heating it to high temperatures or by applying an electrical spark of sufficient energy (Cady 1993). However, fuel, oxidizers, and temperature are all important parameters. If fuel, oxidizers, or high temperatures (initiators) are not present in sufficient amounts, then a runaway or propagating reaction cannot occur. To bound the safety concern, methods are needed to definitively measure and quantitate ferrocyanide concentration present within the actual waste. The target analyte concentration for cyanide in waste is approximately 0.1 to 15 wt % (as cyanide) in the original undiluted sample. After dissolution of the original sample and appropriate dilutions, the concentration range of interest in the analytical solutions can vary between 0.001 to 0.1 wt % (as cyanide). In FY 1992, 1993, and 1994, two solution (wet) methods were developed based on Fourier transform infrared (FTIR) spectroscopy and ion chromatography (IC); these methods were chosen for further development activities. The results of these activities are described

  19. Defense High-Level Waste Leaching Mechanisms Program. Final report

    International Nuclear Information System (INIS)

    Mendel, J.E.

    1984-08-01

    The Defense High-Level Waste Leaching Mechanisms Program brought six major US laboratories together for three years of cooperative research. The participants reached a consensus that solubility of the leached glass species, particularly solubility in the altered surface layer, is the dominant factor controlling the leaching behavior of defense waste glass in a system in which the flow of leachant is constrained, as it will be in a deep geologic repository. Also, once the surface of waste glass is contacted by ground water, the kinetics of establishing solubility control are relatively rapid. The concentrations of leached species reach saturation, or steady-state concentrations, within a few months to a year at 70 to 90 0 C. Thus, reaction kinetics, which were the main subject of earlier leaching mechanisms studies, are now shown to assume much less importance. The dominance of solubility means that the leach rate is, in fact, directly proportional to ground water flow rate. Doubling the flow rate doubles the effective leach rate. This relationship is expected to obtain in most, if not all, repository situations

  20. Defense High-Level Waste Leaching Mechanisms Program. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Mendel, J.E. (compiler)

    1984-08-01

    The Defense High-Level Waste Leaching Mechanisms Program brought six major US laboratories together for three years of cooperative research. The participants reached a consensus that solubility of the leached glass species, particularly solubility in the altered surface layer, is the dominant factor controlling the leaching behavior of defense waste glass in a system in which the flow of leachant is constrained, as it will be in a deep geologic repository. Also, once the surface of waste glass is contacted by ground water, the kinetics of establishing solubility control are relatively rapid. The concentrations of leached species reach saturation, or steady-state concentrations, within a few months to a year at 70 to 90/sup 0/C. Thus, reaction kinetics, which were the main subject of earlier leaching mechanisms studies, are now shown to assume much less importance. The dominance of solubility means that the leach rate is, in fact, directly proportional to ground water flow rate. Doubling the flow rate doubles the effective leach rate. This relationship is expected to obtain in most, if not all, repository situations.

  1. PWR steam-side chemistry follow program. Final report

    International Nuclear Information System (INIS)

    Economy, G.; Wootten, M.J.

    1982-08-01

    Denting is the diametral reduction of Inconel 600 tubes at the support plates of several nuclear steam generators during operation. This tube deformation was shown to be caused by the expansion forces resulting from formation of voluminous oxide generated by corrosion of the carbon steel support plate. The denting phenomenon and potential methods for its inhibition were investigated in the laboratory using isothermal capsules and heated crevice (heat transfer) testing at temperatures relevant to operating steam generators. Both test methods simulate the tube-support plate geometry and materials. Mathematical models were developed to predict the denting behavior of isothermal capsules. Three additives were investigated as potential denting inhibitors. Soaking with calcium hydroxide or sodium phosphate under heat transfer conditions did not inhibit denting when the environment was recontaminated, in contrast to similar soaks in boric acid which inhibited denting for two to four weeks following recontamination. When the boric acid soak was followed by on-line boric acid treatment, inhibition was maintained

  2. Tests and final integration of the ATLAS semiconductor tracker

    CERN Document Server

    Mikulec, Bettina

    2005-01-01

    The Silicon Tracker (SCT) is part of the Inner Detector at the ATLAS experiment at CERN. Its basic building blocks are 5 different types of silicon strip modules. In total more than 15000 p-on-n single-sided silicon strip sensors of an area of about 61 m2 were used to produce 4088 SCT modules. An overall module production yield of 92% could be achieved, where the silicon modules comply with the tight electrical, thermal and mechanical specifications. The macro-assembly of 2112 barrel modules to the four barrel support cylinders was successfully carried out. The nine disks of one endcap are fully populated with 988 modules, and for the second endcap more than 50% of the modules are already mounted. Test results operating complete barrels will be presented as well as a description of the test setup. The different integration steps of the SCT with the surrounding Transition Radiation Tracker (TRT) will be explained. The installation of SCT and TRT into the ATLAS pit will happen during 2006.

  3. Final Technical Report - Photovoltaics for You (PV4You) Program

    Energy Technology Data Exchange (ETDEWEB)

    Weissman, J. M. [Interstate Renewable Energy Council (IREC), New York, NY (United States); Sherwood, L. [Interstate Renewable Energy Council (IREC), New York, NY (United States); Pulaski, J. [Interstate Renewable Energy Council (IREC), New York, NY (United States); Cook, C. [Interstate Renewable Energy Council (IREC), New York, NY (United States); Kalland, S. [Interstate Renewable Energy Council (IREC), New York, NY (United States); Haynes, J. [Interstate Renewable Energy Council (IREC), New York, NY (United States)

    2005-08-14

    In September 2000, the Interstate Renewable Energy Council (IREC) began its 5-year work on contract # DE-FGO3-00SF22116, the Photovoltaics for You (PV4You) Project. The objective was to develop and distribute information on photovoltaics and to educate key stakeholder groups including state government agencies, local government offices, consumer representative agencies, school officials and students, and Million Solar Roofs Partnerships. In addition, the project was to identify barriers to the deployment of photovoltaics and implement strategies to overcome them. Information dissemination and education was accomplished by publishing newsletters; creating a base of information, guides, and models on the www.irecusa.org and the www.millionsolarroofs.org web sites; convening workshops and seminars; engaging multiple stakeholders; and widening the solar network to include new consumers and decision makers. Two major web sites were maintained throughout the project cycle. The www.irecusa.org web site housed dedicated pages for Connecting to the Grid, Schools Going Solar, Community Outreach, and Certification & Training. The www.millionsolarroofs.org web site was created to serve the MSR Partnerships with news, interviews, key documents, and resource material. Through the course of this grant, the Interstate Renewable Energy Council has been supporting the Department of Energy's solar energy program goals by providing the Department with expertise services for their network of city, state, and community stakeholders. IREC has been the leading force at the state and federal levels regarding net metering and interconnection policy for photovoltaic systems. The principal goal and benefit of the interconnection and net metering work is to lower both barriers and cost for the installation of PV. IREC typically plays a leadership role among small generator stakeholders and has come to be relied upon for its expertise by industry and regulators. IREC also took a leadership

  4. Actinide partitioning-transmutation program final report. I. Overall assessment

    International Nuclear Information System (INIS)

    Croff, A.G.; Blomeke, J.O.; Finney, B.C.

    1980-06-01

    This report is concerned with an overall assessment of the feasibility of and incentives for partitioning (recovering) long-lived nuclides from fuel reprocessing and fuel refabrication plant radioactive wastes and transmuting them to shorter-lived or stable nuclides by neutron irradiation. The principal class of nuclides considered is the actinides, although a brief analysis is given of the partitioning and transmutation (P-T) of 99 Tc and 129 I. The results obtained in this program permit us to make a comparison of the impacts of waste management with and without actinide recovery and transmutation. Three major conclusions concerning technical feasibility can be drawn from the assessment: (1) actinide P-T is feasible, subject to the acceptability of fuels containing recycle actinides; (2) technetium P-T is feasible if satisfactory partitioning processes can be developed and satisfactory fuels identified (no studies have been made in this area); and (3) iodine P-T is marginally feasible at best because of the low transmutation rates, the high volatility, and the corrosiveness of iodine and iodine compounds. It was concluded on the basis of a very conservative repository risk analysis that there are no safety or cost incentives for actinide P-T. In fact, if nonradiological risks are included, the short-term risks of P-T exceed the long-term benefits integrated over a period of 1 million years. Incentives for technetium and iodine P-T exist only if extremely conservative long-term risk analyses are used. Further RD and D in support of P-T is not warranted

  5. DOE Program for Academic and Industrial Research (PAIR) - Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Rabolt, J. F.

    2003-02-12

    The use of polymeric materials is extremely widespread in our lives today. The value of these materials is directly related to various macroscopic properties. High elasticity, toughness, and strength may all be ultimately important to the end user. A large number of analytical tests can be used to measure these macroscopic properties after the material has been processed. However, it is important to remember that these macroscopic properties ultimately derive from molecular level effects and hence, are already set when processing is complete. Polymers can be extruded into films, spun into fibers, and molded into parts with differing properties, but the understanding of how these properties can be affected by the processing step is unclear. An understanding of the cause and effect.

  6. Communicating radon risk effectively: Radon testing in Maryland. Final report

    International Nuclear Information System (INIS)

    Desvousges, W.H.; Smith, V.K.; Rink, H.H.

    1988-10-01

    Two sets of materials and corresponding delivery strategies for communicating radon risk were evaluated, compared with a 'no-special-treatment' strategy in a comparison community. One community received radio public-service announcements and utility bill inserts. The second received these plus posters, local government sponsorship of a radon awareness week, and local slide presentations. The most-intensive efforts (multiple channels, multiple hits) were more effective than the less intensive effort, which had little impact compared with no special treatment. From a marketing perspective, the effort was very successful, increasing the share of homeowners who tested for radon from 5% to 15%. This may not be viewed as sufficiently effective from a public-health perspective, however

  7. Final project report: High energy rotor development, test and evaluation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    Under the auspices of the {open_quotes}Government/Industry Wind Technology Applications Project{close_quotes} [{open_quotes}Letter of Interest{close_quotes} (LOI) Number RC-1-11101], Flo Wind Corp. has successfully developed, tested, and delivered a high-energy rotor upgrade candidate for their 19-meter Vertical Axis Wind Turbine. The project included the demonstration of the innovative extended height-to-diameter ratio concept, the development of a continuous span single-piece composite blade, the demonstration of a continuous blade manufacturing technique, the utilization of the Sandia National Laboratories developed SNLA 2150 natural laminar flow airfoil and the reuse of existing wind turbine and wind power plant infrastructure.

  8. Final turbine and test facility design report Alden/NREC fish friendly turbine

    Energy Technology Data Exchange (ETDEWEB)

    Cook, Thomas C. [Alden Research Lab., Holden, MA (United States); Cain, Stuart A. [Alden Research Lab., Holden, MA (United States); Fetfatsidis, Paul [Alden Research Lab., Holden, MA (United States); Hecker, George E. [Alden Research Lab., Holden, MA (United States); Stacy, Philip S. [Alden Research Lab., Holden, MA (United States)

    2000-09-01

    The final report provides an overview of the Alden/NREC Fish Friendly turbine design phase, turbine test plan, preliminary test results, costs, schedule, and a hypothetical application at a real world project.

  9. 75 FR 52892 - Energy Conservation Program for Consumer Products: Test Procedures for Residential Water Heaters...

    Science.gov (United States)

    2010-08-30

    ... ``Energy Conservation Program for Consumer Products Other Than Automobiles,'' including residential water... final rule revising energy conservation standards for residential water heaters, direct heating.... EERE-2009-BT-TP-0013] RIN 1904-AB95 Energy Conservation Program for Consumer Products: Test Procedures...

  10. CAS-NETL-PNNL CEP Program Final Report

    Energy Technology Data Exchange (ETDEWEB)

    King, David L.; Spies, Kurt A.; Rainbolt, James E.; Zhang, Keling

    2014-03-31

    This collaborative joint research project is in the area of advanced gasification and conversion, within the CAS-NETL-PNNL Memorandum of Understanding. The goal is the development and testing of an integrated warm syngas cleanup process. This effort is focused on an advanced, integrated system for capture and removal of alkali, sulfur, PH3, AsH3, chloride, and CO2, leading to a future process demonstration at a CAS gasification facility. Syngas produced by gasification can be used for production of fuels (Fischer-Tropsch, SNG, mixed alcohols), chemicals (MeOH, NH3), and hydrogen for fuel cells and IGCC. To employ this syngas, especially for synthesis reactions, contained impurities must be removed to sub-ppmv levels [1]. Commercially available approaches to remove contaminant species suffer from inefficiencies, employing solvents at ambient or lower temperature along with backup sacrificial sorbents, whereas syngas utilization occurs at higher temperatures. The efficiency and economics syngas utilization can be significantly improved if all the contaminants and CO2 are removed at temperatures higher than the chemical synthesis reaction temperatures (> 250 °C) [2].

  11. Solair heater program: solair applications study. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1977-12-01

    General Electric has designed and tested a low-cost solar system using a vacuum tube solar air heater under ERDA Contract E(11-1)-2705. This contract extension has been provided to evaluate various applications of this solar collector. The evaluation identified attractive applications, evaluated corresponding control procedures, estimated system performance, compared economically insolation and insulation, and evaluated the repackaging of off-the-shelf equipment for improved cost effectiveness. The results of this study prompted General Electric's marketing group to do a detailed commercialization study of a residential domestic water heating system using the Solair concept which has been selected as the most attractive application. Other attractive applications are space/domestic water heating and a heat pump assisted solar system/domestic water heating where the heat pump and the solar system function in parallel. A prime advantage of heated air solar systems over liquid systems is cost and longer life which results in higher BTU's/dollar. Other air system advantages are no liquid leakage problems, no toxicity of freezing problems, and less complicated equipment. A hybrid solar system has been identified that can improve the market penetration of solar energy. This system would use the existing mass of the house for energy storage thereby reducing solar cost and complexity. Adequate performance can be obtained with house temperature swings comparable to those used in nighttime setback of the thermostat. Details of this system are provided.

  12. Final report of fuel dynamics Test E7

    International Nuclear Information System (INIS)

    Doerner, R.C.; Murphy, W.F.; Stanford, G.S.; Froehle, P.H.

    1977-04-01

    Test data from an in-pile failure experiment of high-power LMFBR-type fuel pins in a simulated $3/s transient-overpower (TOP) accident are reported and analyzed. Major conclusions are that (1) a series of cladding ruptures during the 100-ms period preceding fuel release injected small bursts of fission gas into the flow stream; (2) gas release influenced subsequent cladding melting and fuel release [there were no measurable FCI's (fuel-coolant interactions), and all fuel motion observed by the hodoscope was very slow]; (3) the predominant postfailure fuel motion appears to be radial swelling that left a spongy fuel crust on the holder wall; (4) less than 4 to 6 percent of the fuel moved axially out of the original fuel zone, and most of this froze within a 10-cm region above the original top of the fuel zone to form the outlet blockage. An inlet blockage approximately 1 cm long was formed and consisted of large interconnected void regions. Both blockages began just beyond the ends of the fuel pellets

  13. Spacecraft Testing Programs: Adding Value to the Systems Engineering Process

    Science.gov (United States)

    Britton, Keith J.; Schaible, Dawn M.

    2011-01-01

    Testing has long been recognized as a critical component of spacecraft development activities - yet many major systems failures may have been prevented with more rigorous testing programs. The question is why is more testing not being conducted? Given unlimited resources, more testing would likely be included in a spacecraft development program. Striking the right balance between too much testing and not enough has been a long-term challenge for many industries. The objective of this paper is to discuss some of the barriers, enablers, and best practices for developing and sustaining a strong test program and testing team. This paper will also explore the testing decision factors used by managers; the varying attitudes toward testing; methods to develop strong test engineers; and the influence of behavior, culture and processes on testing programs. KEY WORDS: Risk, Integration and Test, Validation, Verification, Test Program Development

  14. Smart Infrared Inspection System Field Operational Test Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Siekmann, Adam [ORNL; Capps, Gary J [ORNL; Franzese, Oscar [ORNL; Lascurain, Mary Beth [ORNL

    2011-06-01

    The Smart InfraRed Inspection System (SIRIS) is a tool designed to assist inspectors in determining which vehicles passing through the SIRIS system are in need of further inspection by measuring the thermal data from the wheel components. As a vehicle enters the system, infrared cameras on the road measure temperatures of the brakes, tires, and wheel bearings on both wheel ends of commercial motor vehicles (CMVs) in motion. This thermal data is then presented to enforcement personal inside of the inspection station on a user friendly interface. Vehicles that are suspected to have a violation are automatically alerted to the enforcement staff. The main goal of the SIRIS field operational test (FOT) was to collect data to evaluate the performance of the prototype system and determine the viability of such a system being used for commercial motor vehicle enforcement. From March 2010 to September 2010, ORNL facilitated the SIRIS FOT at the Greene County Inspection Station (IS) in Greeneville, Tennessee. During the course of the FOT, 413 CMVs were given a North American Standard (NAS) Level-1 inspection. Of those 413 CMVs, 384 were subjected to a SIRIS screening. A total of 36 (9.38%) of the vehicles were flagged by SIRIS as having one or more thermal issues; with brakes issues making up 33 (91.67%) of those. Of the 36 vehicles flagged as having thermal issues, 31 (86.11%) were found to have a violation and 30 (83.33%) of those vehicles were placed out-of-service (OOS). Overall the enforcement personnel who have used SIRIS for screening purposes have had positive feedback on the potential of SIRIS. With improvements in detection algorithms and stability, the system will be beneficial to the CMV enforcement community and increase overall trooper productivity by accurately identifying a higher percentage of CMVs to be placed OOS with minimal error. No future evaluation of SIRIS has been deemed necessary and specifications for a production system will soon be drafted.

  15. 77 FR 39194 - Combined Drug and Alcohol Testing Programs

    Science.gov (United States)

    2012-07-02

    .... Revise paragraph (c)(5) and redesignate it as (c)(6); Sec. 120.115 Employee Assistance Program (EAP... assistance program (EAP). Finally, this rulemaking would make it clear that the agency's practice of... of the training given to both supervisors and employees in their employee assistance programs...

  16. EZLP: An Interactive Computer Program for Solving Linear Programming Problems. Final Report.

    Science.gov (United States)

    Jarvis, John J.; And Others

    Designed for student use in solving linear programming problems, the interactive computer program described (EZLP) permits the student to input the linear programming model in exactly the same manner in which it would be written on paper. This report includes a brief review of the development of EZLP; narrative descriptions of program features,…

  17. Prototypical Rod Construction Demonstration Project. Phase 3, Final report: Volume 1, Cold checkout test report, Book 3

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    The objective of Phase 3 of the Prototypical Rod consolidation Demonstration Project (PRCDP) was to procure, fabricate, assemble, and test the Prototypical Rod consolidation System as described in the NUS Phase 2 Final Design Report. This effort required providing the materials, components, and fabricated parts which makes up all of the system equipment. In addition, it included the assembly, installation, and setup of this equipment at the Cold Test Facility. During the Phase 3 effort the system was tested on a component, subsystem, and system level. This volume 1, discusses the PRCDP Phase 3 Test Program that was conducted by the HALLIBURTON NUS Environmental Corporation under contract AC07-86ID12651 with the United States Department of Energy. This document, Volume 1, Book 3 discusses the following topics: Downender Test Results and Analysis Report; NFBC Canister Upender Test Results and Analysis Report; Fuel Assembly Handling Fixture Test Results and Analysis Report; and Fuel Canister Upender Test Results and Analysis Report.

  18. 76 FR 18927 - Oklahoma: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2011-04-06

    ...: Final Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental... hazardous waste management program. We authorized the following revisions: Oklahoma received authorization... accordance with 40 CFR 271.21. The Oklahoma Hazardous Waste Management Act (``OHWMA'') provides the ODEQ with...

  19. 78 FR 15299 - New York: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2013-03-11

    ...: Final Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental... Waste program as addressed by the federal used oil management regulations that were published on..., New York Codes, Rules and Regulations (6 NYCRR), Volume A-2A, Hazardous Waste Management System...

  20. 76 FR 6561 - North Carolina: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2011-02-07

    ... Carolina: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... December 31, 1984 (49 FR 48694) to implement its base hazardous waste management program. EPA granted... XV are from the North Carolina Hazardous Waste Management Rules 15A NCAC 13A, effective April 23...

  1. 76 FR 56708 - Ohio: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2011-09-14

    ... Hazardous Waste Management Program Revision AGENCY: Environmental Protection Agency (EPA). ACTION: Proposed..., 1989 (54 FR 27170) to implement the RCRA hazardous waste management program. We granted authorization... December 7, 2004. Waste Combustors; Final Rule; Checklist 198. Hazardous Waste Management March 13, 2002...

  2. 78 FR 15338 - New York: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-03-11

    ... authorization of changes to its hazardous waste program under the Solid Waste Disposal Act, as amended, commonly... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R02-RCRA-2013-0144; FRL-9693-3] New York: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental...

  3. 75 FR 81187 - South Dakota: Final Authorization of State Hazardous Waste Management Program Revision

    Science.gov (United States)

    2010-12-27

    ...: Final Authorization of State Hazardous Waste Management Program Revision AGENCY: Environmental Protection Agency (EPA). ACTION: Proposed Rule. SUMMARY: The Solid Waste Disposal Act, as amended, commonly... Agency (EPA) to authorize states to operate their hazardous waste management programs in lieu of the...

  4. 77 FR 47797 - Arkansas: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-08-10

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R06-RCRA-2010-0307; FRL-9713-2] Arkansas: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act...

  5. 76 FR 19004 - Oklahoma: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2011-04-06

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R06-RCRA-2010-0307; FRL-9290-9] Oklahoma: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act...

  6. 78 FR 32223 - Oklahoma: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-05-29

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R06-RCRA-2012-0821; 9817-5] Oklahoma: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental Protection Agency (EPA... changes to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA). EPA...

  7. 77 FR 38566 - Louisiana: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-06-28

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA--R06-RCRA-2012-0367; FRL-9692-6] Louisiana: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act...

  8. 78 FR 54200 - Virginia: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-09-03

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R03-RCRA-2012-0294; FRL-9900-37-Region3] Virginia: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... of revisions to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA...

  9. 78 FR 25579 - Georgia: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2013-05-02

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... adopted these requirements by reference at Georgia Hazardous Waste Management Rule 391-3-11-.07(1), EPA... authorization of changes to its hazardous waste program under the Resource Conservation and Recovery Act (RCRA...

  10. 76 FR 37048 - Louisiana; Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2011-06-24

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R06-RCRA-2010-0307; FRL-9323-8] Louisiana; Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act...

  11. 77 FR 15343 - Oklahoma: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2012-03-15

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 271 [EPA-R06-RCRA-2012-0054; FRL-9647-8] Oklahoma: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act...

  12. 76 FR 6564 - Florida: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2011-02-07

    ... hazardous pharmaceutical waste to the list of wastes that may be managed under the Universal Waste rule...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental... authorization of the changes to its hazardous waste program under the Resource Conservation and Recovery Act...

  13. Material testing facilities and programs for plasma-facing component testing

    Science.gov (United States)

    Linsmeier, Ch.; Unterberg, B.; Coenen, J. W.; Doerner, R. P.; Greuner, H.; Kreter, A.; Linke, J.; Maier, H.

    2017-09-01

    Component development for operation in a large-scale fusion device requires thorough testing and qualification for the intended operational conditions. In particular environments are necessary which are comparable to the real operation conditions, allowing at the same time for in situ/in vacuo diagnostics and flexible operation, even beyond design limits during the testing. Various electron and neutral particle devices provide the capabilities for high heat load tests, suited for material samples and components from lab-scale dimensions up to full-size parts, containing toxic materials like beryllium, and being activated by neutron irradiation. To simulate the conditions specific to a fusion plasma both at the first wall and in the divertor of fusion devices, linear plasma devices allow for a test of erosion and hydrogen isotope recycling behavior under well-defined and controlled conditions. Finally, the complex conditions in a fusion device (including the effects caused by magnetic fields) are exploited for component and material tests by exposing test mock-ups or material samples to a fusion plasma by manipulator systems. They allow for easy exchange of test pieces in a tokamak or stellarator device, without opening the vessel. Such a chain of test devices and qualification procedures is required for the development of plasma-facing components which then can be successfully operated in future fusion power devices. The various available as well as newly planned devices and test stands, together with their specific capabilities, are presented in this manuscript. Results from experimental programs on test facilities illustrate their significance for the qualification of plasma-facing materials and components. An extended set of references provides access to the current status of material and component testing capabilities in the international fusion programs.

  14. Pioneer Robot Testing Program and Status

    International Nuclear Information System (INIS)

    Herndon, J.N.

    2001-01-01

    The U.S. Department of Energy (USDOE) and Ukraine established a joint program in 1997 to address the need for remotely operated systems for unstructured environments in Ukraine such as the highly hazardous conditions inside the failed Chernobyl Nuclear Power Plant (ChNPP) Unit 4, or Shelter Object. The environment inside Shelter Object is extremely hazardous due to ionizing radiation fields, high airborne contamination, and major industrial safety issues. Although Ukrainian workers have explored and mapped much of the internals of Unit 4 in the time since the accident during the morning hours of April 26, 1986, there remain areas where humans have not entered to this date. Based on the agreement between USDOE and Ukraine, the USDOE, in cooperation with the U.S. National Aeronautics and Space Administration (NASA), developed the Pioneer Robot and has provided it to the ChNPP within the framework of international technical assistance. Pioneer is capable of mobile platform movement and manipulation under teleoperated control, 3-dimensional mapping, and environmental data collection. The Pioneer is radiation hardened for conditions like those of Shelter Object. Pioneer has been evaluated on site in Ukraine for use in both the Shelter Object environment and the more general conditions of ChNPP decommissioning. This paper summarizes the results of these testing activities and describes the status and near-term activities in support of the Pioneer Robot integration into Ukraine

  15. Final design of the neutral beam lines for the Tokamak Fusion Test Reactor

    International Nuclear Information System (INIS)

    Pittenger, L.C.; Valby, L.E.; Stone, R.R.; Pedrotti, L.R.; Denhoy, B.; Yoard, R.

    1979-01-01

    Final design of the neutral beam lines for TFTR has been completed. A prototype has been assembled at Lawrence Berkeley Laboratory and is undergoing testing as part of the Neutral Beam System Test Facility (NBSTF). The final neutral beam line (NBL) configuration differs in several details from that previously reported upon; certain components have been added; and testing of the cryopump system has led to some design simplification. It is these developments which are reported herein

  16. Computer-aided dispatch--traffic management center field operational test final detailed test plan : WSDOT deployment

    Science.gov (United States)

    2003-10-01

    The purpose of this document is to expand upon the evaluation components presented in "Computer-aided dispatch--traffic management center field operational test final evaluation plan : WSDOT deployment". This document defines the objective, approach,...

  17. Computer-aided dispatch--traffic management center field operational test final test plans : state of Utah

    Science.gov (United States)

    2004-01-01

    The purpose of this document is to expand upon the evaluation components presented in "Computer-aided dispatch--traffic management center field operational test final evaluation plan : state of Utah". This document defines the objective, approach, an...

  18. Preliminary irradiation test results from the Yankee Atomic Electric Company reactor vessel test irradiation program

    International Nuclear Information System (INIS)

    Biemiller, E.C.; Fyfitch, S.; Campbell, C.A.

    1993-01-01

    The Yankee Atomic Electric Company test irradiation program was implemented to characterize the irradiation response of representative Yankee Rowe reactor vessel beltline plate materials and to remove uncertainties in the analysis of existing irradiation data on the Yankee Rowe reactor vessel steel. Plate materials each containing 0.24 w/o copper, but different nickel contents at 0.63 w/o and 0.19 w/o, were heat treated to simulate the Yankee vessel heat treatment (austenitized at 1800 deg F) and to simulate Regulatory Guide 1.99 database materials (austenitized at 1600 deg. F). These heat treatments produced different microstructures so the effect of microstructure on irradiation damage sensitivity could be tested. Because the nickel content of the test plates varied and the copper level was constant, the effect of nickel on irradiation embrittlement was also tested. Correlation monitor material, HSST-02, was included in the program to benchmark the Ford Nuclear Reactor (U. of Michigan Test Reactor) which had never been used for this type of irradiation program. Materials taken from plate surface locations (vs. 1/4T) were included to test whether or not the improved toughness properties of the plate surface layer, resulting from the rapid quench, is maintained after irradiation. If the improved properties are maintained, pressurized thermal shock calculations could utilize this margin. Finally, for one experiment, irradiations were conducted at two irradiation temperatures (500 deg. F and 550 deg. F) to determine the effect of irradiation temperature on embrittlement. The preliminary results of the irradiation program show an increase in T 30 shift of 69 deg. F for a decrease in irradiation temperature of 50 deg. F. The results suggest that for nickel bearing steels, the superior toughness of plate surface material is maintained after irradiation and for the copper content tested, nickel had no apparent effect on irradiation response. No apparent microstructure

  19. The RERTR [Reduced Enrichment Research and Test Reactor] program:

    International Nuclear Information System (INIS)

    Travelli, A.

    1987-01-01

    The progress of the Reduced Enrichment Research and Test Reactor (RERTR) program is described. After a brief summary of the results which the RERTR program, in collaboration with its many international partners, had achieved by the end of 1986, the activities, results and new developments which ocurred in 1987 are reviewed. Irradiation of the second miniplate series, concentrating on U 3 Si 2 -Al and U 3 Si-Al fuels was completed and postirradiation examinations were performed on many of its miniplates. The whole-core ORR demonstration with U 3 Si 2 -Al fuel at 4.8 g U/cm 3 was completed at the end of March with excellent results and with 29 elements estimated to have reached at least 40 % average burnup. Good progress was made in the area of LEU usage for the production of fission 99 Mo, and in the coordination of safety evaluations related to LEU conversions of U.S. university reactors. Planned activities include testing and demonstrating advanced fuels intended to allow use of reduced enrichment uranium in very-high-performance reactors. Two candidate fuels are U 3 Si-Al with 19.75 % enrichment and U 3 Si 2 -Al with 45 % enrichment. Demonstration of these fuels will include irradiation of full-size elements and, possibly, a full-core demonstration. Achievement of the final program goals is still projected for 1990. This progress could not have been possible without the close international cooperation which has existed from the beginning, and which is essential to the ultimate success of the RERTR program. (Author)

  20. Preliminary irradiation test results from the Yankee Atomic Electric Company reactor vessel test irradiation program

    International Nuclear Information System (INIS)

    Biemiller, E.C.; Fyfitch, Stephen; Campbell, C.A.

    1994-01-01

    The Yankee Atomic Electric Company test irradiation program was implemented to characterize the irradiation response of representative Yankee Rowe reactor vessel beltline plate materials and to remove uncertainties in the analysis of existing irradiation data on the Yankee Rowe reactor vessel steel. Plate materials each containing 0.24 w/o copper, but different nickel contents at 0.63 w/o and 0.19 w/o, were heat treated to simulate the Yankee vessel heat treatment (austenitized at 982 o C (1800 o F)) and to simulate Regulatory Guide 1.99 database materials (austenitized at 871 o C (1600 o F)). These heat treatments produced different microstructures so the effect of microstructure on irradiation damage sensitivity could be tested. Because the nickel content of the test plates varied and the copper level was constant, the effect of nickel on irradiation embrittlement was also tested. Correlation monitor material, HSST-02, was included in the program to benchmark the Ford Nuclear Reactor (University of Michigan Test Reactor) which had never been used before for this type of irradiation program. Materials taken from plate surface locations (versus 1/4 T) were included to test whether or not the improved toughness properties of the plate surface layer, resulting from the rapid quench, are maintained after irradiation. If the improved properties are maintained, pressurized thermal shock calculations could utilize this margin. Finally, for one experiment, irradiations were conducted at two irradiation temperatures (260 o C and 288 o C) to determine the effect of irradiation temperature on embrittlement. (Author)

  1. WIPP [Waste Isolation Pilot Plant]/SRL in situ tests: Part 2, Pictorial history of MIIT [Materials Interface Interactions Tests] and final MIIT matrices, assemblies, and sample listings

    International Nuclear Information System (INIS)

    Wicks, G.G.; Weinle, M.E.; Molecke, M.A.

    1987-01-01

    In situ testing of Savannah River Plant [SRP] waste glass is an important component in ensuring technical and public confidence in the safety and effective performance of the wasteforms. Savannah River Laboratory [SRL] is currently involved in joint programs involving field testing of SRP waste in Sweden, Belgium, and the United Kingdom. Most recently, this in situ effort has been expanded to include the first field tests to be conducted in the United States, involving burial of a variety of simulated nuclear waste systems. This new effort, called the Materials Interface Interactions Tests or MIIT, is a program jointly conducted by Sandia National Laboratory/Waste Isolation Pilot Plant [WIPP] and SRL. Over 1800 samples, supplied by the United States, France, West Germany, Belgium, Canada, Japan, and the United Kingdom, were buried approximately 650m below the earth's surface in the salt geology at WIPP, near Carlsbad, New Mexico. The MIIT program is one of the largest cooperative efforts ever undertaken in the waste management field; the data produced from these tests are designed to benefit a wide cross-section of the waste management community. An earlier document provided an overview of the WIPP MIIT program and described its place in the waste glass assessment program at Savannah River. This document represents the second in this series and its objectives include: (1) providing a pictorial history of assembly and installation of wasteforms, metals, and geologic samples in WIPP; (2) providing 'finalized and completed' sample matrices for the entire 7-part MIIT program; (3) documenting final sample assemblies by the use of schematic drawings, including each sample, its orientation, and its environment; and (4) providing a complete listing of all samples and the means for managing analyses and resulting data

  2. Site operator program final report for fiscal years 1992 through 1996

    Energy Technology Data Exchange (ETDEWEB)

    Francfort, J.E. [Lockheed Martin Idaho Technologies Co., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.; Bassett, R.R. [Sandia National Labs., Albuquerque, NM (United States); Birasco, S. [Los Angeles Dept. of Water and Power, CA (United States)] [and others

    1998-01-01

    The Site Operator Program was an electric vehicle testing and evaluation program sponsored by US Department of Energy and managed at the Idaho National Engineering and Environmental Laboratory. The Program`s goals included the field evaluation of electric vehicles in real-world applications and environments; the support of electric vehicle technology advancement; the development of infrastructure elements necessary to support significant electric vehicle use; and increasing the awareness and acceptance of electric vehicles. This report covers Program activities from 1992 to 1996. The Site Operator Program ended in September 1996, when it was superseded by the Field Operations Program. Electric vehicle testing included baseline performance testing, which was performed in conjunction with EV America. The baseline performance parameters included acceleration, braking, range, energy efficiency, and charging time. The Program collected fleet operations data on electric vehicles operated by the Program`s thirteen partners, comprising electric utilities, universities, and federal agencies. The Program`s partners had over 250 electric vehicles, from vehicle converters and original equipment manufacturers, in their operating fleets. Test results are available via the World Wide Web site at http://ev.inel.gov/sop.

  3. Using Virtual ATE Model to Migrate Test Programs

    Institute of Scientific and Technical Information of China (English)

    王晓明; 杨乔林

    1995-01-01

    Bacause of high development costs of IC (Integrated Circuit)test programs,recycling existing test programs from one kind of ATE (Automatic Test Equipment) to another or generating directly from CAD simulation modules to ATE is more and more valuable.In this paper,a new approach to migrating test programs is presented.A virtual ATE model based on object-oriented paradigm is developed;it runs Test C++ (an intermediate test control language) programs and TeIF(Test Inftermediate Format-an intermediate pattern),migrates test programs among three kinds of ATE (Ando DIC8032,Schlumberger S15 and GenRad 1732) and generates test patterns from two kinds of CAD 9Daisy and Panda) automatically.

  4. Computer-aided dispatch--traffic management center field operational test : state of Utah final report

    Science.gov (United States)

    2006-07-01

    This document provides the final report for the evaluation of the USDOT-sponsored Computer-Aided Dispatch Traffic Management Center Integration Field Operations Test in the State of Utah. The document discusses evaluation findings in the followin...

  5. Computer-aided dispatch--traffic management center field operational test : Washington State final report

    Science.gov (United States)

    2006-05-01

    This document provides the final report for the evaluation of the USDOT-sponsored Computer-Aided Dispatch - Traffic Management Center Integration Field Operations Test in the State of Washington. The document discusses evaluation findings in the foll...

  6. Alternative filtration testing program: Pre-evaluation of test results

    International Nuclear Information System (INIS)

    Georgeton, G.K.; Poirier, M.R.

    1990-01-01

    Based on results of testing eight solids removal technologies and one pretreatment option, it is recommended that a centrifugal ultrafilter and polymeric ultrafilter undergo further testing as possible alternatives to the Norton Ceramic filters. Deep bed filtration should be considered as a third alternative, if a backwashable cartridge filter is shown to be inefficient in separate testing

  7. Alternative filtration testing program: Pre-evaluation of test results

    Energy Technology Data Exchange (ETDEWEB)

    Georgeton, G.K.; Poirier, M.R.

    1990-09-28

    Based on results of testing eight solids removal technologies and one pretreatment option, it is recommended that a centrifugal ultrafilter and polymeric ultrafilter undergo further testing as possible alternatives to the Norton Ceramic filters. Deep bed filtration should be considered as a third alternative, if a backwashable cartridge filter is shown to be inefficient in separate testing.

  8. Program for analyzing power boost tests

    International Nuclear Information System (INIS)

    Wills, C.A.

    1982-03-01

    A rapid increase of power in a reactor produces a failure in the fuel. Experiments to study the conditions in the NRU reactor after such failures have been planned and carried out. Given the concentrations of specified isotopes at a number of times over the length of an experiment as produced for example, from the program SARGS and the power history of the reactor, this program calculates the release rates, escape rate coefficients, and fractional releases for the isotopes. These values may be optionally printed and plotted. Decay schemes for a limited number of mass numbers are implemented. The program is written in FORTRAN and runs on the CDC 6600 - CYBER 170 system

  9. Definition study of a Variable Cycle Experimental Engine (VCEE) and associated test program and test plan

    Science.gov (United States)

    Allan, R. D.

    1978-01-01

    The Definition Study of a Variable Cycle Experimental Engine (VCEE) and Associated Test Program and Test Plan, was initiated to identify the most cost effective program for a follow-on to the AST Test Bed Program. The VCEE Study defined various subscale VCE's based on different available core engine components, and a full scale VCEE utilizing current technology. The cycles were selected, preliminary design accomplished and program plans and engineering costs developed for several program options. In addition to the VCEE program plans and options, a limited effort was applied to identifying programs that could logically be accomplished on the AST Test Bed Program VCE to extend the usefulness of this test hardware. Component programs were provided that could be accomplished prior to the start of a VCEE program.

  10. Progeria Research Foundation Diagnostic Testing Program

    Science.gov (United States)

    ... Share the DVD Meet the Kids in the Movie Bring LATS to the classroom! Close News/Events ... this could severely affect their research results and interpretation. Through the PRF Diagnostics Program, each cell line ...

  11. Towards a Theory for Testing Non-terminating Programs

    DEFF Research Database (Denmark)

    Gotlieb, Arnaud; Petit, Matthieu

    2009-01-01

    Non-terminating programs are programs that legally perform unbounded computations. Though they are ubiquitous in real-world applications, testing these programs requires new theoretic developments as usual definitions of test data adequacy criteria ignore infinite paths. This paper develops...... a theory of program-based structural testing based on operational semantics. Reasoning at the program semantics level permits to cope with infinite paths (and non-feasible paths) when defining test data adequacy criteria. As a result, our criteria respect the first Weyuker’s property on finite...... applicability, even for non-terminating programs. We discuss the consequences of this re-interpretation of test data adequacy criteria w.r.t. existing test coverage criteria....

  12. Program evaluation: Weatherization Residential Assistance Partnership (WRAP) Program. Volume 1, Final report

    Energy Technology Data Exchange (ETDEWEB)

    1991-12-01

    The Connecticut low income weatherization program was developed in response to a 1987 rate docket order from the Connecticut Department of Public Utility Control (DPUC) to Connecticut Light & Power Co., an operating subsidiary of Northeast Utilities (NU). (Throughout this report, NU is referred to as the operator of the program.) This program, known as the Weatherization Residential Assistance Partnership, or WRAP, was configured utilizing input from a collaborative group of interested parties to the docket. It was agreed that this program would be put forth by the electric utility, but would not ignore oil and gas savings (thus, it was to be ``fuel- blind``). The allocated cost of conservation services for each fuel source, however, should be cost effective. It was to be offered to those utility customers at or below 200 percent of the federal poverty levels, and provide a wide array of energy saving measures directed toward heating, water heating and lighting. It was felt by the collaborative group that this program would raise the level of expenditures per participant for weatherization services provided by the state, and by linking to and revising the auditing process for weatherization, would lower the audit unit cost. The program plans ranged from the offering of low-cost heating, water heating and infiltration measures, increased insulation levels, carpentry and plumbing services, to furnace or burner replacement. The program was configured to allow for very comprehensive weatherization and heating system servicing.

  13. Small machine tools for small workpieces final report of the DFG priority program 1476

    CERN Document Server

    Sanders, Adam

    2017-01-01

    This contributed volume presents the research results of the program “Small machine tools for small work pieces” (SPP 1476), funded by the German Research Society (DFG). The book contains the final report of the priority program, presenting novel approached for size-adapted, reconfigurable micro machine tools. The target audience primarily comprises research experts and practitioners in the field of micro machine tools, but the book may also be beneficial for graduate students.

  14. Test plan: Potash Core Test. WIPP experimental program borehole plugging

    International Nuclear Information System (INIS)

    Christensen, C.L.

    1979-09-01

    The Potash Core Test will utilize a WIPP emplaced plug to obtain samples of an in-situ cured plug of known mix constituents for bench scale testing. An earlier effort involved recovery at the salt horizon of Plug 217, a 17 year old plug in a potash exploration hole for bond testing, but the lack of particulars in the emplacement precluded significant determination of plug performance

  15. GPHS-RTGs in support of the Cassini RTG Program. Final technical report, January 11, 1991 - April 30, 1998

    International Nuclear Information System (INIS)

    1998-08-01

    As noted in the historical summary, this program encountered a number of changes in direction, schedule, and scope over the period 11 January 1991 to 31 December 1998. The report provides a comprehensive summary of all the varied aspects of the program over its seven and a quarter years, and highlights those aspects that provide information beneficial to future radioisotope programs. In addition to summarizing the scope of the Cassini GPHS-RTG Program provided as background, the introduction includes a discussion of the scope of the final report and offers reference sources for information on those topics not covered. Much of the design heritage of the GPHS-RTG comes from the Multi-Hundred Watt (MHW) RTGs used on the Lincoln Experimental Satellites (LES) 8/9 and Voyager spacecraft. The design utilized for the Cassini program was developed, in large part, under the GPHS-RTG program which produced the Galileo and Ulysses RTGs. Reports from those programs included detailed documentation of the design, development, and testing of converter components and full converters that were identical to, or similar to, components used in the Cassini program. Where such information is available in previous reports, it is not repeated here

  16. GPHS-RTGs in support of the Cassini RTG Program. Final technical report, January 11, 1991--April 30, 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-08-01

    As noted in the historical summary, this program encountered a number of changes in direction, schedule, and scope over the period 11 January 1991 to 31 December 1998. The report provides a comprehensive summary of all the varied aspects of the program over its seven and a quarter years, and highlights those aspects that provide information beneficial to future radioisotope programs. In addition to summarizing the scope of the Cassini GPHS-RTG Program provided as background, the introduction includes a discussion of the scope of the final report and offers reference sources for information on those topics not covered. Much of the design heritage of the GPHS-RTG comes from the Multi-Hundred Watt (MHW) RTGs used on the Lincoln Experimental Satellites (LES) 8/9 and Voyager spacecraft. The design utilized for the Cassini program was developed, in large part, under the GPHS-RTG program which produced the Galileo and Ulysses RTGs. Reports from those programs included detailed documentation of the design, development, and testing of converter components and full converters that were identical to, or similar to, components used in the Cassini program. Where such information is available in previous reports, it is not repeated here.

  17. Summer Research Program - 1998 High School Apprenticeship Program Final Reports. Volume 12, Armstrong Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1998-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  18. USAF Summer Research Program - 1995 High School Apprenticeship Program Final Reports, Volume 14, Rome Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1995-01-01

    The United States Air Force High School Apprenticeship Program's (USAF HSAP) purpose is to place outstanding high school students whose interests are in the areas of mathematics, engineering, and science to work in a laboratory environment...

  19. Summer Research Program - 1997. High School Apprenticeship Program. Final Reports, Volume 12A, Armstrong Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1997-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  20. Summer Research Program - 1997. High School Apprenticeship Program. Final Reports Volume 15B, Wright Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1997-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  1. Summer Research Program - 1996. High School Apprenticeship Program Final Reports. Volume 15B, Wright Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1996-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  2. 1997 Summer Research Program (SRP), High School Apprenticeship Program (HSAP), Final Reports, Volume 13, Phillips Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1997-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  3. Summer Research Program - 1997. High School Apprenticeship Program Final Reports. Volume 15A, Wright Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1997-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  4. Summer Research Program - 1997. High School Apprenticeship Program. Final Reports. Volume 15C, Wright Laboratory

    National Research Council Canada - National Science Library

    Moore, Gary

    1997-01-01

    The United States Air Force Summer Research Program (USAF-SRP) is designed to introduce university, college, and technical institute faculty members, graduate students, and high school students to Air Force research...

  5. Final report for the 1996 Engineer Starters Program (Pre-Freshmen Enrichment Program)

    Energy Technology Data Exchange (ETDEWEB)

    Sharpe, L. Jr.

    1996-08-15

    This report has been developed for the North Carolina Agricultural and Technical State University College of Engineering, Department of Energy and other foundations/corporations sponsoring the 1996 Engineer Starters Program and for general information. The College of Engineering conducted its Annual outreach program for Middle and High School students from July 8 to August 2, 1996. The continuing primary goal of this program is to expose youth to the various challenging opportunities in the Mathematics and Science based careers, Engineering and Technology. The curriculum for the summer of 1996 included: Mathematics; Science; Computers; Graphics; Problem Solving; Career Explorations; Communications; Field Trips to Manufacturing Plants/Industries; and Engineering Projects/Designs. The 1996 program included rising seventh through tenth graders. Parental involvement was instituted as a vital component of the summer experiences. The primary objective is to increase the number of minorities entering engineering and science professions.

  6. OECD/MCCI 2-D Core Concrete Interaction (CCI) tests : final report February 28, 2006.

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-05-23

    reactor material database for dry cavity conditions is solely one-dimensional. Although the MACE Scoping Test was carried out with a two-dimensional concrete cavity, the interaction was flooded soon after ablation was initiated to investigate debris coolability. Moreover, due to the scoping nature of this test, the apparatus was minimally instrumented and therefore the results are of limited value from the code validation viewpoint. Aside from the MACE program, the COTELS test series also investigated 2-D CCI under flooded cavity conditions. However, the input power density for these tests was quite high relative to the prototypic case. Finally, the BETA test series provided valuable data on 2-D core concrete interaction under dry cavity conditions, but these tests focused on investigating the interaction of the metallic (steel) phase with concrete. Due to these limitations, there is significant uncertainty in the partition of energy dissipated for the ablation of concrete in the lateral and axial directions under dry cavity conditions for the case of a core oxide melt. Accurate knowledge of this 'power split' is important in the evaluation of the consequences of an ex-vessel severe accident; e.g., lateral erosion can undermine containment structures, while axial erosion can penetrate the basemat, leading to ground contamination and/or possible containment bypass. As a result of this uncertainty, there are still substantial differences among computer codes in the prediction of 2-D cavity erosion behavior under both wet and dry cavity conditions. In light of the above issues, the OECD-sponsored Melt Coolability and Concrete Interaction (MCCI) program was initiated at Argonne National Laboratory. The project conducted reactor materials experiments and associated analysis to achieve the following technical objectives: (1) resolve the ex-vessel debris coolability issue through a program that focused on providing both confirmatory evidence and test data for the

  7. Nye County, Nevada 1992 nuclear waste repository program: Program overview. Final report

    International Nuclear Information System (INIS)

    1998-01-01

    The purpose of this document is to provide an overview of the Nye County FY92 Nuclear Waste Repository Program (Program). Funds to pay for Program costs will come from the Federal Nuclear Waste Fund, which was established under the Nuclear Waste Policy Act of 1982 (NWPA). In early 1983, the Yucca Mountain was identified as a potentially suitable site for the nation's first geologic repository for spent reactor fuel and high-level radioactive waste. Later that year, the Nye County Board of County Commissioners (Board) established the capability to monitor the Federal effort to implement the NWPA and evaluate the potential impacts of repository-related activities on Nye County. Over the last eight years, the County's program has grown in complexity and cost in order to address DOE's evolving site characterization studies, and prepare for the potential for facility construction and operation. Changes were necessary as well, in response to Congress's redirection of the repository program specified in the amendments, to the NWPA approved in 1987. In early FY 1991, the County formally established a project office to plan and implement its program of work. The Repository Project Office's (RPO) mission and functions are provided in Section 2.0. The RPO organization structure is described in Section 3.0

  8. Federal Employees Health Benefits Program and Federal Employees Dental and Vision Insurance Program: eligibility for Pathway Programs participants. Interim final rule with request for comments.

    Science.gov (United States)

    2014-01-06

    The U.S. Office of Personnel Management (OPM) is issuing an interim final regulation to update the Federal Employees Health Benefits Program (FEHBP) and the Federal Employees Dental and Vision Insurance Program (FEDVIP) regulations to reflect updated election opportunities for participants in the Pathways Programs. The Pathways Programs were created by Executive Order (E.O.) 13562, signed by the President on December 27, 2010, and are designed to enable the Federal Government to compete effectively for students and recent graduates by improving its recruitment efforts through internships and similar programs with Federal agencies. This interim final rule furthers these recruitment and retention efforts by providing health insurance, as well as dental and vision benefits, to eligible program participants and their families.

  9. AGR-2 Irradiation Test Final As-Run Report, Rev 2

    Energy Technology Data Exchange (ETDEWEB)

    Collin, Blaise P. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2014-08-01

    This document presents the as-run analysis of the AGR-2 irradiation experiment. AGR-2 is the second of the planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the U.S. Department of Energy as part of the Very High Temperature Reactor (VHTR) Technical Development Office (TDO) program. The objectives of the AGR-2 experiment are to: (a) Irradiate UCO (uranium oxycarbide) and UO2 (uranium dioxide) fuel produced in a large coater. Fuel attributes are based on results obtained from the AGR-1 test and other project activities. (b) Provide irradiated fuel samples for post-irradiation experiment (PIE) and safety testing. (c) Support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. The primary objective of the test was to irradiate both UCO and UO2 TRISO (tri-structural isotropic) fuel produced from prototypic scale equipment to obtain normal operation and accident condition fuel performance data. The UCO compacts were subjected to a range of burnups and temperatures typical of anticipated prismatic reactor service conditions in three capsules. The test train also includes compacts containing UO2 particles produced independently by the United States, South Africa, and France in three separate capsules. The range of burnups and temperatures in these capsules were typical of anticipated pebble bed reactor service conditions. The results discussed in this report pertain only to U.S. produced fuel. In order to achieve the test objectives, the AGR-2 experiment was irradiated in the B-12 position of the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) for a total irradiation duration of 559.2 effective full power days (EFPD). Irradiation began on June 22, 2010, and ended on October 16, 2013, spanning 12 ATR power cycles and approximately three and a

  10. AGR-2 irradiation test final as-run report, Rev. 1

    International Nuclear Information System (INIS)

    2014-01-01

    This document presents the as-run analysis of the AGR-2 irradiation experiment. AGR-2 is the second of the planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the U.S. Department of Energy as part of the Very High Temperature Reactor (VHTR) Technical Development Office (TDO) program. The objectives of the AGR-2 experiment are to: (a) Irradiate UCO (uranium oxycarbide) and UO 2 (uranium dioxide) fuel produced in a large coater. Fuel attributes are based on results obtained from the AGR-1 test and other project activities; (b) Provide irradiated fuel samples for post-irradiation experiment (PIE) and safety testing; and, (c) Support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. The primary objective of the test was to irradiate both UCO and UO 2 TRISO (tri-structural isotropic) fuel produced from prototypic scale equipment to obtain normal operation and accident condition fuel performance data. The UCO compacts were subjected to a range of burnups and temperatures typical of anticipated prismatic reactor service conditions in three capsules. The test train also includes compacts containing UO 2 particles produced independently by the United States, South Africa, and France in three separate capsules. The range of burnups and temperatures in these capsules were typical of anticipated pebble bed reactor service conditions. The results discussed in this report pertain only to U.S. produced fuel. In order to achieve the test objectives, the AGR-2 experiment was irradiated in the B-12 position of the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) for a total irradiation duration of 559.2 effective full power days (EFPD). Irradiation began on June 22, 2010, and ended on October 16, 2013, spanning 12 ATR power cycles and approximately three and a half calendar years. The

  11. CIT photoheliograph functional verification unit test program

    Science.gov (United States)

    1973-01-01

    Tests of the 2/3-meter photoheliograph functional verification unit FVU were performed with the FVU installed in its Big Bear Solar Observatory vacuum chamber. Interferometric tests were run both in Newtonian (f/3.85) and Gregorian (f/50) configurations. Tests were run in both configurations with optical axis horizontal, vertical, and at 45 deg to attempt to determine any gravity effects on the system. Gravity effects, if present, were masked by scatter in the data associated with the system wavefront error of 0.16 lambda rms ( = 6328A) apparently due to problems in the primary mirror. Tests showed that the redesigned secondary mirror assembly works well.

  12. 75 FR 43478 - Rhode Island: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2010-07-26

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental.... Mail: Robin Biscaia, RCRA Waste Management Section, Office of Site Remediation and Restoration (OSRR 07... Delivery or Courier: Deliver your comments to: Robin Biscaia, RCRA Waste Management Section, Office of Site...

  13. Facebook and the Final Practicum: The Impact of Online Peer Support in the Assistant Teacher Program

    Science.gov (United States)

    Paris, Lisa F.; Boston, Julie; Morris, Julia

    2015-01-01

    Australian pre-service teachers (PST) frequently report feeling isolated and vulnerable during the high stakes Assistant Teacher Program (ATP) final practicum. Mentoring and online learning communities have been shown to offer effective support during periods in which pre-service and beginning teachers feel challenged. As social media…

  14. 75 FR 35720 - Massachusetts: Final Authorization of State Hazardous Waste Management Program Revisions

    Science.gov (United States)

    2010-06-23

    ...: Final Authorization of State Hazardous Waste Management Program Revisions AGENCY: Environmental...: Robin Biscaia, RCRA Waste Management Section, Office of Site Remediation and Restoration (OSRR 07-1... Courier: Deliver your comments to: Robin Biscaia, RCRA Waste Management Section, Office of Site...

  15. Final summary report of the Nordic Nuclear Safety Research Program 1994 - 1997

    International Nuclear Information System (INIS)

    Bennerstedt, T.; Lemmens, A.

    1999-11-01

    This is a summary report of the NKS research program carried out 1994 - 1997. It is basically a compilation of the executive summaries of the final reports on the nine scientific projects carried out during that period. It highlights the conclusions, recommendations and other results of the projects. (au)

  16. 77 FR 43290 - Children's Health Insurance Program (CHIP); Final Allotments to States, the District of Columbia...

    Science.gov (United States)

    2012-07-24

    ... 0938-AR45 Children's Health Insurance Program (CHIP); Final Allotments to States, the District of... and expand health insurance coverage to uninsured, low-income children under the Children's Health... under title XXI of the Social Security Act (the Act). States may implement Children's Health Insurance...

  17. 77 FR 35953 - Arts in Education National Program; Final Priority, Requirements, Definitions, and Selection...

    Science.gov (United States)

    2012-06-15

    ..., standards-based teaching that is unique to music education. The commenter added that it would be beneficial... DEPARTMENT OF EDUCATION [CFDA Number 84.351F] Arts in Education National Program; Final Priority... Education. ACTION: Notice. SUMMARY: The Assistant Deputy Secretary for Innovation and Improvement announces...

  18. Final report to DOE: Matching Grant Program for the Penn State University Nuclear Engineering Program

    International Nuclear Information System (INIS)

    Jack S. Brenizer, Jr.

    2003-01-01

    The DOE/Industry Matching Grant Program is designed to encourage collaborative support for nuclear engineering education as well as research between the nation's nuclear industry and the U.S. Department of Energy (DOE). Despite a serious decline in student enrollments in the 1980s and 1990s, the discipline of nuclear engineering remained important to the advancement of the mission goals of DOE. The program is designed to ensure that academic programs in nuclear engineering are maintained and enhanced in universities throughout the U.S. At Penn State, the Matching Grant Program played a critical role in the survival of the Nuclear Engineering degree programs. Funds were used in a variety of ways to support both undergraduate and graduate students directly. Some of these included providing seed funding for new graduate research initiatives, funding the development of new course materials, supporting new teaching facilities, maintenance and purchase of teaching laboratory equipment, and providing undergraduate scholarships, graduate fellowships, and wage payroll positions for students

  19. The UKAEA mechanical test programs in air

    International Nuclear Information System (INIS)

    Wood, D.S.

    1977-01-01

    The design of CDFR will be based on the mechanical behaviour of materials in air, although at a later date account may need to be taken of sodium effects. The need for this Information is outlined in the introductory paper. The extent of the air programs and preliminary findings are described in this paper

  20. The UKAEA mechanical test programs in air

    Energy Technology Data Exchange (ETDEWEB)

    Wood, D S [UKAEA, RNPDL, Risley (United Kingdom)

    1977-07-01

    The design of CDFR will be based on the mechanical behaviour of materials in air, although at a later date account may need to be taken of sodium effects. The need for this Information is outlined in the introductory paper. The extent of the air programs and preliminary findings are described in this paper.

  1. Test of user- and system programs coded in real time languages - requirements on program language and testing tool

    International Nuclear Information System (INIS)

    Hertlin, J.; Mackert, M.

    1979-01-01

    In the present paper the functions are presented, which should be part of a test system for user programs in a higher treat time programming language, taking into account time sequences and competitive processes. As can be shown by the problem of testing, use of higher level real time programming languages renders the task of program development essentially easier, however performance of test procedures without appropriate test systems is very difficult. After the presentation of notions and methods for the testing of programs, general requirements on testing tools are described and the test system functions for a program test, beeing uncritical with respect to time, are placed together. Thereby, for every individual function, the interface between the test system, the program under test, and the residual program-generation system (compiler, binder, operating system, delay-time system, and loader) is given too. For the time-critical test, a series of desirable functions are described, which can be implemented with acceptable expense. (orig.) [de

  2. Final Technical Report. DeepCwind Consortium Research Program. January 15, 2010 - March 31, 2013

    Energy Technology Data Exchange (ETDEWEB)

    Dagher, Habib [Univ. of Maine, Orono, ME (United States); Viselli, Anthony [Univ. of Maine, Orono, ME (United States); Goupee, Andrew [Univ. of Maine, Orono, ME (United States); Thaler, Jeffrey [Univ. of Maine, Orono, ME (United States); Brady, Damian [Univ. of Maine, Orono, ME (United States); Browne, Peter [HDR, Inc., Omaha, NE (United States); Browning, James [Univ. of Colorado, Boulder, CO (United States); Chung, Jade [Univ. of Maine, Orono, ME (United States); Coulling, Alexander [Univ. of Maine, Orono, ME (United States); Deese, Heather [Island Institute, Rockland, ME (United States); Fowler, Matthew [Univ. of Maine, Orono, ME (United States); Holberton, Rebecca [Univ. of Maine, Orono, ME (United States); Anant, Jain [Intertek, Duluth, GA (United States); Jalbert, Dustin [Univ. of Maine, Orono, ME (United States); Johnson, Theresa [Univ. of Maine, Orono, ME (United States); Jonkman, Jason [National Renewable Energy Laboratory, Golden, CO (United States); Karlson, Benjamin [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Kimball, Richard [Maine Maritime Academy, Castine, ME (United States); Koo, Bonjun [Technip, Paris (France); Lackner, Matthew [Univ. of Massachusetts, Amherst, MA (United States); Lambrakos, Kostas [Technip, Paris (France); Lankowski, Matthew [Univ. of Maine, Orono, ME (United States); Leopold, Adrienne [Univ. of Maine, Orono, ME (United States); Lim, Ho-Joon [Technip, Paris (France); Mangum, Linda [Univ. of Maine, Orono, ME (United States); Martin, Heather [Univ. of Maine, Orono, ME (United States); Masciola, Marco [National Renewable Energy Laboratory, Golden, CO (United States); Maynard, Melissa [Univ. of Maine, Orono, ME (United States); McCleave, James [Univ. of Maine, Orono, ME (United States); Mizrahi, Robert [New Jersey Audubon Society, Bernardsville, NJ (United States); Molta, Paul [National Renewable Energy Laboratory, Golden, CO (United States); Pershing, Andrew [Gulf of Maine Research Institute, Portland, ME (United States); Pettigrew, Neal [Univ. of Maine, Orono, ME (United States); Prowell, Ian [MMI Engineering, Oakland, CA (United States); Qua, Andrew [Kleinschmidt Associates, Pittsfield, ME (United States); Sherwood, Graham [Gulf of Maine Research Institute, Portland, ME (United States); Snape, Thomas [Univ. of Maine, Orono, ME (United States); Steneck, Robert [Univ. of Maine, Orono, ME (United States); Stewart, Gordon [Univ. of Massachusetts, Amherst, MA (United States); Stockwell, Jason [Gulf of Maine Research Institute, Portland, ME (United States); Swift, Andrew H. P. [Texas Tech Univ., Lubbock, TX (United States); Thomas, Dale [Maine Maritime Academy, Castine, ME (United States); Viselli, Elizabeth [Univ. of Maine, Orono, ME (United States); Zydlewski, Gayle [Univ. of Maine, Orono, ME (United States)

    2013-06-11

    This is the final technical report for the U.S. Department of Energy-funded program, DE-0002981: DeepCwind Consortium Research Program. The project objective was the partial validation of coupled models and optimization of materials for offshore wind structures. The United States has a great opportunity to harness an indigenous abundant renewable energy resource: offshore wind. In 2010, the National Renewable Energy Laboratory (NREL) estimated there to be over 4,000 GW of potential offshore wind energy found within 50 nautical miles of the US coastlines (Musial and Ram, 2010). The US Energy Information Administration reported the total annual US electric energy generation in 2010 was 4,120 billion kilowatt-hours (equivalent to 470 GW) (US EIA, 2011), slightly more than 10% of the potential offshore wind resource. In addition, deep water offshore wind is the dominant US ocean energy resource available comprising 75% of the total assessed ocean energy resource as compared to wave and tidal resources (Musial, 2008). Through these assessments it is clear offshore wind can be a major contributor to US energy supplies. The caveat to capturing offshore wind along many parts of the US coast is deep water. Nearly 60%, or 2,450 GW, of the estimated US offshore wind resource is located in water depths of 60 m or more (Musial and Ram, 2010). At water depths over 60 m building fixed offshore wind turbine foundations, such as those found in Europe, is likely economically infeasible (Musial et al., 2006). Therefore floating wind turbine technology is seen as the best option for extracting a majority of the US offshore wind energy resource. Volume 1 - Test Site; Volume 2 - Coupled Models; and Volume 3 - Composite Materials

  3. HANFORD CONTAINERIZED CAST STONE FACILITY TASK 1 PROCESS TESTING & DEVELOPMENT FINAL TEST REPORT

    Energy Technology Data Exchange (ETDEWEB)

    LOCKREM, L L

    2005-07-13

    Laboratory testing and technical evaluation activities on Containerized Cast Stone (CCS) were conducted under the Scope of Work (SOW) contained in CH2M HILL Hanford Group, Inc. (CHG) Contract No. 18548 (CHG 2003a). This report presents the results of testing and demonstration activities discussed in SOW Section 3.1, Task I--''Process Development Testing'', and described in greater detail in the ''Containerized Grout--Phase I Testing and Demonstration Plan'' (CHG, 2003b). CHG (2003b) divided the CCS testing and evaluation activities into six categories, as follows: (1) A short set of tests with simulant to select a preferred dry reagent formulation (DRF), determine allowable liquid addition levels, and confirm the Part 2 test matrix. (2) Waste form performance testing on cast stone made from the preferred DRF and a backup DRF, as selected in Part I, and using low activity waste (LAW) simulant. (3) Waste form performance testing on cast stone made from the preferred DRF using radioactive LAW. (4) Waste form validation testing on a selected nominal cast stone formulation using the preferred DRF and LAW simulant. (5) Engineering evaluations of explosive/toxic gas evolution, including hydrogen, from the cast stone product. (6) Technetium ''getter'' testing with cast stone made with LAW simulant and with radioactive LAW. In addition, nitrate leaching observations were drawn from nitrate leachability data obtained in the course of the Parts 2 and 3 waste form performance testing. The nitrate leachability index results are presented along with other data from the applicable activity categories.

  4. Blood-alcohol proficiency test program

    Science.gov (United States)

    1975-01-01

    A preliminary survey has been performed to ascertain the validity of the blood alcohol analysis performed by a number of laboratories on a voluntary basis. Values of accuracy and precision of the tests are presented. /Abstract from report summary pag...

  5. Accelerated Leach Test(s) Program: Annual report

    International Nuclear Information System (INIS)

    Dougherty, D.R.; Pietrzak, R.F.; Fuhrmann, M.; Colombo, P.

    1986-09-01

    A computerized data base of LLW leaching data has been developed. Long-term tests on portland cement, bitumen and vinyl ester-styrene (VES) polymer waste forms containing simulated wastes are underway which are designed to identify and evaluate factors that accelerate leaching without changing the mechanisms

  6. 77 FR 26607 - Energy Conservation Program: Test Procedures for Electric Motors and Small Electric Motors

    Science.gov (United States)

    2012-05-04

    ... Conservation Program: Test Procedures for Electric Motors and Small Electric Motors; Final Rules #0;#0;Federal... Procedures for Electric Motors and Small Electric Motors AGENCY: Office of Energy Efficiency and Renewable... electric motors and small electric motors. That supplemental proposal, along with an earlier proposal from...

  7. 78 FR 73702 - Federal Travel Regulation (FTR); Telework Travel Expenses Test Programs

    Science.gov (United States)

    2013-12-09

    ...; Docket Number 2013-0012, Sequence 1] RIN 3090-AJ23 Federal Travel Regulation (FTR); Telework Travel...). ACTION: Final rule. SUMMARY: GSA is amending the Federal Travel Regulation (FTR) to incorporate the Telework Enhancement Act of 2010, which establishes and authorizes telework travel expenses test programs...

  8. 77 FR 60318 - Procedures for Transportation Workplace Drug and Alcohol Testing Programs: 6-acetylmorphine (6-AM...

    Science.gov (United States)

    2012-10-03

    ... 2105-AE14 Procedures for Transportation Workplace Drug and Alcohol Testing Programs: 6-acetylmorphine... 12866 and Regulatory Flexibility Act This Final Rule is not significant for purposes of Executive Order... certify, under the Regulatory Flexibility Act, that this rule does not have a significant economic impact...

  9. Hardware test program for evaluation of baseline range/range rate sensor concept

    Science.gov (United States)

    Pernic, E.

    1985-01-01

    The test program Phase II effort provides additional design information in terms of range and range rate (R/R) sensor performance when observing and tracking a typical spacecraft target. The target used in the test program was a one-third scale model of the Hubble Space Telescope (HST) available at the MSFC test site where the tests were performed. A modified Bendix millimeter wave radar served as the R/R sensor test bed for evaluation of range and range rate tracking performance, and generation of radar signature characteristics of the spacecraft target. A summary of program test results and conclusions are presented along with detailed description of the Bendix test bed radar with accompaning instrumentation. The MSFC test site and facilities are described. The test procedures used to establish background levels, and the calibration procedures used in the range accuracy tests and RCS (radar cross section) signature measurements, are presented and a condensed version of the daily log kept during the 5 September through 17 September test period is also presented. The test program results are given starting with the RCS signature measurements, then continuing with range measurement accuracy test results and finally the range and range rate tracking accuracy test results.

  10. Final safety and hazards analysis for the Battelle LOCA simulation tests in the NRU reactor

    International Nuclear Information System (INIS)

    Axford, D.J.; Martin, I.C.; McAuley, S.J.

    1981-04-01

    This is the final safety and hazards report for the proposed Battelle LOCA simulation tests in NRU. A brief description of equipment test design and operating procedure precedes a safety analysis and hazards review of the project. The hazards review addresses potential equipment failures as well as potential for a metal/water reaction and evaluates the consequences. The operation of the tests as proposed does not present an unacceptable risk to the NRU Reactor, CRNL personnel or members of the public. (author)

  11. Medicare program; requirements for the Medicare incentive reward program and provider enrollment. Final rule.

    Science.gov (United States)

    2014-12-05

    This final rule implements various provider enrollment requirements. These include: Expanding the instances in which a felony conviction can serve as a basis for denial or revocation of a provider or supplier's enrollment; if certain criteria are met, enabling us to deny enrollment if the enrolling provider, supplier, or owner thereof had an ownership relationship with a previously enrolled provider or supplier that had a Medicare debt; enabling us to revoke Medicare billing privileges if we determine that the provider or supplier has a pattern or practice of submitting claims that fail to meet Medicare requirements; and limiting the ability of ambulance suppliers to "backbill" for services performed prior to enrollment.

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

    Energy Technology Data Exchange (ETDEWEB)

    BRONOWSKI,DAVID R.

    2000-06-01

    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.

  13. Helping Students Test Programs That Have Graphical User Interfaces

    Directory of Open Access Journals (Sweden)

    Matthew Thornton

    2008-08-01

    Full Text Available Within computer science education, many educators are incorporating software testing activities into regular programming assignments. Tools like JUnit and its relatives make software testing tasks much easier, bringing them into the realm of even introductory students. At the same time, many introductory programming courses are now including graphical interfaces as part of student assignments to improve student interest and engagement. Unfortunately, writing software tests for programs that have significant graphical user interfaces is beyond the skills of typical students (and many educators. This paper presents initial work at combining educationally oriented and open-source tools to create an infrastructure for writing tests for Java programs that have graphical user interfaces. Critically, these tools are intended to be appropriate for introductory (CS1/CS2 student use, and to dovetail with current teaching approaches that incorporate software testing in programming assignments. We also include in our findings our proposed approach to evaluating our techniques.

  14. FINAL REPORT FORMER RADIATION WORKER MEDICAL SURVEILLANCE PROGRAM AT ROCKY FLATS For Department of Energy Programs

    Energy Technology Data Exchange (ETDEWEB)

    Joe M. Aldrich

    2004-11-01

    The Former Radiation Worker Medical Surveillance Program at Rocky Flats was conducted in Arvada, CO, by Oak Ridge Associated Universities through the Oak Ridge Institute for Science and Education under DOE Contract DE-AC05-00OR22750. Objectives of the program were to obtain information on the value of medical surveillance among at-risk former radiation workers and to provide long-term internal radiation dosimetry information to the scientific community. This program provided the former radiation workers of the Rocky Flats Environmental Technology Site (formerly Rocky Flats Plant) an opportunity to receive follow-up medical monitoring and a re-evaluation of their internal radiation dose. The former Rocky Flats radiation worker population is distinctive because it was a reasonably stable work force that received occupational exposures, at times substantial, over several decades. This report reflects the summation of health outcomes, statistical analyses, and dose assessment information on former Rocky Flats radiation workers to the date of study termination as of March 2004.

  15. FINAL REPORT. FORMER RADIATION WORKER MEDICAL SURVEILLANCE PROGRAM AT ROCKY FLATS For Department of Energy Programs

    International Nuclear Information System (INIS)

    Aldrich, Joe M.

    2004-01-01

    The Former Radiation Worker Medical Surveillance Program at Rocky Flats was conducted in Arvada, CO, by Oak Ridge Associated Universities through the Oak Ridge Institute for Science and Education under DOE Contract DE-AC--05-00OR22750. Objectives of the program were to obtain information on the value of medical surveillance among at-risk former radiation workers and to provide long-term internal radiation dosimetry information to the scientific community. This program provided the former radiation workers of the Rocky Flats Environmental Technology Site (formerly Rocky Flats Plant) an opportunity to receive follow-up medical monitoring and a re-evaluation of their internal radiation dose. The former Rocky Flats radiation worker population is distinctive because it was a reasonably stable work force that received occupational exposures, at times substantial, over several decades. This report reflects the summation of health outcomes, statistical analyses, and dose assessment information on former Rocky Flats radiation workers to the date of study termination as of March 2004

  16. Tested program for Third World economic development

    Energy Technology Data Exchange (ETDEWEB)

    Lindholm, R.W.

    1977-04-01

    Some of the responsibility for the inability of Western-oriented Third World Countries (1) to make democratic economic institutions work rests upon advisers to American and international financial institutions who recommend principles of economic growth distilled out of Keynesian recipes for an over-saving Western society of the 1930s, and out of aspects of American experience with no applicability elsewhere. Applicable aspects of U.S. experience suggest a program relying on capitalistic drives and using fiscal and monetary policy of the type that proved useful in the development of democratic capitalism in the U.S. in the 19th century.

  17. Biosphere 2 test module experimentation program

    Science.gov (United States)

    Alling, Abigail; Leigh, Linda S.; Maccallum, Taber; Alvarez-Romo, Norberto

    1990-01-01

    The Biosphere 2 Test Module is a facility which has the capability to do either short or long term closures: five month closures with plants were conducted. Also conducted were investigations of specific problems, such as trace gas purification by bioregenerative systems by in-putting a fixed concentration of a gas and observing its uptake over time. In other Test Module experiments, the concentration of one gas was changed to observe what effects this has on other gases present or on the system. The science of biospherics which encompasses the study of closed biological systems provides an opening into the future in space as well as in the Earth's biosphere.

  18. PBF/LOFT Lead Rod Test Program experiment predictions document

    International Nuclear Information System (INIS)

    Varacalle, D.J.; Cox, W.R.; Niebruegge, D.A.; Seiber, S.J.; Brake, T.E.; Driskell, W.E.; Nigg, D.W.; Tolman, E.L.

    1978-12-01

    The PBF/LOFT Lead Rod (LLR) Test Program is being conducted to provide experimental information on the behavior of nuclear fuel under normal and accident conditions in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory. The PBF/LLR tests are designed to simulate the test conditions for the LOFT Power Ascension Tests L2-3 through L2-5. The test program has been designed to provide a parametric evaluation of the LOFT fuel (center and peripheral modules) over a wide range of power. This report presents the experiment predictions for the three four-rod LOCA tests

  19. Barometric pressure transient testing applications at the Nevada Test Site: formation permeability analysis. Final report

    International Nuclear Information System (INIS)

    Hanson, J.M.

    1984-12-01

    The report evaluates previous investigations of the gas permeability of the rock surrounding emplacement holes at the Nevada Test Site. The discussion sets the framework from which the present uncertainty in gas permeability can be overcome. The usefulness of the barometric pressure testing method has been established. Flow models were used to evaluate barometric pressure transients taken at NTS holes U2fe, U19ac and U20ai. 31 refs., 103 figs., 18 tabs

  20. Next Generation Drivetrain Development and Test Program

    Energy Technology Data Exchange (ETDEWEB)

    Keller, Jonathan; Erdman, Bill; Blodgett, Doug; Halse, Chris; Grider, Dave

    2015-11-03

    This presentation was given at the Wind Energy IQ conference in Bremen, Germany, November 30 through December 2, 2105. It focused on the next-generation drivetrain architecture and drivetrain technology development and testing (including gearbox and inverter software and medium-voltage inverter modules.

  1. Validating High-Stakes Testing Programs.

    Science.gov (United States)

    Kane, Michael

    2002-01-01

    Makes the point that the interpretations and use of high-stakes test scores rely on policy assumptions about what should be taught and the content standards and performance standards that should be applied. The assumptions built into an assessment need to be subjected to scrutiny and criticism if a strong case is to be made for the validity of the…

  2. 75 FR 16072 - Fisheries Finance Program; Final Program Notice and Announcement of Availability of Federal...

    Science.gov (United States)

    2010-03-31

    ...NMFS announces the availability of long-term direct loans made underthe Fisheries Finance Program (FFP). The FFP provides financing for the purchase of used vessels or the reconstruction of vessels (limited to reconstructions that do not add to fishing capacity); refinancing for existing debt obligations; financing or refinancing fisheries shoreside facilities or aquacultural facilities; and the purchase or refinancing of Individual Fishing Quota (IFQ) in the North Pacific. FFP loans are not issued for purposes which could contribute to over capitalization of the fishing industry.

  3. ERDA nuclear energy center program. Phase I. Program definition. Final report

    International Nuclear Information System (INIS)

    1977-06-01

    This Phase I report describes the procedures used and the results obtained from a survey of SINB states and major utilities to determine their interest in participating in an ERDA-sponsored study to investigate the technical, economic, and institutional practicality of establishing a potential Nuclear Energy Center at a specific site. The State of South Carolina was the only SINB member to express positive interest in ERDA's Nuclear Energy Center Program, and to offer to submit a proposal through the SINB to select and evaluate a site in South Carolina having the potential for being developed into a Nuclear Energy Center

  4. AGR-1 Irradiation Test Final As-Run Report, Rev. 3

    Energy Technology Data Exchange (ETDEWEB)

    Collin, Blaise P. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-01-01

    This document presents the as-run analysis of the AGR-1 irradiation experiment. AGR-1 is the first of eight planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the US Department of Energy (DOE) as part of the Next-Generation Nuclear Plant (NGNP) project. The objectives of the AGR-1 experiment are: 1. To gain experience with multi-capsule test train design, fabrication, and operation with the intent to reduce the probability of capsule or test train failure in subsequent irradiation tests. 2. To irradiate fuel produced in conjunction with the AGR fuel process development effort. 3. To provide data that will support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. In order to achieve the test objectives, the AGR-1 experiment was irradiated in the B-10 position of the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL) for a total duration of 620 effective full power days of irradiation. Irradiation began on December 24, 2006 and ended on November 6, 2009 spanning 13 ATR cycles and approximately three calendar years. The test contained six independently controlled and monitored capsules. Each capsule contained 12 compacts of a single type, or variant, of the AGR coated fuel. No fuel particles failed during the AGR-1 irradiation. Final burnup values on a per compact basis ranged from 11.5 to 19.6 %FIMA, while fast fluence values ranged from 2.21 to 4.39 x 1025 n/m2 (E >0.18 MeV). We’ll say something here about temperatures once thermal recalc is done. Thermocouples performed well, failing at a lower rate than expected. At the end of the irradiation, nine of the originally-planned 19 TCs were considered functional. Fission product release-to-birth (R/B) ratios were quite low. In most capsules, R/B values at the end of the irradiation were at or below

  5. PULSE COMBUSTOR DESIGN QUALIFICATION TEST AND CLEAN COAL FEEDSTOCK TEST - VOLUME I AND VOLUME II; FINAL

    International Nuclear Information System (INIS)

    Unknown

    2002-01-01

    For this Cooperative Agreement, the pulse heater module is the technology envelope for an indirectly heated steam reformer. The field of use of the steam reformer pursuant to this Cooperative Agreement with DOE is for the processing of sub-bituminous coals and lignite. The main focus is the mild gasification of such coals for the generation of both fuel gas and char-for the steel industry is the main focus. An alternate market application for the substitution of metallurgical coke is also presented. This project was devoted to qualification of a 253-tube pulse heater module. This module was designed, fabricated, installed, instrumented and tested in a fluidized bed test facility. Several test campaigns were conducted. This larger heater is a 3.5 times scale-up of the previous pulse heaters that had 72 tubes each. The smaller heater has been part of previous pilot field testing of the steam reformer at New Bern, North Carolina. The project also included collection and reduction of mild gasification process data from operation of the process development unit (PDU). The operation of the PDU was aimed at conditions required to produce char (and gas) for the Northshore Steel Operations. Northshore Steel supplied the coal for the process unit tests

  6. Test results of Nb3Sn ribbons for the Princeton D coil test program

    International Nuclear Information System (INIS)

    Kaugerts, J.; File, J.; Willard, J.W.

    1974-10-01

    A previously described D coil test program was modified. Details of a smaller Nb 3 Sn D coil test program are described. Cusp coil tests were made with several Nb 3 Sn composite ribbons. Measurements of both the quench and recovery currents as a function of magnetic field component perpendicular to the wide edge of the ribbon are presented. (auth)

  7. Brine migration test for Asse Mine, Federal Republic of Germany: final test plan

    International Nuclear Information System (INIS)

    1983-07-01

    The United States and the Federal Republic of Germany (FRG) will conduct a brine migration test in the Asse Salt Mine in the FRG as part of the US/FRG Cooperative Radioactive Waste Management Agreement. Two sets of two tests each will be conducted to study both liquid inclusion migration and vapor migration in the two salt types chosen for the experiments: (1) pure salt, for its characteristics similar to the salt that might occur in potential US repositories, and (2) transitional salt, for its similarity to the salt that might occur in potential repositories in Germany

  8. Prioritization of tasks in the draft LWR safety technology program plan. Final report

    International Nuclear Information System (INIS)

    Lim, E.Y.; Miller, W.J.; Parkinson, W.J.; Ritzman, R.L.; vonHerrmann, J.L.; Wood, P.J.

    1980-05-01

    The purpose of this report is to describe both the approach taken and the results produced in the SAI effort to prioritize the tasks in the Sandia draft LWR Safety Technology Program Plan. This work used the description of important safety issues developed in the Reactor Safety Study (2) to quantify the effect of safety improvements resulting from a research and development program on the risk from nuclear power plants. Costs of implementation of these safety improvements were also estimated to allow a presentation of the final results in a value (i.e., risk reduction) vs. impact (i.e., implementation costs) matrix

  9. Federal Employees Health Benefits Program: Removal of Eligible and Ineligible Individuals From Existing Enrollments. Final rule.

    Science.gov (United States)

    2018-01-23

    The United States Office of Personnel Management (OPM) is issuing a final rule amending Federal Employees Health Benefits (FEHB) Program regulations to provide a process for removal of certain identified individuals who are found not to be eligible as family members from FEHB enrollments. This process would apply to individuals for whom there is a failure to provide adequate documentation of eligibility when requested. This action also amends Federal Employees Health Benefits (FEHB) Program regulations to allow certain eligible family members to be removed from existing self and family or self plus one enrollments.

  10. Final report on special impact tests of plutonium shipping containers description of test results

    International Nuclear Information System (INIS)

    Bonzon, L.L.

    1977-02-01

    The results from tests conducted to determine the structural response of the LLD-1, Model 1518-6M, and FL-10 plutonium shipping packages when subjected to high-speed impacts (170 to 760 ft/sec) onto unyielding, concrete, and soil targets are presented

  11. Tritium Systems Test Assembly operator training program

    International Nuclear Information System (INIS)

    Kerstiens, F.L.

    1985-01-01

    Proper operator training is needed to help ensure the safe operation of fusion facilities by personnel who are qualified to carry out their assigned responsibilities. Operators control and monitor the Tritium Systems Test Assembly (TSTA) during normal, emergency, and maintenance phases. Their performance is critical both to operational safety, assuring no release of tritium to the atmosphere, and to the successful simulation of the fusion reaction progress. Through proper training we are helping assure that TSTA facility operators perform their assignments in a safe and efficient manner and that the operators maintain high levels of operational proficiency through continuing training, retraining, requalification, and recertification

  12. VA Dental Insurance Program--federalism. Direct final rule; confirmation of effective date.

    Science.gov (United States)

    2014-03-20

    The Department of Veterans Affairs (VA) published a direct final rule in the Federal Register on October 22, 2013, amending its regulations related to the VA Dental Insurance Program (VADIP), a pilot program to offer premium-based dental insurance to enrolled veterans and certain survivors and dependents of veterans. Specifically, this rule adds language to clarify the limited preemptive effect of certain criteria in the VADIP regulations. VA received no comments concerning this rule or its companion substantially identical proposed rule published in the Federal Register on October 23, 2013. This document confirms that the direct final rule became effective on December 23, 2013. In a companion document in this issue of the Federal Register, we are withdrawing as unnecessary the proposed rule.

  13. No. 2 heating oil/propane program. Final report, 1992/93

    Energy Technology Data Exchange (ETDEWEB)

    McBrien, J.

    1993-05-01

    During the 1992--93 heating season, the Massachusetts Division Energy Resources (DOER) participated in a joint data collection program between several state energy offices and the federal Department of Energy`s (DOE) Energy Information Administration (EIA). The purpose of the program was to collect and monitor retail and wholesale heating oil and propane prices and inventories from October, 1992 through March, 1993. This final report begins with an overview of the unique events which had an impact on the petroleum markets prior to and during the reporting period. Next, the report summarizes the results from residential heating oil and propane price surveys conducted by DOER over the 1992--93 heating season. The report also incorporates the wholesale heating oil and propane prices and inventories collected by the EIA and distributed to the states. Finally, the report outlines DOER`s use of the data.

  14. Number 2 heating oil/propane program. Final report, 1991/92

    Energy Technology Data Exchange (ETDEWEB)

    McBrien, J.

    1992-06-01

    During the 1991--92 heating season, the Massachusetts Division of Energy Resources (DOER) participated in a joint data collection program between several state energy offices and the federal Department of Energy`s (DOE) Energy Information Administration (EIA). The purpose of the program was to collect and monitor retail and wholesale heating oil and propane prices and inventories from October, 1991 through March, 1992. This final report begins with an overview of the unique events which had an impact on the reporting period. Next, the report summarizes the results from the residential heating oil and propane price surveys conducted by DOER over the 1991--1992 heating season. The report also incorporates the wholesale heating oil and propane prices and inventories collected by the EIA and distributed to the states. Finally, the report outlines DOER`s use of the data and responses to the events which unfolded during the 1991--1992 heating season.

  15. Mission definition study for Stanford relativity satellite. Volume 2: Engineering flight test program

    Science.gov (United States)

    1971-01-01

    The need is examined for orbital flight tests of gyroscope, dewar, and other components, in order to reduce the technical and financial risk in performing the relativity experiment. A program is described that would generate engineering data to permit prediction of final performance. Two flight tests are recommended. The first flight would test a dewar smaller than that required for the final flight, but of size and form sufficient to allow extrapolation to the final design. The second flight would use the same dewar design to carry a set of three gyroscopes, which would be evaluated for spinup and drift characteristics for a period of a month or more. A proportional gas control system using boiloff helium gas from the dewar, and having the ability to prevent sloshing of liquid helium, would also be tested.

  16. History of ground motion programs at the Nevada Test Site

    International Nuclear Information System (INIS)

    Banister, J.R.

    1984-01-01

    Some measurements were made in the atmospheric testing era, but the study of ground motion from nuclear tests became of wider interest after the instigation of underground testing. The ground motion generated by underground nuclear test has been investigated for a number of reasons including understanding basic phenomena, operational and safety concerns, yield determination, stimulation of earthquake concerns, and developing methods to aid in treaty verifications. This history of ground motion programs will include discussing early studies, high yield programs, Peaceful Nuclear Explosions tests, and some more recent developments. 6 references, 10 figures

  17. USAF Summer Research Program - 1993 High School Apprenticeship Program Final Reports, Volume 12, Armstrong Laboratory

    Science.gov (United States)

    1993-12-01

    photoelectric effect in biological substances (amino acids, proteins , or spores), a conducting metal, salt (NaCl), was tested to determine if granule...eliminating exercise before a flight, and maintaining a high protein , low bulk diet. Some leave alcohol out of their daily routine to help in the process...WISE has eight tools: Freewriting ( Dinosaur Drag), Sticky Notes, Writing Pad, Thought Log, Crossword Puzzle, Cubing, Revision, and Idea Board. In

  18. Full-Length High-Temperature Severe Fuel Damage Test No. 5: Final safety analysis

    International Nuclear Information System (INIS)

    Lanning, D.D.; Lombardo, N.J.; Panisko, F.E.

    1993-09-01

    This report presents the final safety analysis for the preparation, conduct, and post-test discharge operation for the Full-Length High Temperature Experiment-5 (FLHT-5) to be conducted in the L-24 position of the National Research Universal (NRU) Reactor at Chalk River Nuclear Laboratories (CRNL), Ontario, Canada. The test is sponsored by an international group organized by the US Nuclear Regulatory Commission. The test is designed and conducted by staff from Pacific Northwest Laboratory with CRNL staff support. The test will study the consequences of loss-of-coolant and the progression of severe fuel damage

  19. Oregon state university's advanced plant experiment (APEX) AP1000 integral facility test program

    International Nuclear Information System (INIS)

    Reyes, J.N.; Groome, J.T.; Woods, B.G.; Young, E.; Abel, K.; Wu, Q.

    2005-01-01

    Oregon State University (OSU) has recently completed a three year study of the thermal hydraulic behavior of the Westinghouse AP1000 passive safety systems. Eleven Design Basis Accident (DBA) scenarios, sponsored by the U.S. Department of Energy (DOE) with technical support from Westinghouse Electric, were simulated in OSU's Advanced Plant Experiment (APEX)-1000. The OSU test program was conducted within the purview of the requirements of 10CFR50 Appendix B, NQA-1 and 10 CFR 21 and the test data was used to provide benchmarks for computer codes used in the final design approval of the AP1000. In addition to the DOE certification testing, OSU conducted eleven confirmatory tests for the U.S. Nuclear Regulatory Commission. This paper presents the test program objectives, a description of the APEX-1000 test facility and an overview of the test matrix that was conducted in support of plant certification. (authors)

  20. Testing program for concrete at temperatures to 8940K

    International Nuclear Information System (INIS)

    Naus, D.J.; Oland, C.B.; Robinson, G.C.

    1981-01-01

    A test program was conducted to define the variations in mechanical properties of a limestone aggregate concrete and a lightweight insulating concrete exposed to elevated temperatures. Four test series were conducted: (1) unconfined compression; (2) shear; (3) rebar bond; and (4) sustained loading (creep). Tests results are presented

  1. Justice downwind: America's atomic testing program in the 1950s

    International Nuclear Information System (INIS)

    Ball, H.

    1986-01-01

    Drawing on personal interviews, case histories, and the archives of the Atomic Energy Commission, Professor Ball discusses the American nuclear-testing program from 1951 to 1963, the impact of the testing on people living downwind from the Nevada Test Site, long-term effects of radiation exposure, and the clash between the ''downwinders'' and the government

  2. The Department of Energy's radon testing program

    International Nuclear Information System (INIS)

    Scott, H.L.; Dudney, C.S.; Wilson, D.L.; Gammage, R.B.

    1993-01-01

    The US Department of Energy recently completed an initial survey of indoor radon in its buildings in response to Public Law 100--551, the Indoor Radon Abatement Act of 1988. Other federal agencies have also conducted radon surveys. This paper presents an overview of the results from radon testing of several thousand buildings ranging from 100 m 2 to over 10,000 M 2 in size. In addition, we have examined results from groups of buildings, classified according to ventilation and usage characteristics. So far, there is no apparent difference among building classes. The paper also discusses our proposal for phased radon surveys. We suggest that first-phase results can be used to identify facilities with radon problems. In the second phase, we suggest measurements be made at a much higher sampling density at facilities with radon problems. The results of the second phase are expected to identify all buildings in need of mitigation

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

    Energy Technology Data Exchange (ETDEWEB)

    Collar, Craig W

    2012-11-16

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

  4. Construction and test of the final CMS Barrel Drift Tube Muon Chamber prototype

    Energy Technology Data Exchange (ETDEWEB)

    Aguilar-Benitez, M.; Alberdi, J.; Arneodo, M.; Banicz, K.; Benettoni, M.; Benvenuti, A.; Bethke, S.; Cerrada, M. E-mail: cerrada@ciemat.es; Cirio, R.; Colino, N.; Conti, E.; Dallavalle, M.; Daniel, M.; Dattola, D.; Daudo, F.; De Giorgi, M.; Dosselli, U.; Fanfani, A.; Fanin, C.; Fouz, M.C.; Gasparini, F.; Gasparini, U.; Giacomelli, P.; Giordano, V.; Gonella, F.; Grandi, C.; Guaita, P.; Guerzoni, M.; Lacaprara, S.; Lippi, I.; Marcellini, S.; Marin, J.; Martinelli, R.; Maselli, S.; Meneguzzo, A.; Migliore, E.; Mocholi, J.; Monaco, V.; Montanari, A.; Montanari, C.; Odorici, F.; Oller, J.C.; Paoletti, S.; Passaseo, M.; Pegoraro, M.; Peroni, C.; Puerta, J.; Reithler, H.; Romero, A.; Romero, L.; Ronchese, P.; Rossi, A.M.; Rovelli, T.; Sacchi, R.; Salicio, J.M.; Staiano, A.; Steinbeck, T.; Torassa, E.; Travaglini, R.; Ventura, L.; Ventura, S.; Vitelli, A.; Voetee, F.; Wegner, M.; Willmott, C.; Zotto, P.; Zumerle, G

    2002-03-21

    A prototype of the CMS Barrel Muon Detector incorporating all the features of the final chambers was built using the mass production assembly procedures and tools. The performance of this prototype was studied in a muon test beam at CERN and the results obtained are presented in this paper.

  5. Final report of the Buffer Mass Test. Volume II: test results

    International Nuclear Information System (INIS)

    Pusch, R.; Boerjesson, L.; Ramqvist, G.

    1985-08-01

    The evaluation of the Buffer Mass Test mainly concerned the heating of the bentonite/rock system that simulated hot canisters in deposition holes, the swelling and swelling pressure of the expanding bentonite in the heater holes, and the water uptake of the bentonite in the holes as well as in the tunnel backfill. These processes had been predicted on the basis of laboratory-derived data and FEM calculations with due consideration of the actual geometry. The recorded temperatures of the bentonite and surrounding rock were found to be below the maximum temperature that had been set, but higher than the expected values in the initial period of testing. The heater surface temperatures dropped in the course of the tests due to the uptake of water from the rock even in the driest hole which was located in almost fracture-free rock. The water uptake in the highly compacted bentonite in the heater holes was manifested by a successively increased swelling pressure at the bentonite/rock interface. It was rather uniformly distributed over this interface and reached a maximum value of about 10 MPa. The water content determination confirmed that water had been absorbed by the bentonite from the rock even in the driest holes where the counteracting thermal gradient was rather high. In the wettest holes the saturation became almost complete and a high degree of saturation was also observed in the tunnel backfill. Both in the heater holes and the tunnel, the moistening was found to be very uniform along the periphery, which is at least partly explained by the self-sealing ability of bentonite buffer materials. A general conclusion is that the involved physical processes are well understood and that the ultimate physical state of the buffer materials under repository conditions can be safely predicted. With 15 refs. (Author)

  6. High energy physics program at Texas A&M University. Final report, April 1, 1990--March 31, 1991

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-01

    The Texas A&M experimental high energy physics program has been supported since its inception by DOE Contract DE-AS05-81ER40039. During that period we established a viable experimental program at a university which before this time had no program in high energy physics. In 1990, the experimental program was augmented with a program in particle theory. In the accompanying final report, we outline the research work accomplished during the final year of this contract and the program being proposed for consideration by the Department of Energy for future grant support. Some of the particular areas covered are: Collider detector at Fermilab program; the TAMU MACRO program; SSC R&D program; SSC experimental program; and theoretical physics program.

  7. PBF/LOFT Lead Rod Test Program experiment operating specification

    International Nuclear Information System (INIS)

    Varacalle, D.J. Jr.

    1978-11-01

    The PBF/LOFT Lead Rod (LLR) Test Program is being conducted to provide experimental information on the behavior of nuclear fuel under normal and accident conditions in the Power Burst Facility at the Idaho National Engineering Laboratory. Understanding the behavior of light-water reactors (LWR) under loss-of-coolant conditions is a major objective of the NRC Reactor Safety Research Program. The Loss of Fluid Test (LOFT) facility is the major testing facility to evaluate the systems response of an LWR over a wide range of Loss of Coolant Experment (LOCE) conditions. As such, the LOFT core is intended to be used for sequential LOCE tests provided no significant fuel rod failures occur. The PFB/LLR tests are designed to simulate the test conditions for the LOFT Power Ascension Tests L2-2 through L2-5. The test program has been designed to provide a parametric evaluation of the LOFT fuel over a wide range of power. Thus, a relatively accurate assessment of the state of the LOFT core after the completion of each subtest and the anticipated effect of the next test can be obtained by utilizing a combination of LLR test data and analytical predictions. Specifications for the test program are presented

  8. Final report of the Buffer Mass Test - Volume I: Scope, preparative field work and test arrangement

    International Nuclear Information System (INIS)

    Pusch, R.; Nilsson, J.; Ramqvist, G.

    1985-07-01

    The Buffer Mass Test was conducted in a 30 m long drift at 340 m depth in the Stripa mine, The main objective being to check the predicted functions of certain bentonite-based buffer materials in rock environment. These materials were blocks of highly compacted sodium bentonite placed in large boreholes simulating deposition holes for canisters, and on-site compacted sand/bentonite mixtures used as tunnel backfill. The blocks of bentonite embedded electrical heaters which served to produce heat so as to create conditions similar to those in a repository. The temperature in the initially non-saturated buffer materials was expected to be a function of the water uptake from the rock, which was also assumed to lead to rather high swelling pressures. The recording of these processes and of the moistening of the buffer materials , as well as of the associated build-up of piezometric heads at rock/buffer interfaces, was the major item of the field test. For this purpose the buffer materials and the rock were equipped with a large number of thermal elements, pressure and piezometric cells as well as moisture sensors. The choise of positions and properties of these gauges, which were connected to an effective data acquisition system, was based on predictions that required a careful site documentation with respect to the fracture characteristics and hydrological properties of the surrounding rock. (author)

  9. Testing the structure of a hydrological model using Genetic Programming

    Science.gov (United States)

    Selle, Benny; Muttil, Nitin

    2011-01-01

    SummaryGenetic Programming is able to systematically explore many alternative model structures of different complexity from available input and response data. We hypothesised that Genetic Programming can be used to test the structure of hydrological models and to identify dominant processes in hydrological systems. To test this, Genetic Programming was used to analyse a data set from a lysimeter experiment in southeastern Australia. The lysimeter experiment was conducted to quantify the deep percolation response under surface irrigated pasture to different soil types, watertable depths and water ponding times during surface irrigation. Using Genetic Programming, a simple model of deep percolation was recurrently evolved in multiple Genetic Programming runs. This simple and interpretable model supported the dominant process contributing to deep percolation represented in a conceptual model that was published earlier. Thus, this study shows that Genetic Programming can be used to evaluate the structure of hydrological models and to gain insight about the dominant processes in hydrological systems.

  10. No. 2 heating oil/propane program 1994--1995. Final report

    International Nuclear Information System (INIS)

    McBrien, J.

    1995-05-01

    During the 1994--95 heating season, the Massachusetts Division of Energy Resources (DOER) participated in a joint data collection program between several state energy offices and the federal Department of Energy's (DOE) Energy Information Administration (EIA). The purpose of the program was to collect and monitor retail and wholesale heating oil and propane prices and inventories from October 1994 through March 1995. This program augmented the existing Massachusetts data collection system and served several important functions. The information helped the federal and state governments respond to consumer, congressional and media inquiries regarding No. 2 oil and propane. The information also provided policy decision-makers with timely, accurate and consistent data to monitor current heating oil and propane markets and develop appropriate state responses when necessary. In addition, the communication network between states and the DOE was strengthened through this program. This final report begins with an overview of the unique events that had an impact on the petroleum markets prior to and during the reporting period. Next, the report summarizes the results from residential heating oil and propane price surveys conducted by DOER over the 1994--95 heating season. The report also incorporates the wholesale heating oil and propane prices and inventories collected by EIA and distributed to the states. Finally, the report outlines DOER's use of the data

  11. Low NOx Burner Development Program - Final Report - 09/15/1996 - 09/30/2000

    Energy Technology Data Exchange (ETDEWEB)

    McClaine, Andrew W.

    2000-09-30

    This report describes the work performed to develop and demonstrate the VISTA combustor. The development effort was planned for three phases. Laboratory testing at a 1.5 and 6 MMBtu/hr scale was performed at thermo Power Corporation during the first phase. Also during the first phase, analytic modeling was performed to guide the design modifications evaluated in the experimental testing. Toward the end of the first phase, John Zink Company entered the program to participate in the design, evaluation, testing, and demonstration of a 30 MMBtu/hr combustor. The results of the second phase testing were to be used in the demonstration of the 30 MMBtu/hr combustor in a Koch Industries boiler. The program proceeded into the second phase. Two models of the VISTA combustor were tested. Measurements of the first stage NOx production were in the range anticipated to achieve the program goals, based on analytical modeling results. While testing the VISTA combustor at the John Zink facility, John Zink elected to discontinue the development of the VISTA combustor in favor of an alternative in-house concept. As a result, this program was terminated.

  12. Final Project Report on RCCS Testing with Air-based NSTF

    Energy Technology Data Exchange (ETDEWEB)

    Lisowski, Darius D. [Argonne National Lab. (ANL), Argonne, IL (United States); Gerardi, Craig D. [Argonne National Lab. (ANL), Argonne, IL (United States); Kilsdonk, Dennis J. [Argonne National Lab. (ANL), Argonne, IL (United States); Bremer, Nathan C. [Argonne National Lab. (ANL), Argonne, IL (United States); Lomperski, Stephen W. [Argonne National Lab. (ANL), Argonne, IL (United States); Hu, Rui [Argonne National Lab. (ANL), Argonne, IL (United States); Kraus, Adam R. [Argonne National Lab. (ANL), Argonne, IL (United States); Bucknor, Matthew D. [Argonne National Lab. (ANL), Argonne, IL (United States); Lv, Qiuping [Argonne National Lab. (ANL), Argonne, IL (United States); Lee, Taeseung [Argonne National Lab. (ANL), Argonne, IL (United States); Farmer, Mitchell T. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-08-01

    The following report serves as a comprehensive summary of the air-based portion of the Natural convection Shutdown heat removal Test Facility (NSTF) program at Argonne National Laboratory (Argonne). Initiated in 2005 to generate validation data for the Next Generation Nuclear Plant (NGNP), the project was centered on an experimental testing program to study the behavior and bound the performance of Reactor Cavity Cooling System (RCCS) concepts. Parallel modeling and simulation efforts also have been performed to guide the design, fabrication, and operation of NSTF, as well as to assess the suitability of analysis methods for natural convection systems. The program operates under support from the Department of Energy (DOE) Office of Advanced Reactor Technologies (ART), and maintained compliance with NQA-1 2008 with 2009a in both administrative and technical portions of program activities.

  13. CRIEPI test program for seismic isolation of the FBR

    International Nuclear Information System (INIS)

    Shiojiri, Hiroo

    1989-01-01

    This paper describes the Central Research Institute of Electric Power Industry's (CRIEPIs) seismic isolation program. The test and research program on seismic isolation was started in 1987 by CRIEPI under contract with the Ministry of International Trade and Industry (MITI) of Japan. It was intended to establish a technical basis for the application of seismic isolation to fast breeder reactors (FBRs). In this paper, some details of the program and results of the preliminary study are described

  14. Prototype steam generator test at SCTI/ETEC. Acoustic program test plan

    International Nuclear Information System (INIS)

    Greene, D.A.; Thiele, A.; Claytor, T.N.

    1981-10-01

    This document is an integrated test plan covering programs at General Electric (ARSD), Rockwell International (RI) and Argonne National Laboratory (CT). It provides an overview of the acoustic leak detection test program which will be completed in conjunction with the prototype LMFBR steam generator at the Energy Technology Engineering Laboratory. The steam generator is installed in the Sodium Components Test Installation (SCTI). Two acoustic detection systems will be used during the test program, a low frequency system developed by GE-ARSD (GAAD system) and a high frequency system developed by RI-AI (HALD system). These systems will be used to acquire data on background noise during the thermal-hydraulic test program. Injection devices were installed during fabrication of the prototype steam generator to provide localized noise sources in the active region of the tube bundle. These injectors will be operated during the steam generator test program, and it will be shown that they are detected by the acoustic systems

  15. LWR aerosol containment experiments (LACE) program and initial test results

    International Nuclear Information System (INIS)

    Muhlestein, L.D.; Hilliard, R.K.; Bloom, G.R.; McCormack, J.D.; Rahn, F.J.

    1985-01-01

    The LWR aerosol containment experiments (LACE) program is described. The LACE program is being performed at the Hanford Engineer Development Laboratory (operated by Westinghouse Hanford Company) and the initial tests are sponsored by EPRI. The objectives of the LACE program are: to demonstrate, at large-scale, inherent radioactive aerosol retention behavior for postulated high consequence LWR accident situations; and to provide a data base to be used for aerosol behavior . Test results from the first phase of the LACE program are presented and discussed. Three large-scale scoping tests, simulating a containment bypass accident sequence, demonstrated the extent of agglomeration and deposition of aerosols occurring in the pipe pathway and vented auxiliary building under realistic accident conditions. Parameters varied during the scoping tests were aerosol type and steam condensation

  16. Sodium sulfur electric vehicle battery engineering program final report, September 2, 1986--June 15, 1993

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-06-01

    In September 1986 a contract was signed between Chloride Silent Power Limited (CSPL) and Sandia National Laboratories (SNL) entitled ``Sodium Sulfur Electric Vehicle Battery Engineering Program``. The aim of the cost shared program was to advance the state of the art of sodium sulfur batteries for electric vehicle propulsion. Initially, the work statement was non-specific in regard to the vehicle to be used as the design and test platform. Under a separate contract with the DOE, Ford Motor Company was designing an advanced electric vehicle drive system. This program, called the ETX II, used a modified Aerostar van for its platform. In 1987, the ETX II vehicle was adopted for the purposes of this contract. This report details the development and testing of a series of battery designs and concepts which led to the testing, in the US, of three substantial battery deliverables.

  17. Simultaneous test construction by zero-one programming

    NARCIS (Netherlands)

    Boekkooi-Timminga, Ellen

    1986-01-01

    A method is described for simultaneous test construction using the Operations Research technique zero-one programming. The model for zero-one programming consists of two parts. The first contains the objective function that describes the aspect to be optimized. The second part contains the

  18. 76 FR 23914 - National Organic Program; Periodic Residue Testing

    Science.gov (United States)

    2011-04-29

    ... NOP. Residue testing plays an important role in organic certification by providing a means for... OFPA (7 U.S.C. 6503 through 6507) from creating certification programs to certify organic farms or... State organic certification program may contain additional requirements for the production and handling...

  19. NCAA Drug-Testing Program 2010-11

    Science.gov (United States)

    National Collegiate Athletic Association (NJ1), 2010

    2010-01-01

    The National Collegiate Athletic Association (NCAA) Drug-Testing Program was created to protect the health and safety of student-athletes and to ensure that no one participant might have an artificially induced advantage or be pressured to use chemical substances. This publication describes this program in the following chapters: (1) NCAA…

  20. Final Report for the MANNRRSS II Program Management of Nevada's Natural Resources with Remote Sensing Systems, Beatty, NV

    Energy Technology Data Exchange (ETDEWEB)

    Lester Miller; Brian Horowitz; Chris Kratt; Tim Minor; Stephen F. Zitzer; James. V. Taranik; Zan L. Aslett; Todd O. Morken

    2009-06-04

    This document provides the Final Report on the Management of Nevada’s Natural Resources with Remote Sensing Systems (MANNRRSS) II program. This is a U.S. Department of Energy (DOE)-funded project tasked with utilizing hyperspectral and ancillary electro-optical instrumentation data to create an environmental characterization of an area directly adjacent to the Nevada Test Site (NTS).

  1. Oil spill sorbents: Testing protocol and certification listing program

    International Nuclear Information System (INIS)

    Cooper, D.; Gausemel, I.

    1993-01-01

    Environment Canada's Emergencies Engineering Division is spearheading a program in conjunction with the Canadian General Standards Board that would see the development of a certification and listing program in addition to a national standard for the testing of sorbent materials. Funding for this program is provided by Environment Canada (EC), Canadian Coast Guard (CCG), Marine Spill Response Corporation (MSRC), US Coast Guard (USCG), and US Minerals Management Service (MMS). The test methods are based upon those defined by the American Society for Testing and Materials and previous test methods developed by Environment Canada for our series of reports entitled Selection Criteria and Laboratory Evaluation of Oil Spill Sorbents. This series, which was started in 1975, encompasses a number of commercially available oil spill sorbents tested with different petroleum products and hydrocarbon solvents. The testing program will categorize the sorbents according to their operating characteristics. The main categories are oil spills on water, oil spills on land, and industrial use. The characteristics to be evaluated with the new test protocols include initial and maximum sorption capacities, water pickup, buoyancy, reuse potential, retention profile, disintegration (material integrity), and ease of application and retrieval. In the near future are plans to incorporate changes to the test that would involve increasing the list of test liquids to encompass spills in an industrial setting, in addition to testing sorbent booms and addressing the disposal problem

  2. High Performance Computing Modernization Program Kerberos Throughput Test Report

    Science.gov (United States)

    2017-10-26

    Naval Research Laboratory Washington, DC 20375-5320 NRL/MR/5524--17-9751 High Performance Computing Modernization Program Kerberos Throughput Test ...NUMBER 5d. PROJECT NUMBER 5e. TASK NUMBER 5f. WORK UNIT NUMBER 2. REPORT TYPE1. REPORT DATE (DD-MM-YYYY) 4. TITLE AND SUBTITLE 6. AUTHOR(S) 8. PERFORMING...PAGE 18. NUMBER OF PAGES 17. LIMITATION OF ABSTRACT High Performance Computing Modernization Program Kerberos Throughput Test Report Daniel G. Gdula* and

  3. NedWind 25 Blade Testing at NREL for the European Standards Measurement and Testing Program

    Energy Technology Data Exchange (ETDEWEB)

    Larwood, S.; Musial, W.; Freebury, G.; Beattie, A.G.

    2001-04-19

    In the mid-90s the European community initiated the Standards, Measurements, and Testing (SMT) program to harmonize testing and measurement procedures in several industries. Within the program, a project was carried out called the European Wind Turbine Testing Procedure Development. The second part of that project, called Blade Test Methods and Techniques, included the United States and was devised to help blade-testing laboratories harmonize their testing methods. This report provides the results of those tests conducted by the National Renewable Energy Laboratory.

  4. Final Test at the Surface of the ATLAS Endcap Muon Trigger Chamber Electronics

    CERN Document Server

    Kubota, T; Kanaya, N; Kawamoto, T; Kobayashi, T; Kuwabara, T; Nomoto, H; Sakamoto, H; Yamaguchi, T; Fukunaga, C; Ikeno, M; Iwasaki, H; Nagano, K; Nozaki, M; Sasaki, O; Tanaka, S; Yasu, Y; Hasegawa, Y; Oshita, H; Takeshita, T; Nomachi, M; Sugaya, Y; Sugimoto, T; Okumura, Y; Takahashi, Y; Tomoto, M; Kadosaka, T; Kawagoe, K; Kiyamura, H; Kurashige, H; Niwa, T; Ochi, A; Omachi, C; Takeda, H; Lifshitz, R; Lupu, N; Bressler, S; Tarem, S; Kajomovitz, E; Ben Ami, S; Bahat Treidel, O; Benhammou, Ya; Etzion, E; Lellouch, D; Levinson, L; Mikenberg, G; Roich, A

    2007-01-01

    For the detector commissioning planned in 2007, sector assembly of the ATLAS muon-endcap trigger chambers and final test at the surface for the assembled electronics are being done in CERN and almost completed. For the test, we built up the Data Acquisition (DAQ) system using test pulse of two types and cosmic rays in order to check functionality of the various aspects of the electronics mounted on a sector. So far, 99% of all 320,000 channels have been tested and most of them were installed into the ATLAS cavern. In this presentation, we will describe the DAQ systems and mass-test procedure in detail, and report the result of electronics test with some actual experiences

  5. Testing Automation of Context-Oriented Programs Using Separation Logic

    Directory of Open Access Journals (Sweden)

    Mohamed A. El-Zawawy

    2014-01-01

    Full Text Available A new approach for programming that enables switching among contexts of commands during program execution is context-oriented programming (COP. This technique is more structured and modular than object-oriented and aspect-oriented programming and hence more flexible. For context-oriented programming, as implemented in COP languages such as ContextJ* and ContextL, this paper introduces accurate operational semantics. The language model of this paper uses Java concepts and is equipped with layer techniques for activation/deactivation of layer contexts. This paper also presents a logical system for COP programs. This logic is necessary for the automation of testing, developing, and validating of partial correctness specifications for COP programs and is an extension of separation logic. A mathematical soundness proof for the logical system against the proposed operational semantics is presented in the paper.

  6. History and Benefits of Engine Level Testing Throughout the Space Shuttle Main Engine Program

    Science.gov (United States)

    VanHooser, Katherine; Kan, Kenneth; Maddux, Lewis; Runkle, Everett

    2010-01-01

    Rocket engine testing is important throughout a program s life and is essential to the overall success of the program. Space Shuttle Main Engine (SSME) testing can be divided into three phases: development, certification, and operational. Development tests are conducted on the basic design and are used to develop safe start and shutdown transients and to demonstrate mainstage operation. This phase helps form the foundation of the program, demands navigation of a very steep learning curve, and yields results that shape the final engine design. Certification testing involves multiple engine samples and more aggressive test profiles that explore the boundaries of the engine to vehicle interface requirements. The hardware being tested may have evolved slightly from that in the development phase. Operational testing is conducted with mature hardware and includes acceptance testing of flight assets, resolving anomalies that occur in flight, continuing to expand the performance envelope, and implementing design upgrades. This paper will examine these phases of testing and their importance to the SSME program. Examples of tests conducted in each phase will also be presented.

  7. SPSS and SAS programming for the testing of mediation models.

    Science.gov (United States)

    Dudley, William N; Benuzillo, Jose G; Carrico, Mineh S

    2004-01-01

    Mediation modeling can explain the nature of the relation among three or more variables. In addition, it can be used to show how a variable mediates the relation between levels of intervention and outcome. The Sobel test, developed in 1990, provides a statistical method for determining the influence of a mediator on an intervention or outcome. Although interactive Web-based and stand-alone methods exist for computing the Sobel test, SPSS and SAS programs that automatically run the required regression analyses and computations increase the accessibility of mediation modeling to nursing researchers. To illustrate the utility of the Sobel test and to make this programming available to the Nursing Research audience in both SAS and SPSS. The history, logic, and technical aspects of mediation testing are introduced. The syntax files sobel.sps and sobel.sas, created to automate the computation of the regression analysis and test statistic, are available from the corresponding author. The reported programming allows the user to complete mediation testing with the user's own data in a single-step fashion. A technical manual included with the programming provides instruction on program use and interpretation of the output. Mediation modeling is a useful tool for describing the relation between three or more variables. Programming and manuals for using this model are made available.

  8. FEBEX II Project Final report on thermo-hydro-mechanical laboratory tests

    Energy Technology Data Exchange (ETDEWEB)

    Lloret, A.; Romero, E.; Villar, M. V.

    2004-07-01

    The results of the thermo-hydro-mechanical (THM) study of the FEBEX bentonite performed during FEBEX II are presented. The laboratory test program continued in part with the works carried out during FEBEX I, particularly in activities related to tests aimed to the calibration of the models, the acquisition of parameters by back-analysis and the improvement of the knowledge on the behaviour of expansive clays. But the program has also included tests on new areas: investigations about the influence of the microstructure changes in bentonite, of temperature and of the solute concentration on the behaviour of clay. Besides, several tests were proposed in order to understand the unexpected behaviour observed in the mock-up test, towards the end of year 2. Temperature effects on water retention curves in confined and unconfined conditions were determined, and swelling pressure, hydraulic conductivity and swelling and consolidation strains as a function of temperature were successfully measured. Different experimental techniques and equipments were developed to study thermal induced changes under partially saturated states, covering a wide range of suctions. FEBEX bentonite remains suitable as a sealing material in HLW repositories (from the hydro- mechanical point of view) for temperatures of up to 80 C, as it keeps its high water retention capacity, low permeability and self-healing ability. The extrapolation of results points out to the preservation of properties for at least up to 100 C. Mercury intrusion porosimetry and environmental scanning electron microscopy provided promising results in order to characterise the bentonite microstructure and to give information about the mechanisms influencing pore size distribution changes on high active clays. The use of digital imaging techniques allowed verifying that at micro-scale level, where chemical phenomena prevail, strains are almost reversible as it is considered in the two-level elasto-plastic models. The swelling

  9. FEBEX II Project Final report on thermo-hydro-mechanical laboratory tests

    International Nuclear Information System (INIS)

    Lloret, A.; Romero, E.; Villar, M. V.

    2004-01-01

    The results of the thermo-hydro-mechanical (THM) study of the FEBEX bentonite performed during FEBEX II are presented. The laboratory test program continued in part with the works carried out during FEBEX I, particularly in activities related to tests aimed to the calibration of the models, the acquisition of parameters by back-analysis and the improvement of the knowledge on the behaviour of expansive clays. But the program has also included tests on new areas: investigations about the influence of the microstructure changes in bentonite, of temperature and of the solute concentration on the behaviour of clay. Besides, several tests were proposed in order to understand the unexpected behaviour observed in the mock-up test, towards the end of year 2. Temperature effects on water retention curves in confined and unconfined conditions were determined, and swelling pressure, hydraulic conductivity and swelling and consolidation strains as a function of temperature were successfully measured. Different experimental techniques and equipments were developed to study thermal induced changes under partially saturated states, covering a wide range of suctions. FEBEX bentonite remains suitable as a sealing material in HLW repositories (from the hydro- mechanical point of view) for temperatures of up to 80 C, as it keeps its high water retention capacity, low permeability and self-healing ability. The extrapolation of results points out to the preservation of properties for at least up to 100 C. Mercury intrusion porosimetry and environmental scanning electron microscopy provided promising results in order to characterise the bentonite microstructure and to give information about the mechanisms influencing pore size distribution changes on high active clays. The use of digital imaging techniques allowed verifying that at micro-scale level, where chemical phenomena prevail, strains are almost reversible as it is considered in the two-level elasto-plastic models. The swelling

  10. Advanced fighter technology integration (AFTI)/F-16 Automated Maneuvering Attack System final flight test results

    Science.gov (United States)

    Dowden, Donald J.; Bessette, Denis E.

    1987-01-01

    The AFTI F-16 Automated Maneuvering Attack System has undergone developmental and demonstration flight testing over a total of 347.3 flying hours in 237 sorties. The emphasis of this phase of the flight test program was on the development of automated guidance and control systems for air-to-air and air-to-ground weapons delivery, using a digital flight control system, dual avionics multiplex buses, an advanced FLIR sensor with laser ranger, integrated flight/fire-control software, advanced cockpit display and controls, and modified core Multinational Stage Improvement Program avionics.

  11. The MuCool Test Area and RF Program

    International Nuclear Information System (INIS)

    Torun, Y.; Huang, D.; Norem, J.; Palmer, Robert B.; Stratakis, Diktys; Bross, A.; Chung, M.; Jansson, A.; Moretti, A.; Yonehara, K.; Li, D.

    2010-01-01

    The MuCool RF Program focuses on the study of normal conducting RF structures operating in high magnetic field for applications in muon ionization cooling for Neutrino Factories and Muon Colliders. Here we give an overview of the program, which includes a description of the test facility and its capabilities, the current test program, and the status of a cavity that can be rotated in the magnetic field, which allows for a detailed study of the maximum stable operating gradient vs. magnetic field strength and angle.

  12. Final safety analysis report for the Ground Test Accelerator (GTA), Phase 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-10-01

    This document is the second volume of a 3 volume safety analysis report on the Ground Test Accelerator (GTA). The GTA program at the Los Alamos National Laboratory (LANL) is the major element of the national Neutral Particle Beam (NPB) program, which is supported by the Strategic Defense Initiative Office (SDIO). A principal goal of the national NPB program is to assess the feasibility of using hydrogen and deuterium neutral particle beams outside the Earth`s atmosphere. The main effort of the NPB program at Los Alamos concentrates on developing the GTA. The GTA is classified as a low-hazard facility, except for the cryogenic-cooling system, which is classified as a moderate-hazard facility. This volume consists of failure modes and effects analysis; accident analysis; operational safety requirements; quality assurance program; ES&H management program; environmental, safety, and health systems critical to safety; summary of waste-management program; environmental monitoring program; facility expansion, decontamination, and decommissioning; summary of emergency response plan; summary plan for employee training; summary plan for operating procedures; glossary; and appendices A and B.

  13. Testing the Structure of Hydrological Models using Genetic Programming

    Science.gov (United States)

    Selle, B.; Muttil, N.

    2009-04-01

    Genetic Programming is able to systematically explore many alternative model structures of different complexity from available input and response data. We hypothesised that genetic programming can be used to test the structure hydrological models and to identify dominant processes in hydrological systems. To test this, genetic programming was used to analyse a data set from a lysimeter experiment in southeastern Australia. The lysimeter experiment was conducted to quantify the deep percolation response under surface irrigated pasture to different soil types, water table depths and water ponding times during surface irrigation. Using genetic programming, a simple model of deep percolation was consistently evolved in multiple model runs. This simple and interpretable model confirmed the dominant process contributing to deep percolation represented in a conceptual model that was published earlier. Thus, this study shows that genetic programming can be used to evaluate the structure of hydrological models and to gain insight about the dominant processes in hydrological systems.

  14. Integrated Data Collection Analysis (IDCA) Program - SSST Testing Methods

    Energy Technology Data Exchange (ETDEWEB)

    Sandstrom, Mary M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Brown, Geoffrey W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Preston, Daniel N. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Pollard, Colin J. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Warner, Kirstin F. [Naval Surface Warfare Center (NSWC), Indian Head, MD (United States). Indian Head Division; Remmers, Daniel L. [Naval Surface Warfare Center (NSWC), Indian Head, MD (United States). Indian Head Division; Sorensen, Daniel N. [Naval Surface Warfare Center (NSWC), Indian Head, MD (United States). Indian Head Division; Whinnery, LeRoy L. [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Phillips, Jason J. [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Shelley, Timothy J. [Bureau of Alcohol, Tobacco and Firearms (ATF), Huntsville, AL (United States); Reyes, Jose A. [Applied Research Associates, Tyndall AFB, FL (United States); Hsu, Peter C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Reynolds, John G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2013-03-25

    The Integrated Data Collection Analysis (IDCA) program is conducting a proficiency study for Small- Scale Safety and Thermal (SSST) testing of homemade explosives (HMEs). Described here are the methods used for impact, friction, electrostatic discharge, and differential scanning calorimetry analysis during the IDCA program. These methods changed throughout the Proficiency Test and the reasons for these changes are documented in this report. The most significant modifications in standard testing methods are: 1) including one specified sandpaper in impact testing among all the participants, 2) diversifying liquid test methods for selected participants, and 3) including sealed sample holders for thermal testing by at least one participant. This effort, funded by the Department of Homeland Security (DHS), is putting the issues of safe handling of these materials in perspective with standard military explosives. The study is adding SSST testing results for a broad suite of different HMEs to the literature. Ultimately the study will suggest new guidelines and methods and possibly establish the SSST testing accuracies needed to develop safe handling practices for HMEs. Each participating testing laboratory uses identical test materials and preparation methods wherever possible. The testing performers involved are Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Indian Head Division, Naval Surface Warfare Center, (NSWC IHD), Sandia National Laboratories (SNL), and Air Force Research Laboratory (AFRL/RXQL). These tests are conducted as a proficiency study in order to establish some consistency in test protocols, procedures, and experiments and to compare results when these testing variables cannot be made consistent.

  15. 75 FR 3153 - Drug and Alcohol Testing Program; Correction

    Science.gov (United States)

    2010-01-20

    ... definition of prohibited drugs. In Sec. Sec. 120.103 and 120.211, we omitted the reference to Sec. 135.1 from.... FAA-2008-0937; Amendment No. 120-0A, 135-117A] RIN 2120-AJ37 Drug and Alcohol Testing Program... Aviation Administration (FAA) is correcting its drug and alcohol testing regulations published on May 14...

  16. Frequency of chest pain in primary care, diagnostic tests performed and final diagnoses.

    Science.gov (United States)

    Hoorweg, Beatrijs Bn; Willemsen, Robert Ta; Cleef, Lotte E; Boogaerts, Tom; Buntinx, Frank; Glatz, Jan Fc; Dinant, Geert Jan

    2017-11-01

    Observational study of patients with chest pain in primary care: determination of incidence, referral rate, diagnostic tests and (agreement between) working and final diagnoses. 118 general practitioners (GPs) in the Netherlands and Belgium recorded all patient contacts during  2weeks. Furthermore, patients presenting with chest pain were registered extensively. A follow-up form was filled in after 30 days. 22 294 patient contacts were registered. In 281 (1.26%), chest pain was a reason for consulting the GP (mean age for men 54.4/women 53 years). In this cohort of 281 patients, in 38.1% of patients, acute coronary syndrome (ACS) was suspected at least temporarily during consultation, 40.2% of patients were referred to secondary care and 512 diagnostic tests were performed by GPs and consulted specialists. Musculoskeletal pain was the most frequent working (26.1%) and final diagnoses (33.1%). Potentially life-threatening diseases as final diagnosis (such as myocardial infarction) accounted for 8.4% of all chest pain cases. In 23.1% of cases, a major difference between working and final diagnoses was found, in 0.7% a severe disease was initially missed by the GP. Chest pain was present in 281 patients (1.26% of all consultations). Final diagnoses were mostly non-life-threatening. Nevertheless, in 8.4% of patients with chest pain, life-threatening underlying causes were identified. This seems reflected in the magnitude and wide variety of diagnostic tests performed in these patients by GPs and specialists, in the (safe) overestimation of life-threatening diseases by GPs at initial assessment and in the high referral rate we found. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2017. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

  17. Containment Leakage Rate Testing Program in NPP Krsko

    International Nuclear Information System (INIS)

    Dudas, M.; Heruc, Z.

    2002-01-01

    NPP Krsko adopted new regulations for testing of the reactor building containment as stipulated by 10CFR50 (Code of Federal Regulation) Appendix J, Option B instead of the previous requirement 10CFR50 Appendix J now renamed to 10CFR50 Appendix J, Option A. In the USA a thorough analyses of nuclear power plants reactor building containment testing was conducted. As part of these analyses the test results obtained from testing of various reactor-building containments in the last ten years were reviewed. It was concluded that it would be meaningful to, based on test results historical data, reconsider possibility of redefining testing intervals. The official proposal of such approach was reviewed and approved by the NRC and published in September of 1995 in the FR Vol.60 No.186. Based on directions from 10CFR50 Appendix J, Option B, the new criteria for definition of test intervals were created. Criteria were based upon past performance during testing (Performance-based Requirements) and safety impact. At NPP Krsko, the analyses of the Reactor Building Containment. Integrity Test results was performed . This included test results of the Containment Integrated Leak Rate Testing (CILRT or Type A tests), Containment Isolation Valves Local Leak Rater Tests (Type C tests) and Mechanical and Electrical Penetrations Local Leak Rate tests (Type B tests). In accordance with instructions from NEI 94-01 and based on analyses of test results, NPP Krsko created Containment Leakage Rate Testing Program with the purpose to establish the performance-based definition of test intervals, inspection scope, trending and reporting. Equally, the program gives instructions how to evaluate test results and how to deal with the containment penetration or isolation valve repair contingency. All changes caused with transition from Option A to Option B are marginal to public safety. (author)

  18. AN EVALUATION OF A PRESCHOOL TRAINING PROGRAM FOR CULTURALLY DEPRIVED CHILDREN. FINAL REPORT.

    Science.gov (United States)

    TAMMINEN, ARMAS W.; AND OTHERS

    TO FIND OUT IF CULTURALLY DEPRIVED CHILDREN SHOW CHANGE IN ACADEMIC READINESS AS A RESULT OF SPECIAL PRESCHOOL PROGRAMS, 3 GROUPS OF CHILDREN (14 TO 17 IN EACH) IN 3 DULUTH SCHOOL AREAS WERE PRE- AND POSTTESTED WITH THE STANFORD-BINET AND SRA PRIMARY MENTAL ABILITIES TESTS. A CONTROL GROUP OF 30 CHILDREN FROM THE SAME 3 SCHOOL AREAS WERE GIVEN THE…

  19. A final report on the Phase 1 testing of a molten-salt cavity receiver

    Energy Technology Data Exchange (ETDEWEB)

    Chavez, J M [ed.; Smith, D C [Babcock and Wilcox Co., Barberton, OH (United States). Nuclear Equipment Div.

    1992-05-01

    This report describes the design, construction, and testing of a solar central receiver using molten nitrate salt as a heat exchange fluid. Design studies for large commercial plants (30--100 MWe) have shown molten salt to be an excellent fluid for solar thermal plants as it allows for efficient thermal storage. Plant design studies concluded that an advanced receiver test was required to address uncertainties not covered in prior receiver tests. This recommendation led to the current test program managed by Sandia National Laboratories for the US Department of Energy. The 4.5 MWt receiver is installed at Sandia National Laboratories' Central Receiver Test Facility in Albuquerque, New Mexico. The receiver incorporates features of large commercial receiver designs. This report describes the receiver's configuration, heat absorption surface (design and sizing), the structure and supporting systems, and the methods for control. The receiver was solar tested during a six-month period at the Central Receiver Test Facility in Albuquerque, NM. The purpose of the testing was to characterize the operational capabilities of the receiver under a number of solar operating and stand-by conditions. This testing consisted of initial check-out of the systems, followed by steady-state performance, transient receiver operation, receiver operation in clouds, receiver thermal loss testing, receiver start-up operation, and overnight thermal conditioning tests. This report describes the design, fabrication, and results of testing of the receiver.

  20. Acoustic monitoring systems tests at Indian Point Unit 1. Final report

    International Nuclear Information System (INIS)

    Smith, J.R.; Rao, G.V.; Craig, J.

    1979-12-01

    This report describes the results of a program to test acoustic monitoring systems on Indian Point Unit No. 1 under actual plant operating conditions, less the reactor core. The two types of systems evaluated were the monitoring of acoustic emissions generated by growing flaws and the monitoring of acoustic signals from leaks

  1. 77 FR 30514 - Native Hawaiian Career and Technical Education Program; Final Waiver and Extension of Project Period

    Science.gov (United States)

    2012-05-23

    ... DEPARTMENT OF EDUCATION Native Hawaiian Career and Technical Education Program; Final Waiver and... Career and Technical Education Program Catalog of Federal Domestic Assistance (CFDA) Number: 84.259A... Technical Education Program (NHCTEP), the Secretary hereby waives 34 CFR 75.261(c)(2) in order to extend the...

  2. Radiation Tolerance Qualification Tests of the Final Source Interface Unit for the ALICE Experiment

    CERN Document Server

    Dénes, E; Futó, E; Kerék, A; Kiss, T; Molnár, J; Novák, D; Soós, C; Tölyhi, T; Van de Vyvre, P

    2007-01-01

    The ALICE Detector Data Link (DDL) is a high-speed optical link designed to interface the readout electronics of ALICE sub-detectors to the DAQ computers. The Source Interface Unit (SIU) of the DDL will operate in radiation environment. Previous tests showed that a configuration loss of SRAM-based FPGA devices may happen and the frequency of undetected data errors in the FPGA user memory area is also not acceptable. Therefore, we redesigned the SIU card using another FPGA based on flash technology. In order to detect bit errors in the user memory we added parity check logic to the design. The new SIU has been extensively tested using neutron and proton irradiation to verify its radiation tolerance. In this paper we summarize the design changes, introduce the final design, and the results of the radiation tolerance measurements on the final card.

  3. Final safety analysis report for the Ground Test Accelerator (GTA), Phase 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-10-01

    This document is the first volume of a 3 volume safety analysis report on the Ground Test Accelerator (GTA). The GTA program at the Los Alamos National Laboratory (LANL) is the major element of the national Neutral Particle Beam (NPB) program, which is supported by the Strategic Defense Initiative Office (SDIO). A principal goal of the national NPB program is to assess the feasibility of using hydrogen and deuterium neutral particle beams outside the Earth`s atmosphere. The main effort of the NPB program at Los Alamos concentrates on developing the GTA. The GTA is classified as a low-hazard facility, except for the cryogenic-cooling system, which is classified as a moderate-hazard facility. This volume consists of an introduction, summary/conclusion, site description and assessment, description of facility, and description of operation.

  4. Medicare program; clarification of Medicare's accrual basis of accounting policy--HCFA. Final rule.

    Science.gov (United States)

    1995-06-27

    This final rule revises the Medicare regulations to clarify the concept of "accrual basis of accounting" to indicate that expenses must be incurred by a provider of health care services before Medicare will pay its share of those expenses. This rule does not signify a change in policy but, rather, incorporates into the regulations Medicare's longstanding policy regarding the circumstances under which we recognize, for the purposes of program payment, a provider's claim for costs for which it has not actually expended funds during the current cost reporting period.

  5. 8th Asia oceania congress of nuclear medicine and biology final program abstracts

    International Nuclear Information System (INIS)

    2004-01-01

    The eighth Asia and Oceania congress of nuclear medicine and biology was held in Beijing, China, October 9-13 2004. The congress also held satellite meeting in Hong Kong SAR, China October 16-17 2004 and in Shanghai, China October 15 2005 respectively. The congress was sponsored by Chinese Society of Nuclear Medicine and organized by Asia and Oceania Federation of Nuclear Medicine and Biology. The final program includes 379 pieces abstracts, whose contents contain nuclear medicine diagnosis and therapy and biology

  6. No. 2 heating oil/propane program. Final report, 1990/91

    Energy Technology Data Exchange (ETDEWEB)

    McBrien, J.

    1991-06-01

    During the 1990/91 heating season, the Massachusetts Division of Energy Resources (DOER) participated in a joint data collection program between several state energy offices and the federal Department of Energy`s (DOE) Energy Information Administration (EIA). The purpose of the program was to collect and monitor retail and wholesale heating oil and propane prices and inventories from October 1990 through March 1991. This final report begins with an overview of the unique events which had an impact on the reporting period. Next, the report summarizes the results from the residential heating oil and propane price surveys conducted by DOER over the 1990/91 heating season. The report also incorporates the wholesale heating oil and propane prices and inventories collected by the EIA and distributed to the states.

  7. IFE chamber technology testing program in NIF and chamber development test plan

    International Nuclear Information System (INIS)

    Abdou, M.A.

    1995-01-01

    Issues concerning chamber technology testing program in NIF involving: criteria for evaluation/prioritization of experiments, engineering scaling requirements for test article design and material selection and R and D plan prior to NIF testing were addressed in this paper. In order to maximize the benefits of testing program in NIF, the testing in NIF should provide the experimental data relevant to DEMO design choice or to DEMO design predictive capability by utilizing engineering scaling test article designs. Test plans were developed for 2 promising chamber design concepts. Early testing in non-fusion/non-ignition prior to testing in ignition facility serves a critical role in chamber R and D test plans in order to reduce the risks and costs of the more complex experiments in NIF

  8. Final report proficiency test on the determination of α, β and γ-emitting radionuclides

    International Nuclear Information System (INIS)

    Shakhashiro, A.; Trinkl, A.; Benesch, T.; Sansone, U.

    2005-06-01

    A proficiency test on the determination of α, β and γ-emitting radionuclides was organised within the frame of the Technical Cooperation project: RAS/9/024 'Environmental Radiation Monitoring and Regional Data Base' to evaluate the analytical performance of 14 laboratories from 12 Asian countries. This report summarises the performance evaluation of the participating laboratories. Analytical data evaluation of this proficiency test showed that 58% of all reported results obtained a 'Passed' final score for both the trueness and precision criteria applied to this exercise. (author)

  9. High Efficiency Thermionics (HET-IV) and Converter Advancement (CAP) programs. Final reports

    Energy Technology Data Exchange (ETDEWEB)

    Geller, C.B.; Murray, C.S.; Riley, D.R. [Bettis Atomic Power Lab., West Mifflin, PA (United States); Desplat, J.L.; Hansen, L.K.; Hatch, G.L.; McVey, J.B.; Rasor, N.S. [Rasor Associates, Inc., Sunnyvale, CA (United States)

    1996-04-01

    This report contains the final report of the High Efficiency Thermionics (HET-IV) Program, Attachment A, performed at Rasor Associates, Inc. (RAI); and the final report of the Converter Advancement Program (CAP), performed at the Bettis Atomic Power Laboratory, Attachment B. The phenomenology of cesium-oxygen thermionic converters was elucidated in these programs, and the factors that had prevented the achievement of stable, enhanced cesium-oxygen converter performance for the previous thirty years were identified. Based on these discoveries, cesium-oxygen vapor sources were developed that achieved stable performance with factor-of-two improvements in power density and thermal efficiency, relative to conventional, cesium-only ignited mode thermionic converters. Key achievements of the HET-IV/CAP programs are as follows: a new technique for measuring minute traces of oxygen in cesium atmospheres; the determination of the proper range of oxygen partial pressures for optimum converter performance--10{sup {minus}7} to 10{sup {minus}9} torr; the discovery, and analysis of the cesium-oxygen liquid migration and compositional segregation phenomena; the successful use of capillary forces to contain the migration phenomenon; the use of differential heating to control compositional segregation, and induce vapor circulation; the development of mechanically and chemically stable, porous reservoir structures; the development of precise, in situ oxygen charging methods; stable improvements in emitter performance, up to effective emitter bare work functions of 5.4 eV; stable improvements in barrier index, to value below 1.8 Volts; the development of detailed microscopic models for cesium-oxygen reservoir dynamics and collector work function behavior; and the discovery of new relationships between electrode geometry and Schock Instability.

  10. Deep Vadose Zone Treatability Test of Soil Desiccation for the Hanford Central Plateau: Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Truex, Michael J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Chronister, Glen B. [CH2M Hill Plateau Remediation Co., Richland, WA (United States); Strickland, Christopher E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Johnson, Christian D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Tartakovsky, Guzel D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Oostrom, Martinus [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Clayton, Ray E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Johnson, Timothy C. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Freedman, Vicky L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Rockhold, Mark L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Greenwood, William J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Peterson, John E. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Hubbard, Susan S. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Ward, Anderson L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2018-02-20

    Some of the inorganic and radionuclide contaminants in the deep vadose zone at the Hanford Site are at depths where direct exposure pathways are not of concern, but may need to be remediated to protect groundwater. The Department of Energy developed a treatability test program for technologies to address Tc-99 and uranium in the deep vadose zone. These contaminants are mobile in the subsurface environment, have been detected at high concentrations deep in the vadose zone, and at some locations have reached groundwater. The treatability test of desiccation described herein was conducted as an element of the deep vadose zone treatability test program. Desiccation was shown to be a potentially effective vadose zone remediation technology to protect groundwater when used in conjunction with a surface infiltration barrier.

  11. Development of a test set for adjustment of residential furnaces and boilers. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    A program was undertaken to design and develop a portable test set for simplified field adjustment of residential furnaces and boilers to achieve peak operating efficiency. Advanced technology was applied to provide continuous analysis of flue gases and the display of temperature, oxygen concentrations, smoke value and furnace efficiency. Prototype models were constructed and delivered to Brookhaven National Laboratory for further testing. A survey of furnace dealers was conducted, and a commercialization plan was developed based on survey responses and the status of the equipment developed under the program. Goals for a marketable test set and development steps to achieve a projected energy savings were determined and recommended. Recommendations for specific areas of further development are included.

  12. Medicaid/CHIP Program; Medicaid Program and Children's Health Insurance Program (CHIP); Changes to the Medicaid Eligibility Quality Control and Payment Error Rate Measurement Programs in Response to the Affordable Care Act. Final rule.

    Science.gov (United States)

    2017-07-05

    This final rule updates the Medicaid Eligibility Quality Control (MEQC) and Payment Error Rate Measurement (PERM) programs based on the changes to Medicaid and the Children's Health Insurance Program (CHIP) eligibility under the Patient Protection and Affordable Care Act. This rule also implements various other improvements to the PERM program.

  13. Strengthening the fission reactor nuclear science and engineering program at UCLA. Final technical report

    International Nuclear Information System (INIS)

    Okrent, D.

    1997-01-01

    This is the final report on DOE Award No. DE-FG03-92ER75838 A000, a three year matching grant program with Pacific Gas and Electric Company (PG and E) to support strengthening of the fission reactor nuclear science and engineering program at UCLA. The program began on September 30, 1992. The program has enabled UCLA to use its strong existing background to train students in technological problems which simultaneously are of interest to the industry and of specific interest to PG and E. The program included undergraduate scholarships, graduate traineeships and distinguished lecturers. Four topics were selected for research the first year, with the benefit of active collaboration with personnel from PG and E. These topics remained the same during the second year of this program. During the third year, two topics ended with the departure o the students involved (reflux cooling in a PWR during a shutdown and erosion/corrosion of carbon steel piping). Two new topics (long-term risk and fuel relocation within the reactor vessel) were added; hence, the topics during the third year award were the following: reflux condensation and the effect of non-condensable gases; erosion/corrosion of carbon steel piping; use of artificial intelligence in severe accident diagnosis for PWRs (diagnosis of plant status during a PWR station blackout scenario); the influence on risk of organization and management quality; considerations of long term risk from the disposal of hazardous wastes; and a probabilistic treatment of fuel motion and fuel relocation within the reactor vessel during a severe core damage accident

  14. Test and evaluation of Alco/BLH prototype sodium-heated steam generator. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Kaplan, C.J.; Auge, L.J.; Cho, S.M.; Hanna, R.W.; Prevost, J.R.; Steger, N.A.; Wagner, R.K.

    1971-01-31

    A 30-Mwt prototype sodium-to-sodium intermediate heat exchanger and a 30-Mwt prototype sodium-heated steam generator were tested in combined operation in its Sodium Components Test Installation. This report contains the results of test and evaluation of the steam generator. During plant performance tests, performance degradation was observed, which resulted in the initiation of a diagnostic test series. This test series revealed that under certain operating conditions, the thermohydraulic characteristic of the steam generator changed either suddenly or gradually, resulting in overall performance degradation. A structural failure, requiring retirement of the unit, occurred before the diagnostic test series and analytical support effort were completed. This report describes the thermohydraulic and structural performance, including the structural failures, and related evaluation analyses of the Alco/BLH prototype steam generator performed prior to termination of the test and evaluation program. In addition, the report presents a post-test examination plan to obtain data that could possibly explain the cause of performance anomalies and structural failures experienced during testing.

  15. BWR Full Integral Simulation Test (FIST) program: facility description report

    International Nuclear Information System (INIS)

    Stephens, A.G.

    1984-09-01

    A new boiling water reactor safety test facility (FIST, Full Integral Simulation Test) is described. It will be used to investigate small breaks and operational transients and to tie results from such tests to earlier large-break test results determined in the TLTA. The new facility's full height and prototypical components constitute a major scaling improvement over earlier test facilities. A heated feedwater system, permitting steady-state operation, and a large increase in the number of measurements are other significant improvements. The program background is outlined and program objectives defined. The design basis is presented together with a detailed, complete description of the facility and measurements to be made. An extensive component scaling analysis and prediction of performance are presented

  16. EBR-2 [Experimental Breeder Reactor-2] test programs

    International Nuclear Information System (INIS)

    Sackett, J.I.; Lehto, W.K.; Lindsay, R.W.; Planchon, H.P.; Lambert, J.D.B.; Hill, D.J.

    1990-01-01

    The Experimental Breeder Reactor-2 (EBR-2) is a sodium cooled power reactor supplying about 20 MWe to the Idaho National Engineering Laboratory (INEL) grid and, in addition, is the key component in the development of the Integral Fast Reactor (IFR). EBR-2's testing capability is extensive and has seen four major phases: (1) demonstration of LMFBR power plant feasibility, (2) irradiation testing for fuel and material development, (3) testing the off-normal performance of fuel and plant systems and (4) operation as the IFR prototype, developing and demonstrating the IFR technology associated with fuel and plant design. Specific programs being carried out in support of the IFR include advanced fuels and materials development, advanced control system development, plant diagnostics development and component testing. This paper discusses EBR-2 as the IFR prototype and the associated testing programs. 29 refs

  17. A compliance testing program for diagnostic X-ray equipment

    International Nuclear Information System (INIS)

    Hutchinson, D.E.; Cobb, B.J.; Jacob, C.S.

    1999-01-01

    Compliance testing is nominally that part of a quality assurance program dealing with those aspects of X-ray equipment performance that are subject to radiation control legislation. Quality assurance programs for medical X-ray equipment should be an integral part of the quality culture in health care. However while major hospitals and individual medical centers may implement such programs with some diligence, much X-ray equipment can remain unappraised unless there is a comprehensive regulatory inspection program or some form of compulsion on the equipment owner to implement a testing program. Since the late 1950s all X-ray equipment in the State of Western Australia has been inspected by authorized officers acting on behalf of the Radiological Council, the regulatory authority responsible for administration of the State's Radiation Safety Act. However, economic constraints, coupled with increasing X-ray equipment numbers and a geographically large State have significantly affected the inspection rate. Data available from inspections demonstrate that regular compliance and performance checks are essential in order to ensure proper performance and to minimize unnecessary patient and operator dose. To ensure that diagnostic X-ray equipment complies with accepted standards and performance criteria, the regulatory authority introduced a compulsory compliance testing program for all medical, dental and chiropractic diagnostic X-ray equipment effective from 1 January 1997

  18. Framework for a National Testing and Evaluation Program ...

    Science.gov (United States)

    Abstract:The National STEPP Program seeks to improve water quality by accelerating the effective implementation and adoption of innovative stormwater management technologies. Itwill attempt to accomplish this by establishing practices through highly reliable, and cost-effective Stormwater control measures (SCM) testing, evaluation, and verification services. The program will aim to remove barriers to innovation, minimize duplicative performance evaluation needs, increase confidence that regulatory requirements are met by creating consistency among testing and evaluation protocols, and establishing equity between public domain and proprietary SCM evaluation approaches.The Environmental Technology Verification Program, established by the U.S. Environmental Protection Agency (EPA) 18 years ago, was the only national program of its kindin the stormwater sector, but is now defunct, leaving a national leadership void. The STEPP initiative was triggered in part by regulatory demands in the government and private sectors to fill this vacuum. A concerted focus and study of this matter led to the release of a Water Environment Federation (WEF) white paper entitled “Investigation into the Feasibility of a National Testing and Evaluation Program for Stormwater Products and Practices” in February 2014. During this second phase of the STEPP initiative, and with EPA support, five analogous technology evaluation programs related to both stormwater and non-stormwater were an

  19. Wireless Roadside Inspection Phase II Tennessee Commercial Mobile Radio Services Pilot Test Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Franzese, Oscar [ORNL; Lascurain, Mary Beth [ORNL; Capps, Gary J [ORNL; Siekmann, Adam [ORNL

    2011-05-01

    The Federal Motor Carrier Safety Administration (FMCSA) Wireless Roadside Inspection (WRI) Program is researching the feasibility and value of electronically assessing truck and bus driver and vehicle safety at least 25 times more often than is possible using only roadside physical inspections. The WRI program is evaluating the potential benefits to both the motor carrier industry and to government. These potential benefits include reduction in accidents, fatalities and injuries on our highways and keeping safe and legal drivers and vehicles moving on the highways. WRI Pilot tests were conducted to prototype, test and demonstrate the feasibility and benefits of electronically collecting safety data message sets from in-service commercial vehicles and performing wireless roadside inspections using three different communication methods. This report summarizes the design, conduct and results of the Tennessee CMRS WRI Pilot Test. The purpose of this Pilot test was to demonstrate the implementation of commercial mobile radio services to electronically request and collect safety data message sets from a limited number of commercial vehicles operating in Tennessee. The results of this test have been used in conjunction with the results of the complimentary pilot tests to support an overall assessment of the feasibility and benefits of WRI in enhancing motor carrier safety (reduction in accidents) due to increased compliance (change in motor carrier and driver behavior) caused by conducting frequent safety inspections electronically, at highway speeds, without delay or need to divert into a weigh station

  20. Healy Clean Coal Project: Healy coal firing at TRW Cleveland Test Facility. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Koyama, T.; Petrill, E.; Sheppard, D.

    1991-08-01

    A test burn of two Alaskan coals was conducted at TRW`s Cleveland test facility in support of the Healy Clean Coal Project, as part of Clean Coal Technology III Program in which a new power plant will be constructed using a TRW Coal Combustion System. This system features ash slagging technology combined with NO{sub x} and SO{sub x} control. The tests, funded by the Alaska Industrial Development and Export Authority (AIDEA) and TRW, were conducted to verify that the candidate Healy station coals could be successfully fired in the TRW coal combustor, to provide data required for scale-up to the utility project size requirements, and to produce sufficient flash-calcined material (FCM) for spray dryer tests to be conducted by Joy/NIRO. The tests demonstrated that both coals are viable candidates for the project, provided the data required for scale-up, and produced the FCM material. This report describes the modifications to the test facility which were required for the test burn, the tests run, and the results of the tests.