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Sample records for testing technical progress

  1. PFBC HGCU Test Facility. Technical progress report No. 24, Third quarter, CY 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    This is the twenty-fourth and final Technical Progress Report submitted to the Department of Energy (DOE) in connection with the cooperative agreement between the DOE and Ohio Power Company for the Tidd PFBC Hot Gas Clean Up Test Facility. This report covers the work completed during the Third Quarter of CY 1995. All activity this quarter was directed toward the completion of the program final report. A draft copy of the final report was forwarded to DOE during this quarter, and DOE submitted their comments on the report to AEPSC. DOE requested that Westinghouse write an appendix to the report covering the performance of the fail-safe regenerator devices during Tad operation, and Westinghouse subsequently prepared the appendix. Additional DOE comments were incorporated into the report, and it will be issued in camera-ready form by the end of October, 1995, which is the program end date. Appendix 1 presents the results of filter candle posttest examination by Westinghouse performed on selected filter candles following final shutdown of the system.

  2. Technical Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    Paul D. Ronney

    2004-08-26

    An ignition source was constructed that is capable of producing a pulsed corona discharge for the purpose of igniting mixtures in a test chamber. The corona generator can also be used as the ignition source for one cylinder on a test engine. The first tests were performed in a cylindrical shaped chamber to study the characteristics of the corona and analyze various electrode geometries. Next a test chamber was constructed that closely represented the dimensions of the combustion chamber of the test engine at USC. Combustion tests were performed in this chamber and various electrode diameters and geometries were tested. Higher peak pressures and faster pressure rise times were realized consistently in all test chambers versus standard spark plug ignition. A test engine was purchased for the project that has two spark plug ports per cylinder to The data acquisition and control system hardware for the USC engine lab was updated with new equipment. New software was also developed to perform the engine control and data acquisition functions including cylinder pressure monitoring. A ceramic corona electrode has been designed that fits in the new test engine and is capable of withstanding the pressures and temperatures encountered inside the combustion chamber. The corona ignition system was tested on the engine and an increase in both peak pressure and IMEP were seen in the initial test. There are issues that must be addressed before on-engine testing can continue such as EMF interference from the corona generator and electrical insulation on portions of the piston and cylinder head to prevent arcing. The EMF issue can be solved with proper shielding and grounding and various ceramic coatings are being researched for electrical insulation.

  3. Technical progress report

    International Nuclear Information System (INIS)

    1996-01-01

    This report summarizes experimental and theoretical work in basic nuclear physics carried out between October 1, 1995, the closing of our last Progress Report, and September 30, 1996 at the Nuclear Physics Laboratory of the University of Colorado, Boulder, under contracts DE-FG03-93ER-40774 and DE-FG03-95ER-40913 with the United States Department of Energy. The experimental contract supports broadly-based experimental research in intermediate energy nuclear physics. This report includes results from studies of Elementary Systems involving the study of the structure of the nucleon via polarized high-energy positron scattering (the HERMES experiment) and lower energy pion scattering from both polarized and unpolarized nucleon targets. Results from pion- and kaon-induced reactions in a variety of nuclear systems are reported under the section heading Meson Reactions; the impact of these and other results on understanding the nucleus is presented in the Nuclear Structure section. In addition, new results from scattering of high-energy electrons (from CEBAF/TJNAF) and pions (from KEK) from a broad range of nuclei are reported in the section on Incoherent Reactions. Finally, the development and performance of detectors produced by the laboratory are described in the section titled Instrumentation

  4. Final Technical Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    J.Y. Hwang; R.C. Greenlund

    2002-12-31

    Michigan Technological University has demonstrated major inroads in establishing the viability of utilizing aluminum smelting by-product waste materials in lightweight concrete product applications. The research identified key elements of producing various forms of lightweight concrete products through utilizing various procedures and mixture components with the by-product materials. A process was developed through pilot plant testing that results in additional aluminum recovery at finer sizes, a clean returnable salt product through spray drying technology, and a low-salt-content oxide product with enough aluminum metal content that it can be used to form lightweight cementitious mixtures. Having three distinct products aids in generating favorable process economics. Revenue projections from aluminum recovery and salt recovery are enough to cover processing costs and create a cost-free oxide product to market for lightweight concrete applications. This supply side commercialization strategy offers aluminum by-product recyclers a potentially no cost product, which has been demonstrated through this project to create desirable and marketable lightweight concrete products of various forms. Environmental benefits to the public are tremendous. At best, all dross and salt cake materials have the potential to be completely recycled and utilized. At worst, disposal sites would see a reduced amount of material: a post processed oxide product with little salt and no hydrogen sulfide or ammonia gas generating capability, which, if isolated from high alkali conditions, would pose no reactivity concerns. The US aluminum industry has historically, along with the steel industry, been a leader in recycling metal. The findings from this project, increased metal recovery, improved salt recycling, and demonstrated end uses for oxide residues, will go a long way in helping the aluminum industry obtain 100% material utilization and zero discharge.

  5. Diagnostic development and support of MHD test facilities: Technical progress report for the period January, February, March 1985

    International Nuclear Information System (INIS)

    Shepard, W.S.; Cook, R.L.

    1985-04-01

    Mississippi State University is developing diagnostic instruments for MHD power train data acquisition and for support of MHD component development test facilities. Microprocessor-controlled optical instruments, initially developed for HRSR support, are being refined, and new systems to measure temperatures and gas-seed-slag stream characteristics are being developed. To further data acquisition and analysis capabilities, the diagnostic systems are being interfaced with MHD Energy Center computers. Additionally, technical support of the diagnostic needs of the national MHD research effort is being provided

  6. High temperature turbine technology program. Phase II. Technology test and support studies. Annual technical progress report, January 1, 1979-December 31, 1979

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    Work performed on the High Temperature Turbine Technology Program, Phase II - Technology Test and Support Studies during the period from January 1, 1979 through December 31, 1979 is summarized. Objectives of the program elements as well as technical progress and problems encountered during this Phase II annual reporting period are presented. Progress on design, fabrication and checkout of test facilities and test rigs is described. LP turbine cascade tests were concluded. 350 hours of testing were conducted on the LP rig engine first with clean distillate fuel and then with fly ash particulates injected into the hot gas stream. Design and fabrication of the turbine spool technology rig components are described. TSTR 60/sup 0/ sector combustor rig fabrication and testing are reviewed. Progress in the design and fabrication of TSTR cascade rig components for operation on both distillate fuel and low Btu gas is described. The new coal-derived gaseous fuel synthesizing facility is reviewed. Results and future plans for the supporting metallurgical programs are discussed.

  7. Technical progress and climatic change

    International Nuclear Information System (INIS)

    Ausubel, J.H.

    1995-01-01

    The global warming debate has neglected and thus underestimated the importance of technical change in considering reduction in greenhouse gases and adaptation to climate change. Relevant quantitative cases of long-run technical change during the past 100 years are presented in computing, communications, transport, energy, and agriculture. A noteworthy technological trajectory is that of decarbonization, or decreasing carbon intensity of primary energy. If human societies have not yet reached the end of the history of technology, the cost structure for mitigation and adaptation changes could be cheap. (Author)

  8. Progress test utopia.

    Science.gov (United States)

    van der Vleuten, Cees; Freeman, Adrian; Collares, Carlos Fernando

    2018-04-01

    This paper discusses the advantages of progress testing. A utopia is described where medical schools would work together to develop and administer progress testing. This would lead to a significant reduction of cost, an increase in the quality of measurement and phenomenal feedback to learner and school. Progress testing would also provide more freedom and resources for more creative in-school assessment. It would be an educationally attractive alternative for the creation of cognitive licensing exams. A utopia is always far away in the future, but by formulating a vision for that future we may engage in discussions on how to get there.

  9. Bench-scale testing of on-line control of column flotation using a novel analyzer. Third quarterly technical progress report, April 1, 1993--June 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-24

    This document contains the third quarterly technical progress report for PTI`s Bench-Scale Testing Project of a circuit integrating PTI`s KEN-FLOTETM Column Flotation Technology and PTI`s On-Line Quality Monitor and Control System. The twelve-month project involves installation and testing of a 200--300 lb/hr. bench-scale flotation circuit at PETC`s Coal Preparation Process Research Facility (CPPRF) for two bituminous coals (Upper Freeport and Pittsburgh No. 8 Seam Raw Coals). Figure 1 contains the project plan, as well as the approach to completing the major tasks within the twelve-month project schedule. The project is broken down into three phases, which include: Phase I -- Preparation: The preparation phase was performed principally at PTI`s Calumet offices from October through December, 1992. It involved building of the equipment and circuitry, as well as some preliminary design and equipment testing; Phase II -- ET Circuit Installation and Testing: This installation and testing phase of the project was performed at PETC`s CPPRF from January through June, 1993, and was the major focus of the project. It involved testing of the continuous 200--300 lb/hr. circuit; and Phase III -- Project Finalization: The project finalization phase is occurring from July through September, 1993, at PTI`s Calumet offices and involves finalizing analytical work and data evaluation, as well as final project reporting. This Third Quarterly Technical Progress Report principally summarizes the results from the benchscale testing with the second coal (Pittsburgh No. 8 Seam Coal), which occurred in April through June, 1993. It also contains preliminary economic evaluations that will go into the Final Report, as well as the plan for the final reporting task.

  10. Progress report : Technical Physics Division

    International Nuclear Information System (INIS)

    Gopalaraman, C.P.; Deshpande, R.Y.

    1978-01-01

    The research and development work carried out in the Technical Physics Division of the Bhabha Atomic Research Centre, Bombay, is reported. Some of the achievements are: (1) fabrication of mass spectrometers for heavy water analysis and lithium 6/7 isotope ratio measurement, (2) fabrication of electronic components for mass spectrometers, (3) growing of sodium iodide crystals for radiation detectors, (4) development of sandwich detectors comprising of NaI(Tl) and CaI(Na), (5) fabrication of mass spectrometer type leak detectors and (6) fabrication of the high vacuum components of the vacuum system of the variable energy cyclotron based at Calcutta. (M.G.B.)

  11. 48 CFR 2052.211-71 - Technical progress report.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 6 2010-10-01 2010-10-01 true Technical progress report... Technical progress report. As prescribed at 2011.104-70(b), the contracting officer shall insert the... solicitation. Technical Progress Report (JAN 1993) The contractor shall provide a monthly Technical Progress...

  12. Technical progress by major task. Semiannual technical progress report, September 29, 1997 - March 29, 1998

    International Nuclear Information System (INIS)

    1998-01-01

    The technical progress achieved during the period 29 September 1997 through 29 March 1998 on Contract DE-AC03-91SF18852 Radioisotope Thermoelectric Generators and Ancillary Activities is described in this report. The report is organized by program task structure: spacecraft integration and liaison; engineering support; safety; qualified unicouple production; RTG fabrication, assembly, and test; ground support equipment; RTG shipping and launch support; designs, reviews, and mission applications; project management, quality assurance, reliability, contract changes, CAGO acquisition (operating funds), and CAGO maintenance and repair

  13. Hot gas cleanup test facility for gasification and pressurized combustion. Quarterly technical progress report, July 1--September 30, 1992

    Energy Technology Data Exchange (ETDEWEB)

    1992-12-31

    The objective of this project is to evaluate hot gas particle control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scale-up of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phased expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the existing Transport Reactor gas source and Hot Gas Cleanup Units: Carbonizer/Pressurized Circulating Fluidized Bed Gas Source; hot Gas Cleanup Units to mate to all gas streams; and Combustion Gas Turbine. Fuel Cell and associated gas treatment. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF).

  14. A coupled mechanical-hydrological investigation of crystalline rocks: Annual technical progress report, proposed test matrix, and preliminary results

    International Nuclear Information System (INIS)

    Bastian, R.J.; Voss, C.F.; Apted, M.J.; Shotwell, L.R.

    1988-02-01

    This report reviews the Fracture Flow Behavior in Rock Study being performed at the Pacific Northwest Laboratory. The study's objective is to determine the feasibility of predicting mechanical-hydrological behavior of natural rock fractures by accurately characterizing fracture surface topography and mineralization. A laboratory-scale facility is currently being used to ensure optimum control of variables. Devising a technique to study small-scale samples is the first step to understanding the complex coupled processes encountered in geomechanics and hydrology. The major accomplishments during fiscal year 1987 were initial development of the innovative testing method, identification of appropriate specimens, substantial renovation to the facility, completion of several sets of experiments, and procurement of hardware components for a laser-imaging device used to characterize fracture surfaces. A complete set of preliminary results and findings is presented in this report. These results, gathered from a basalt core with a natural fracture, have demonstrated that the methodology is valid, and definite trends in the data are readily apparent. 10 refs., 14 figs., 1 tab

  15. Technical progress and its strategic consequences

    International Nuclear Information System (INIS)

    Bouchard, G.

    1999-01-01

    The history of energy during recent decades has shown that technical progress can have consequences for the organisation of markets, company strategies and the economy in general, confounding all forecasts and going beyond simple technical change. As a consequence for example, improvements in the techniques concerning the exploration and production of hydrocarbons have led to the petrol 'counter-crisis', the reduction in the power of OPEC and undreamed of gains in wealth for certain countries. The progress in gas turbines has led to the reversal of the age-old tendency towards increases in the size of electricity production units and encouraged the liberation of this sector. When looking at the future it is therefore judicious to try and understand the forces at work, and the major trends which result. This is the aim of the articles in this edition of the Revue de l'Energie, published on the occasion of the European colloquium on 'Technical progress faced with the challenges of the energy sector in the future' organised by the Association of Energy Economists. (authors)

  16. International linear collider. A technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    Arnold, Ned [Argonne National Laboratory, IL (United States); Aderhold, Sebastian [DESY, Hamburg (Germany); Adolphsen, Chris [Stanford Linear Accelerator Center, Menlo Park, CA (United States); and others

    2012-07-01

    The International Linear Collider: A Technical Progress Report marks the halfway point towards the Global Design Effort fulfilling its mandate to follow up the ILC Reference Design Report with a more optimised Technical Design Report (TDR) by the end of 2012. The TDR will be based on much of the work reported here and will contain all the elements needed to propose the ILC to collaborating governments, including a technical design and implementation plan that are realistic and have been better optimised for performance, cost and risk. We are on track to develop detailed plans for the ILC, such that once results from the Large Hadron Collider (LHC) at CERN establish the main science goals and parameters of the next machine, we will be in good position to make a strong proposal for this new major global project in particle physics. The two overriding issues for the ILC R and D programme are to demonstrate that the technical requirements for the accelerator are achievable with practical technologies, and that the ambitious physics goals can be addressed by realistic ILC detectors. This GDE interim report documents the impressive progress on the accelerator technologies that can make the ILC a reality. It highlights results of the technological demonstrations that are giving the community increased confidence that we will be ready to proceed with an ILC project following the TDR. The companion detector and physics report document likewise demonstrates how detector designs can meet the ambitious and detailed physics goals set out by the ILC Steering Committee. LHC results will likely affect the requirements for the machine design and the detectors, and we are monitoring that very closely, intending to adapt our design as those results become available.

  17. Progress in design, research and development and testing of safety systems for advanced water cooled reactors. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1996-04-01

    The meeting covered the following topics: Developments in design of safety-related heat removal components and systems for advanced water cooled reactors; status of test programmes on heat removal components and systems of new designs; range of validity and extrapolation of test results for the qualification of design/licensing computer models and codes for advanced water cooled reactors; future needs and trends in testing of safety systems for advanced water cooled reactors. Tests of heat removal safety systems have been conducted by various groups supporting the design, testing and certification of advanced water cooled reactors. The Technical Committee concluded that the reported test results generally confirm the predicted performance features of the advanced designs. Refs, figs, tabs

  18. Progress in design, research and development and testing of safety systems for advanced water cooled reactors. Proceedings of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    The meeting covered the following topics: Developments in design of safety-related heat removal components and systems for advanced water cooled reactors; status of test programmes on heat removal components and systems of new designs; range of validity and extrapolation of test results for the qualification of design/licensing computer models and codes for advanced water cooled reactors; future needs and trends in testing of safety systems for advanced water cooled reactors. Tests of heat removal safety systems have been conducted by various groups supporting the design, testing and certification of advanced water cooled reactors. The Technical Committee concluded that the reported test results generally confirm the predicted performance features of the advanced designs. Refs, figs, tabs.

  19. Sludge Treatment Evaluation: 1992 Technical progress

    International Nuclear Information System (INIS)

    Silva, L.J.; Felmy, A.R.; Ding, E.R.

    1993-01-01

    This report documents Fiscal Year 1992 technical progress on the Sludge Treatment Evaluation Task, which is being conducted by Pacific Northwest Laboratory. The objective of this task is to develop a capability to predict the performance of pretreatment processes for mixed radioactive and hazardous waste stored at Hanford and other US Department of Energy (DOE) sites. Significant cost savings can be achieved if radionuclides and other undesirable constituents can be effectively separated from the bulk waste prior to final treatment and disposal. This work is initially focused on chemical equilibrium prediction of water washing and acid or base dissolution of Hanford single-shell tank (SST) sludges, but may also be applied to other steps in pretreatment processes or to other wastes. Although SST wastes contain many chemical species, there are relatively few constituents -- Na, Al, NO 3 , NO 2 , PO 4 , SO 4 , and F -- contained in the majority of the waste. These constituents comprise 86% and 74% of samples from B-110 and U-110 SSTS, respectively. The major radionuclides of interest (Cs, Sr, Tc, U) are present in the sludge in small molal quantities. For these constituents, and other important components that are present in small molal quantities, the specific ion-interaction terms used in the Pitzer or NRTL equations may be assumed to be zero for a first approximation. Model development can also be accelerated by considering only the acid or base conditions that apply for the key pretreatment steps. This significantly reduces the number of chemical species and chemical reactions that need to be considered. Therefore, significant progress can be made by developing all the specific ion interactions for a base model and an acid dissolution model

  20. Sludge Treatment Evaluation: 1992 Technical progress

    Energy Technology Data Exchange (ETDEWEB)

    Silva, L J; Felmy, A R; Ding, E R

    1993-01-01

    This report documents Fiscal Year 1992 technical progress on the Sludge Treatment Evaluation Task, which is being conducted by Pacific Northwest Laboratory. The objective of this task is to develop a capability to predict the performance of pretreatment processes for mixed radioactive and hazardous waste stored at Hanford and other US Department of Energy (DOE) sites. Significant cost savings can be achieved if radionuclides and other undesirable constituents can be effectively separated from the bulk waste prior to final treatment and disposal. This work is initially focused on chemical equilibrium prediction of water washing and acid or base dissolution of Hanford single-shell tank (SST) sludges, but may also be applied to other steps in pretreatment processes or to other wastes. Although SST wastes contain many chemical species, there are relatively few constituents -- Na, Al, NO[sub 3], NO[sub 2], PO[sub 4], SO[sub 4], and F -- contained in the majority of the waste. These constituents comprise 86% and 74% of samples from B-110 and U-110 SSTS, respectively. The major radionuclides of interest (Cs, Sr, Tc, U) are present in the sludge in small molal quantities. For these constituents, and other important components that are present in small molal quantities, the specific ion-interaction terms used in the Pitzer or NRTL equations may be assumed to be zero for a first approximation. Model development can also be accelerated by considering only the acid or base conditions that apply for the key pretreatment steps. This significantly reduces the number of chemical species and chemical reactions that need to be considered. Therefore, significant progress can be made by developing all the specific ion interactions for a base model and an acid dissolution model.

  1. Works Technical Department progress report, March 1961

    Energy Technology Data Exchange (ETDEWEB)

    None

    1961-04-19

    This document details the activities of the Savannah River Works Technical Department during the month of March 1961. Topics discussed are: Reactor Technology, Separations Technology, Engineering Assistance, Health Physics, Laboratories Overview, and Technical Papers Issued.

  2. FMIT Test assemblies. Progress report

    International Nuclear Information System (INIS)

    Nygren, R.E.; Opperman, E.K.

    1978-08-01

    This progress report is a reference document for a number of inter-related tasks supporting the Fusion Materials Irradiation Test (FMIT) Facility being developed by the Hanford Engineering Development Laboratory. The report describes the basic configuration of test assemblies and supporting rationale based on the neutron flux distribution. Perturbed and unperturbed flux profiles are discussed as well as heating rates and cooling requirements

  3. Materials testing and requirements for the ERDA nuclear-powered artificial heart. Technical progress report, July 15, 1974--May 1, 1975

    International Nuclear Information System (INIS)

    Andrade, J.D.; Coleman, D.L.; Leigh, A.; Hufferd, W.L.

    1975-01-01

    Progress on the materials research and development effort for the ERDA-sponsored nuclear-powered artificial heart program is presented. Progress made during the first three years on hydrogel grafting and biological studies is summarized. Progress during the fourth year on studies of implanted artificial hearts, development of albumin surfaces, and in vitro mechanical studies is presented. (U.S.)

  4. Solar lease grant program. Technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    1981-04-01

    Progress on a lease program for the installation of a solar water heater with no installation charge is reported. Information on the announcement of the program, the selection of participants, the contractural agreement, progress on installation of equipment, monitoring, and evaluation is summarized. The status of the budget concerned with the program is announced. Forms used for applications for the program and an announcement from Resource Alternatives for Cilco customers are presented.

  5. Nuclear theory research. Technical progress report

    International Nuclear Information System (INIS)

    1982-01-01

    Progress is briefly described on the following studies: (1) Dirac phenomenology for deuteron elastic scattering, (2) Dirac wave functions in nuclear distorted wave calculations, (3) impulse approximation for p→p → dπ + reaction above the 3-3 resonance, (4) coherent π production, (5) nuclear potentials from Dirac bound state wavefunctions, (6) nonlocality effects in nuclear reactions, (7) unhappiness factors in DWBA description of (t,p) and (p,t) reactions, (8) absolute normalization of three-nucleon transfer reactions, (9) formulation of a finite-range CCBA computer program, (10) crossing symmetric solutions of the low equations, (11) pion scattering from quark bags, (12) study of the p 11 channel in the delta model, (13) isovector corrections in pion-nucleus scattering, (14) pionic excitation of nuclear giant resonances, and (15) isospin dependence of the second-order pion-nucleus optical potential

  6. Progress report [of] Technical Physics Division

    International Nuclear Information System (INIS)

    Vijendran, P.; Deshpande, R.Y.

    1975-01-01

    Activities of the Technical Physics Division of the Bhabha Atomic Research Centre, Bombay, over the last few years are reported. This division is engaged in developing various technologies supporting the development of nuclear technology. The various fields in which development is actively being carried out are : (i) vacuum technology, (ii) mass spectrometry, (iii) crystal technology, (iv) cryogenics, and (v) magnet technology. For surface studies, the field emission microscope and the Auger electron spectrometer and other types of spectrometers have been devised and perfected. Electromagnets of requisite strength to be used in MHD programme and NMR instruments are being fabricated. Various crystals such as NaI(Tl), Ge, Fluorides, etc. required as windows and prisms in X and gamma-ray spectroscopy, have been grown. In the cryogenics field, expansion engines required for air liquefaction plants, vacuum insulated dewars, helium gas thermometers etc. have been constructed. In addition to the above, the Division provides consultancy and training to personnel from various institutions and laboratories. Equipment and systems perfected are transferred to commercial organizations for regular production. (A.K.)

  7. Materials testing and requirement for the ERDA nuclear-powered artificial heart. Technical progress report, July 15, 1975--May 30, 1976. [BIOMER and AVCOTHANE

    Energy Technology Data Exchange (ETDEWEB)

    Andrade, J. D.; Hufferd, W. L.; Lyman, D. J.

    1976-01-01

    The two materials currently being used for the artificial heart fabrication are BIOMER and AVCOTHANE. BIOMER is a polyether urethane polymer. AVCOTHANE is a proprietary polyurethane/polydimethylsiloxane polymer blend. Research progress on the chemical degradation, mechanical strength, and blood compatibility is reported. (TFD)

  8. Materials testing and requirement for the ERDA nuclear-powered artificial heart. Technical progress report, July 15, 1975--May 30, 1976

    International Nuclear Information System (INIS)

    Andrade, J.D.; Hufferd, W.L.; Lyman, D.J.

    1976-01-01

    The two materials currently being used for the artificial heart fabrication are BIOMER and AVCOTHANE. BIOMER is a polyether urethane polymer. AVCOTHANE is a proprietary polyurethane/polydimethylsiloxane polymer blend. Research progress on the chemical degradation, mechanical strength, and blood compatibility is reported

  9. Development and testing of industrial scale, coal fired combustion system, Phase 3. Eighteenth quarterly technical progress report, April 1, 1996--June 30, 1996

    Energy Technology Data Exchange (ETDEWEB)

    Zauderer, B.

    1996-08-18

    In the second quarter of calendar year 1996, 16 days of combust- boiler tests were performed, including 2 days of tests on a parallel DOE sponsored project on sulfur retention in a slagging combustor. Between tests, modifications and improvements that were indicated by these tests were implemented. This brings the total number of test days to the end of June in the task 5 effort to 28, increased to 36 as of the date of this Report, 8/18/96. This compares with a total of 63 test days needed to complete the task 5 test effort. It is important to note that the only major modification to the Williamsport combustor has been the addition of a new downstream section, which lengthens the combustor and improves the combustor-boiler interface. The original combustor section, which includes the fuel, air, and cooling water delivery systems remained basically unchanged. Only the refractory liner was completely replaced, a task which occurs on an annual basis in all commercial slagging utility combustors. Therefore, this combustor has been operated since 1988 without replacement. The tests in the present reporting period are of major significance in that beginning with the first test on March 31st, for the first time slagging opening conditions were achieved in the upgraded combustor. The first results showed that the present 20 MMBtu/hr combustor design is far superior to the previous one tested since 1988 in Williamsport, PA. The most important change is that over 95% of the slag was drained from the slag tap in the combustor. This compares with an range of one-third to one-half in Williamsport. In the latter, the balance of the slag flowed out of the exit nozzle into the boiler floor. In addition, the overall system performance, including the combustor, boiler, and stack equipment, ranged from good to excellent. Those areas requiring improvement were of a nature that could be corrected with some work. but in no case were the problems encountered of a barrier type.

  10. ERIP invention 637. Technical progress report 2nd quarter, April 1997--June 1997

    Energy Technology Data Exchange (ETDEWEB)

    Thacker, G.W.

    1997-07-22

    This technical report describes progress in the development of the Pegasus plow, a stalk and root embedding apparatus. Prototype testing is reported, and includes the addition of precision tillage. Disease data, organic matter, and nitrogen levels results are very briefly described. Progress in marketing is also reported. Current marketing issues include test use by cotton and wheat growers, establishment of dealer relationships, incorporation of design modifications, expansion of marketing activities, and expansion of loan and lease program.

  11. FY 1992 work plan and technical progress reports

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-11-01

    The Desert Research Institute (DRI) is a division of the University of Nevada System devoted to multidisciplinary scientific research. For more than 25 years, DRI has conducted research for the US Department of Energy`s Nevada Field Office (DOE/NV) in support of operations at the Nevada Test Site (NTS). During that time, the research program has grown from an early focus on hydrologic studies to include the areas of geology, archaeology, environmental compliance and monitoring, statistics, database management, public education, and community relations. The range of DRI`s activities has also expanded to include a considerable amount of management and administrative support in addition to scientific investigations. DRI`s work plan for FY 1992 reflects a changing emphasis in DOE/NV activities from nuclear weapons testing to environmental restoration and monitoring. Most of the environmental projects from FY 1991 are continuing, and several new projects have been added to the Environmental Compliance Program. The Office of Technology Development Program, created during FY 1991, also includes a number of environmental projects. This document contains the FY 1992 work plan and quarterly technical progress reports for each DRI project.

  12. Annual technical progress report: reactor safety, Government fiscal year 1978

    International Nuclear Information System (INIS)

    1978-01-01

    Progress in LMFBR safety studies on accident debris behavior is reported under the following subtask titles: high-temperature-concentration aerosols, large-scale molten fuel tests, sodium release tests, and risk analysis

  13. Swallowable Wireless Capsule Endoscopy: Progress and Technical Challenges

    Directory of Open Access Journals (Sweden)

    Guobing Pan

    2012-01-01

    Full Text Available Wireless capsule endoscopy (WCE offers a feasible noninvasive way to detect the whole gastrointestinal (GI tract and revolutionizes the diagnosis technology. However, compared with wired endoscopies, the limited working time, the low frame rate, and the low image resolution limit the wider application. The progress of this new technology is reviewed in this paper, and the evolution tendencies are analyzed to be high image resolution, high frame rate, and long working time. Unfortunately, the power supply of capsule endoscope (CE is the bottleneck. Wireless power transmission (WPT is the promising solution to this problem, but is also the technical challenge. Active CE is another tendency and will be the next geneion of the WCE. Nevertheless, it will not come true shortly, unless the practical locomotion mechanism of the active CE in GI tract is achieved. The locomotion mechanism is the other technical challenge, besides the challenge of WPT. The progress about the WPT and the active capsule technology is reviewed.

  14. Sandia Laboratories technical capabilities: testing

    International Nuclear Information System (INIS)

    Lundergan, C.D.

    1975-12-01

    The testing capabilities at Sandia Laboratories are characterized. Selected applications of these capabilities are presented to illustrate the extent to which they can be applied in research and development programs

  15. Nuclear waste glass melter: an update of technical progress

    International Nuclear Information System (INIS)

    Brouns, R.A.; Hanson, M.S.

    1984-08-01

    The direct slurry-fed ceramic-lined melter is currently the reference US process for treating defense and civilian high-level liquid waste. Extensive nonradioactive pilot-scale testing at Pacific Northwest Laboratory (PNL) and Savannah River Laboratory has proven the process, defined operating parameters, and identified successful equipment design concepts. Programs at PNL continue to support several of the planned US vitrification plants through preparation of equipment designs and flowsheet testing. Current emphasis is on remotization of equipment, radioactive verification testing, and resolution of remaining technical issues. Development of this technology, technical status, and planned development activities are discussed. 9 references, 4 figures

  16. Cassini RTG Program. Monthly technical progress report, 27 November--31 December 1995

    International Nuclear Information System (INIS)

    1996-01-01

    This monthly technical progress report provided information on the following tasks: spacecraft integration and liaison; engineering support; safety analysis; qualified unicouple fabrication; ETG fabrication, assembly, and test; ground support equipment (GSE); RTG shipping and launch support; designs, reviews, and mission applications; project management, quality assurance, and reliability, and contractor acquired government owned (CAGO) property acquisition

  17. Technical Progress of the New Worlds Observer Mission

    Science.gov (United States)

    Lo, Amy; Noecker, C.; Cash, W.; NWO Study Team

    2009-01-01

    We report on the technical progress of the New Worlds Observer (NWO) mission concept. NWO is a two spacecraft mission that is capable of detecting and characterizing extra-solar, terrestrial planets and planetary systems. NWO consists of an external starshade and an UV-optical space telescope, flying in tandem. The starshade is a petal-shaped, opaque screen that creates an extremely dark shadow large enough to shade the telescope aperture from the target star. The NWO team has been addressing the top technology challenges of the concept, and report here our progress. We will present the current mission configuration best suited to address Terrestrial Planet Finding requirements, and highlight the technological breakthroughs that we have achieved this year. In particular, we will report on progress made in precision deployables for the large starshade, and the trajectory & alignment control system for NWO. We will also briefly highlight advances in understanding the starshade optical performance.

  18. Technical Manual: 2002 Series GED Tests

    Science.gov (United States)

    Ezzelle, Carol; Setzer, J. Carl

    2009-01-01

    This manual was written to provide technical information regarding the 2002 Series GED (General Educational Development) Tests. Throughout this manual, documentation is provided regarding the development of the GED Tests, data collection activities, as well as reliability and validity evidence. The purpose of this manual is to provide evidence…

  19. Technical progress safeguards future. Technischer Fortschritt sichert die Zukunft

    Energy Technology Data Exchange (ETDEWEB)

    1985-01-01

    'Technical progress safeguards future', the guiding theme of the 1985 conference of German engineers, calls for discussion. In five lectures representatives of the subdivisions of 'VDI' issued their statements from the viewpoints of their special fields. These lectures were completed by reports on the part of the remaining VDI subdivisions, which are published together with the lectures in this volume. The complex guiding theme is meant to stimulate discussion, which should be conducted also with representatives of other sciences and the public. The volume contains a.o. contributions regarding future prospects, given certain modifications in construction engineering and user behaviour in the sector heating and air-conditioning, regarding the development of new construction techniques to protect the environment, and regarding clean air as an international concern of engineers. For these three contributions separate entries were made. Other presentations relate to: automobile production technology; energy supply as an engineering task; information, invention, innovation as stages of technical progress; progress in materials technology; noise of motor vehicles - current state and future prospects. (orig./HSCH).

  20. International Linear Collider-A Technical Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    Elsen, Eckhard; /DESY; Harrison, Mike; /Brookhaven; Hesla, Leah; /Fermilab; Ross, Marc; /Fermilab; Royole-Degieux, Perrine; /Paris, IN2P3; Takahashi, Rika; /KEK, Tsukuba; Walker, Nicholas; /DESY; Warmbein, Barbara; /DESY; Yamamoto, Akira; /KEK, Tsukuba; Yokoya, Kaoru; /KEK, Tsukuba; Zhang, Min; /Beijing, Inst. High Energy Phys.

    2011-11-04

    The International Linear Collider: A Technical Progress Report marks the halfway point towards the Global Design Effort fulfilling its mandate to follow up the ILC Reference Design Report with a more optimised Technical Design Report (TDR) by the end of 2012. The TDR will be based on much of the work reported here and will contain all the elements needed to propose the ILC to collaborating governments, including a technical design and implementation plan that are realistic and have been better optimised for performance, cost and risk. We are on track to develop detailed plans for the ILC, such that once results from the Large Hadron Collider (LHC) at CERN establish the main science goals and parameters of the next machine, we will be in good position to make a strong proposal for this new major global project in particle physics. The two overriding issues for the ILC R&D programme are to demonstrate that the technical requirements for the accelerator are achievable with practical technologies, and that the ambitious physics goals can be addressed by realistic ILC detectors. This GDE interim report documents the impressive progress on the accelerator technologies that can make the ILC a reality. It highlights results of the technological demonstrations that are giving the community increased confidence that we will be ready to proceed with an ILC project following the TDR. The companion detector and physics report document likewise demonstrates how detector designs can meet the ambitious and detailed physics goals set out by the ILC Steering Committee. LHC results will likely affect the requirements for the machine design and the detectors, and we are monitoring that very closely, intending to adapt our design as those results become available.

  1. Environmental Research Division technical progress report, January 1984-December 1985

    International Nuclear Information System (INIS)

    1986-05-01

    Technical progress in the various research and assessment activities of Argonne National Laboratory's Environmental Research Division is reported for the period 1984 to 1985. Textual, graphic, and tabular information is used to briefly summarize (in separate chapters) the work of the Division's Atmospheric Physics, Environmental Effects Research, Environmental Impacts, Fundamental Molecular Physics and Chemistry, and Waste Management Programs. Information on professional qualifications, awards, and outstanding professional activities of staff members, as well as lists of publications, oral presentations, special events organized, and participants in educational programs, are provided in appendices at the end of each chapter

  2. Environmental Research Division technical progress report, January 1984-December 1985

    Energy Technology Data Exchange (ETDEWEB)

    1986-05-01

    Technical progress in the various research and assessment activities of Argonne National Laboratory's Environmental Research Division is reported for the period 1984 to 1985. Textual, graphic, and tabular information is used to briefly summarize (in separate chapters) the work of the Division's Atmospheric Physics, Environmental Effects Research, Environmental Impacts, Fundamental Molecular Physics and Chemistry, and Waste Management Programs. Information on professional qualifications, awards, and outstanding professional activities of staff members, as well as lists of publications, oral presentations, special events organized, and participants in educational programs, are provided in appendices at the end of each chapter.

  3. Gas Test Loop Functional and Technical Requirements

    International Nuclear Information System (INIS)

    Glen R. Longhurst; Soli T. Khericha; James L. Jones

    2004-01-01

    This document defines the technical and functional requirements for a gas test loop (GTL) to be constructed for the purpose of providing a high intensity fast-flux irradiation environment for developers of advanced concept nuclear reactors. This capability is needed to meet fuels and materials testing requirements of the designers of Generation IV (GEN IV) reactors and other programs within the purview of the Advanced Fuel Cycle Initiative (AFCI). Space nuclear power development programs may also benefit by the services the GTL will offer. The overall GTL technical objective is to provide developers with the means for investigating and qualifying fuels and materials needed for advanced reactor concepts. The testing environment includes a fast-flux neutron spectrum of sufficient intensity to perform accelerated irradiation testing. Appropriate irradiation temperature, gaseous environment, test volume, diagnostics, and access and handling features are also needed. This document serves to identify those requirements as well as generic requirements applicable to any system of this kind

  4. Gas Test Loop Functional and Technical Requirements

    Energy Technology Data Exchange (ETDEWEB)

    Glen R. Longhurst; Soli T. Khericha; James L. Jones

    2004-09-01

    This document defines the technical and functional requirements for a gas test loop (GTL) to be constructed for the purpose of providing a high intensity fast-flux irradiation environment for developers of advanced concept nuclear reactors. This capability is needed to meet fuels and materials testing requirements of the designers of Generation IV (GEN IV) reactors and other programs within the purview of the Advanced Fuel Cycle Initiative (AFCI). Space nuclear power development programs may also benefit by the services the GTL will offer. The overall GTL technical objective is to provide developers with the means for investigating and qualifying fuels and materials needed for advanced reactor concepts. The testing environment includes a fast-flux neutron spectrum of sufficient intensity to perform accelerated irradiation testing. Appropriate irradiation temperature, gaseous environment, test volume, diagnostics, and access and handling features are also needed. This document serves to identify those requirements as well as generic requirements applicable to any system of this kind.

  5. 46 CFR 160.066-13 - Technical tests.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 6 2010-10-01 2010-10-01 false Technical tests. 160.066-13 Section 160.066-13 Shipping....066-13 Technical tests. (a) The following conditions apply to technical tests as described in this... signals are protected by sealed packaging, then the conditioning for the technical tests must be conducted...

  6. Nonequilibrium photochemical reactions induced by lasers. Technical progress report

    International Nuclear Information System (INIS)

    Steinfeld, J.I.

    1978-04-01

    Research has progressed in six principal subject areas of interest to DOE advanced (laser) isotope separation efforts. These are (1) Infrared double resonance spectroscopy of molecules excited by multiple infrared photon absorption, particularly SF 6 and vinyl chloride. (2) Infrared multiphoton excitation of metastable triplet-state molecules, e.g., biacetyl. (3) An Information Theory analysis of multiphoton excitation and collisional deactivation has been carried out. (4) The mechanism of infrared energy deposition and multiphoton-induced reactions in chlorinated ethylene derivatives; and RRKM (statistical) model accounts for all observed behavior of the system, and a deuterium-specific reaction pathway has been identified. (5) Diffusion-enhanced laser isotope separation in N 16 O/N 18 O. (6) A technical evaluation of laser-induced chemistry and isotope separation

  7. Generation speed in Raven's Progressive Matrices Test

    NARCIS (Netherlands)

    Verguts, T.; Boeck, P. De; Maris, E.G.G.

    1999-01-01

    In this paper, we investigate the role of response fluency on a well-known intelligence test, Raven's (1962) Advanced Progressive Matrices (APM) test. Critical in solving this test is finding rules that govern the items. Response fluency is conceptualized as generation speed or the speed at which a

  8. Projects at the component development and integration facility. Quarterly technical progress report, April 1, 1994--June 30, 1994

    International Nuclear Information System (INIS)

    1994-01-01

    This quarterly technical progress report presents progress on the projects at the Component Development and Integration Facility (CDIF) during the third quarter of FY94. The CDIF is a major Department of Energy test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: Biomass Remediation Project; Heavy Metal-Contaminated Soil Project; MHD Shutdown; Mine Waste Technology Pilot Program; Plasma Projects; Resource Recovery Project; and Spray Casting Project

  9. Technical progress report, 1 April-30 June 1981

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-01-01

    This report describes the technical accomplishments during the quarter ending June 1981, on the commercial nuclear waste management programs under the direction of the Office of Nuclear Waste Isolation (ONWI). The ONWI program is organized into 8 tasks entitled: systems, waste package, site, repository, regulatory and institutional, test facilities and excavations, land acquisition, and program management. Principal investigators in each of these areas have submitted summaries of quarterly highlights for inclusion in this report. Separate abstracts have been prepared for 5 of these tasks for inclusion in the Energy Data Base. (DMC)

  10. Electronic refrigerant leak detector. Quarterly technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    Talamas, E. Jr.

    1998-10-15

    The project comprises three main tasks. They are (1) Develop, design, and fabricate sensors, (2) Develop, design, and fabricate test instruments, (3) Testing and data analysis. The milestone includes 17 sub-tasks for the 52-weeks project period, starting on May 1, 1998 and ending on April 30, 1999. As stated in the Application for Federal Assistance, Micronic intended to relocate to a new office by June of 1998. This decision was delayed, since the first partial payment was transferred on August 12, 1998. Micronic plans to relocate this November. A second Provisional Application for a US patent has been filed. Progress made during this period is reported.

  11. Technical and economic feasibility of membrane technology. Fourth technical progress report, June 17-September 16, 1980

    Energy Technology Data Exchange (ETDEWEB)

    Sandre, A.

    1980-10-01

    Progress is reported on the investigation of the potential application of reverse osmosis, ultrafiltration and electrodialysis to the system of solids concentration in beet sugar process streams. During this period, emphasis was put on running reverse osmosis tests with a new prototype machine to select the most suitable membranes for the concentrating of sugar solutions. An economic analysis of using reverse osmosis in a factory producing 10/sup 6/ gal/day of thin juice is discussed. (DMC)

  12. 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

  13. Technical Evaluation of Oak Ridge Filter Test Facility

    CERN Document Server

    Kriskovich, J R

    2002-01-01

    Two evaluations of the Oak Ridge Department of Energy (DOE) Filter Test Facility (FTF) were performed on December 11 and 12, 2001, and consisted of a quality assurance and a technical evaluation. This report documents results of the technical evaluation.

  14. Technical progress in planning organization of the Ostravo-Karwina coal basin, ''Mining Projects of Ostravo''

    Energy Technology Data Exchange (ETDEWEB)

    Karpeta, B; Kolar, J

    1979-01-01

    Based on the main task of further improvement in labor productivity and improvement in the quality of products, the leading planning organization of the Ostravo-Karwina basin is planning and realizing progressive technological plans based on new equipment. Long-term plans for basin development up to 1990 stipulate a rise in capital investments by 180%, increase in the volume of productivity by 164% with a rise in the number of workers by 142%. Corresponding technical progress in planning is based on an improvement in the system of scientific-technical information, automation and technical equipping of the planning process, improvements in the forms and organizational structure. Organization of specialized research-planning groups to substantiate and to technically-economically evaluate technical progress, and also to develop comprehensive technical assignments is stipulated.

  15. The challenge of the future. Technical progress and ecological perspectives

    International Nuclear Information System (INIS)

    Jischa, M.F.

    1993-01-01

    The book introduces readers into the interrelated global problems population dynamics, energy supply, imminent climate catastrophe, environmetal pollution, finite resources and the conflict between the North and South. It encourages probing more deeply into the technical challenges of the future. The author demonstrates why economic and technical issues will soon be outstripped by questions of the environmental, human and social compatibility of new technologies. (orig./UA) [de

  16. Progress in FMIT test assembly development

    International Nuclear Information System (INIS)

    Opperman, E.K.; Vogel, M.A.; Shen, E.J.; Trego, A.L.

    1983-08-01

    Research and development supporting the completed design of the Fusion Materials Irradiation Test (FMIT) Facility is continuing at the Hanford Engineering Development Laboratory (HEDL) in Richland, Washington. The FMIT, a deuteron accelerator based (d + Li) neutron source, will produce an intense flux of high energy neutrons for use in radiation damage studies of fusion reactor materials. The most intense flux magnitude of greater than 10 15 n/cm 2 -s is located close to the neutron producing lithium target and is distributed within a volume about the size of an American football. The conceptual design and development of FMIT experiments called Test Assemblies has progressed over the past five years in parallel with the design of the FMIT. The paper will describe the recent accomplishments made in developing test assemblies appropriate for use in the limited volume close to the FMIT target where high neutron flux and heating rates and the associated spacial gradients significantly impact design considerations

  17. Monitoring the Durability Performance of Concrete in Nuclear Waste Containment. Technical Progress Report No. 3

    International Nuclear Information System (INIS)

    Ulm, Franz-Josef

    2000-01-01

    OAK-B135 Monitoring the Durability Performance of Concrete in Nuclear Waste Containment. Technical Progress Report No. 3(NOTE: Part II A item 1 indicates ''PAPER'', but a report is attached electronically)

  18. Technical progress of nuclear energy: economic and environmental prospects

    International Nuclear Information System (INIS)

    Naudet, G.

    1994-01-01

    This document deals with three different aspects of the nuclear energy: first the operating and economic performances of nuclear power plants in the world, the French nuclear competitiveness. Then, the technical and economic perspectives about reactors and fuels cycle and the advantages towards atmospheric pollution are discussed to favour a new worldwide nuclear development. (TEC). 8 refs., 4 figs., 6 tabs

  19. Power systems development facility. Quarterly technical progress report, January 1, 1994--March 31, 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    This quarterly technical progress report summarizes work completed during the last quarter of the Second Budget Period, January 1 through March 31, 1994, entitled {open_quotes}Hot Gas Cleanup Test Facility for Gasification and Pressurized Combustion.{close_quotes} The objective of this project is to evaluate hot gas particulate control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scale-up of particulate control systems to commercial size.

  20. Yucca Mountain drift scale test progress report

    Energy Technology Data Exchange (ETDEWEB)

    Apps, J.; Birkholzer, J.T.; Peterson,J.E.; Sonnenthal, E.; Spycher, N.; Tsang, Y.W.; Williams, K.H.

    1999-01-01

    The Drift Scale Test (DST) is part of the Exploratory Studies Facility (ESF) Thermal Test being conducted underground at the potential high-level nuclear waste repository at Yucca Mountain, Nevada. The purpose of the ESF Thermal Test is to acquire a more in-depth understanding of the coupled thermal, mechanical, hydrological, and chemical processes likely to be encountered in the rock mass surrounding the potential geological repository at Yucca Mountain. These processes are monitored by a multitude of sensors to measure the temperature, humidity, gas pressure, and mechanical displacement, of the rock formation in response to the heat generated by the heaters. In addition to collecting passive monitoring data, active hydrological and geophysical testing is also being carried out periodically in the DST. These active tests are intended to monitor changes in the moisture redistribution in the rock mass, to collect water and gas samples for chemical and isotopic analysis, and to detect microfiacturing due to heating. On December 3, 1998, the heaters in the DST were activated. The planned heating phase of the DST is 4 years, and the cooling phase following the power shutoff will be of similar duration. The present report summarizes interpretation and analysis of thermal, hydrological, chemical, and geophysical data for the first 6 months; it is the first of many progress reports to be prepared during the DST.

  1. Evaporation by mechanical vapor recompression. Technical progress report, September 1-December 31, 1979

    Energy Technology Data Exchange (ETDEWEB)

    Iverson, C.H.; Coury, G.E.

    1979-01-01

    Progress to date in the development of a study of the application of the technologies of mechanical vapor recompression and falling film evaporators as applied to the beet sugar industry is reported. Progress is reported in the following areas: technical literature search and plant visitations of existing applications of VR/FFE.

  2. Conjoint utility analysis of technical maturity and project progress of construction project

    Directory of Open Access Journals (Sweden)

    Ma Wei

    2016-01-01

    Full Text Available In this paper, taking construction project as the research object, the relationship between the project maturity index calculated by the construction project technical risks with different fine degree and the project progress index is studied, and the equilibrium relationship between the Party A’s utility curve and the Party B’s cost curve of using project maturity index and project progress index as the research variables is analyzed. The results show that, when the construction project technical risk division is more precise, the conjoint utility of the project's technical maturity index and the project progress is higher, and the project’s Party A and Party B two sides are closer to the optimal equilibrium. This shows that the construction project technical risk must be finely divided, and managed and controlled respectively, which will help to improve the conjoint utility of the project Party A and Party B two sides.

  3. Environmental Research Division technical progress report: January 1986--October 1987

    International Nuclear Information System (INIS)

    1988-07-01

    Technical process in the various research activities of Argonne National Laboratory's Environmental Research Division is reported for the period 1986-1987. Textual, graphic, and tabular information is used to briefly summarize (in separate chapters) the work of the Division's Atmospheric Physics, Environmental Effects Research, Fundamental Molecular Physics and Chemistry, and Organic Geochemistry and Environmental Instrumentation Programs. Information on professional qualifications, awards, and outstanding professional activities of staff members, as well as lists of publications, oral presentations, special events organized, and participants in educational programs, are provided in appendices at the end of each chapter. Individual projects under each division are processed separately for the data bases

  4. Environmental Research Division technical progress report: January 1986--October 1987

    Energy Technology Data Exchange (ETDEWEB)

    1988-07-01

    Technical process in the various research activities of Argonne National Laboratory's Environmental Research Division is reported for the period 1986-1987. Textual, graphic, and tabular information is used to briefly summarize (in separate chapters) the work of the Division's Atmospheric Physics, Environmental Effects Research, Fundamental Molecular Physics and Chemistry, and Organic Geochemistry and Environmental Instrumentation Programs. Information on professional qualifications, awards, and outstanding professional activities of staff members, as well as lists of publications, oral presentations, special events organized, and participants in educational programs, are provided in appendices at the end of each chapter. Individual projects under each division are processed separately for the data bases.

  5. Technical Progress and Development Directions of Oceanic Spatial Information Datum

    Directory of Open Access Journals (Sweden)

    BAO Jingyang

    2017-10-01

    Full Text Available This paper briefly analyzes the basic development and technical situation of oceanic spatial information datum, reviews the main processes of oceanic vertical datum and correlative oceanic tidal study, such as improvement and perfect methods of determining tidal station vertical datum, realizing form of vertical datum controlled by tidal station, effect on maintaining vertical datum by long-term tidal station, oceanic tidal model establishing, and also construction and transformation of tidal datum, and then forecasts the key development directions of oceanic spatial information datum on high-accuracy marine position service, vertical datum and the transferring model refinement and spatial datum application.

  6. Quarterly technical progress report, February 1, 1996--April 30, 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-28

    This report from the Amarillo National REsource Center for PLutonium provides research highlights and provides information regarding the public dissemination of information. The center is a a scientific resource for information regarding the issues of the storage, disposition, potential utilization and transport of plutonium, high explosives, and other hazardous materials generated from nuclear weapons dismantlement. The center responds to informational needs and interpretation of technical and scientific data raised by interested parties and advisory groups. Also, research efforts are carried out on remedial action programs and biological/agricultural studies.

  7. Crystalline Repository Project. Technical progress report, October 1982-March 1983

    International Nuclear Information System (INIS)

    1985-01-01

    This document reports the progress being made periodically on the development of a geologic repository in crystalline rock for the permanent disposal of high-level nuclear waste. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Crystalline Respository Development (OCRD), a prime contractor of the US Department of Energy Repository Project Office. The studies include work by other prime contractors and by subcontractors to OCRD

  8. C-Mod Collaboration Informal Technical Progress Report

    International Nuclear Information System (INIS)

    Kenneth W. Gentle

    2007-01-01

    The aims of the collaboration have not changed. A specific list of tasks was agreed upon during the Fall of 2006 in preparation for the 2007 C-Mod campaign by Earl Marmar, Head of the Alcator Project, Kenneth Gentle, Principal Investigator, and William Rowan, Collaboration Coordinator with the facilitation of Adam Rosenberg (DOE grant monitor for the collaboration). The activities follow the list of tasks and are discussed in this progress report

  9. Progress report of Technical Physics Division: April 1980 - March 1982

    International Nuclear Information System (INIS)

    Chaudhry, Ramesh; Vijendran, P.

    1983-01-01

    Activities, with an individual summary of each, of the Technical Physics Division (TPD) of the Bhabha Atomic Research Centre (BARC), Bombay are reported for the period April 1980 - March 1982. The major thrust of the TPD's work has been in: (i) design and fabrication of instruments, devices and equipment and (ii) development of techniques in the frontline research and technology areas like vacuum science, surface analysis, cryogenics and crystal growing. The Division also provided custombuilt electronics equipment, vacuum systems and glass components and devices to the various Divisions of BARC and other units of the DAE. Training and manpower development activities and technology transfer activities are also reported. Lists of seminars, colloquia, publications during the period of the report are given. (M.G.B.)

  10. Progress report for 1978-79, Technical Physics Division

    International Nuclear Information System (INIS)

    Gopalaraman, C.P.; Deshpande, R.Y.

    1980-01-01

    The research and development activities of the Technical Physics Division (TPD) of the Bhabha Atomic Research Centre, Bombay, during the calendar years 1978 and 1979 are reported. The TPD's major areas of work are electronics instrumentation, crystal technology, mass spectrometers, cryogenic equipment and vacuum equipment. Some of the major achievements are: (1) fabrication of various electronic instruments and components for the pulsed nuclear magnetic resonance spectrometers, (2) growth of large size NaI(Tl) and Ge crystals, (3) growth of CsI, KDP and arsenic selenide crystals, (4) fabrication of quadrupole mass filters and (5) fabrication of mass spectrometers for gas analysis and D/H analysis in water samples. (M.G.B.)

  11. Fundamental studies of separation processes. Technical progress report

    International Nuclear Information System (INIS)

    Rogers, L.B.

    1975-06-01

    Studies using high-precision gas chromatography and supercritical fluid chromatography have produced new types of information on liquid crystals and on behavior of substances in the region of the critical temperature, respectively. In addition, the first successful studies of the effects of pressure on cation exchange have been made using aqueous solutions of alkali metal nitrates. In contrast, progress on separations of isotopic species using gas chromatography has been disappointing. In that area, the chief accomplishment has been a determination of the levels of accuracy and precision with which isotopic abundances can be measured using our quadrupole mass spectrometer. (U.S.)

  12. The role of technical progress in the process of recalculating oil reserves

    International Nuclear Information System (INIS)

    Boulard, J.N.

    1999-01-01

    Contrary to the concept of resources (which is essentially a geological one), the notion of reserves designates the quantities that are technically and economically recoverable. Beyond the production-related effect, the reserves therefore evolve over time in accordance with numerous technical and economic parameters. Among these parameters, it can be seen that technical progress plays a considerable role throughout the process of converting resources into reserves, including progress in the identification, accessibility and processing of the resources, and improvements in economic viability. After having tackled the problem of measuring the 'technical progress effects' and citing examples, we demonstrate that the evolution in oil reserves is subject to three types of impact. These are a quantitative impact by significantly improving the recovery rates or making it possible to identify hitherto undetectable oil fields, a qualitative impact by widening the resource base thanks to the adoption of new categories of oil (in particular the so-called 'unconventional' oils) and by carrying out the gradual substitution between these resources of differing qualities. There is also a dynamic impact, through the acceleration of resource availability. Through these three approaches, technical progress makes makes it possible to ensure continuity in oil supply and contributes significantly to the recalculation of reserves. It therefore acts as a compensating factor, counterbalancing the progressive depletion of resources. (author)

  13. Technical progress report, October 1, 1980-September 30, 1981

    International Nuclear Information System (INIS)

    1981-01-01

    Progress during the 12-month period, October 1, 1980 to September 30, 1981 on the University of Wisconsin Plasma Physics contract is described. Most of the work centers around two major experimental devices, the Levitated Octupole and Tokapole II. A major upgrade of the Octupole is underway to include 2 MW of ICRH and 1.8 MW of neutral beam heating. Meanwhile, gun optimization and low field operation has resulted in the attainment of 35% beta, a factor of 9 above the single fluid ballooning limit. The ICRH experiment is well underway, and the first neutral beam source has been installed. The Tokapole is operating reliably at the full design field of 10 kG with 12 msec discharges. Low q (approx. 0.4) discharges with flat current profiles are obtained at reduced (approx. 3kG) toroidal field. The device is presently being used to study shear Alfven wave heating, ECRH startup, poloidal ohmic heating, and plasma transport

  14. TECHNICAL TRAINING SEMINAR: High Temperature Superconductors: Progress and Issues

    CERN Multimedia

    Davide Vitè

    2002-01-01

    Monday 24 June from 14:30 to 15:30 - Training Centre Auditorium - bldg. 593-11 High Temperature Superconductors: Progress and Issues Prof. Jan Evetts / UNIVERSITY OF CAMBRIDGE, Department of Materials Science and Metallurgy, UK Grappling with grain boundaries: Current transport processes in granular High Temperature Superconductors (HTS) The development of High Temperature Superconductors, seen from a materials scientist's point of view, is relevant to the superconductivity community at CERN: their possible high current applications can include high performance magnets for future accelerators. There is an urgent need to develop a quantitative description of HTS conductors in terms of their complex anisotropy, inhomogeneity and dimensionality. This is essential both for the practical specification of a conductor and for charting routes to conductor optimisation. The critical current, the n-value, dissipation and quenching characteristics are amongst most important parameters that make up an engineering specifi...

  15. Technical progress review of extraction of uranium from fly ash

    International Nuclear Information System (INIS)

    Gao Renxi; Gao Junning; Wu Qingming; Chen Gang; Wan Hongjin; Zhang Ziyue

    2014-01-01

    The increasing of fly ash in coal-fired power plants at home and abroad year by year and the potential impacts to the environment attracted media attention. Although the extraction of uranium from the fly ash in coal-fired power plants had optional process from technique aspect and sufficient preliminary researches, but considering the low grade of the uranium in fly ash and particularity of the mineral composition, it is easy to have a high cost of extraction. As a consequence, it is not included in the development plan of uranium mining and metallurgy. The present applications of fly ash are only building materials, building roads and pit valley backfill, the resource utilization rate was low and was still in its early stages of development and application. In view of this, the research advances and the latest development trends of extraction of uranium from fly ash at home and abroad were introduced from the technical aspect, and the beneficial analyzes of the prospect and advices to this industry were given. (authors)

  16. Technical specification of HANARO fuel test loop

    Energy Technology Data Exchange (ETDEWEB)

    Kim, J. Y

    1998-03-01

    The design and installation of the irradiation test facility for verification test of the fuel performance are very important in connection with maximization of the utilization of HANARO. HANARO fuel test loop was designed in accordance with the same code and standards of nuclear power plant because HANARO FTL will be operated the high pressure and temperature same as nuclear power plant operation conditions. The objective of this study is to confirm the operation limit, safety limit, operation condition and checking points of HANARO fuel test loop. This results will become guidances for the planning of irradiation testing and operation of HANARO fuel test loop. (author). 13 refs., 13 tabs., 8 figs.

  17. Current progress and technical challenges of flexible liquid crystal displays

    Science.gov (United States)

    Fujikake, Hideo; Sato, Hiroto

    2009-02-01

    We focused on several technical approaches to flexible liquid crystal (LC) display in this report. We have been developing flexible displays using plastic film substrates based on polymer-dispersed LC technology with molecular alignment control. In our representative devices, molecular-aligned polymer walls keep plastic-substrate gap constant without LC alignment disorder, and aligned polymer networks create monostable switching of fast-response ferroelectric LC (FLC) for grayscale capability. In the fabrication process, a high-viscosity FLC/monomer solution was printed, sandwiched and pressed between plastic substrates. Then the polymer walls and networks were sequentially formed based on photo-polymerization-induced phase separation in the nematic phase by two exposure processes of patterned and uniform ultraviolet light. The two flexible backlight films of direct illumination and light-guide methods using small three-primary-color light-emitting diodes were fabricated to obtain high-visibility display images. The fabricated flexible FLC panels were driven by external transistor arrays, internal organic thin film transistor (TFT) arrays, and poly-Si TFT arrays. We achieved full-color moving-image displays using the flexible FLC panel and the flexible backlight film based on field-sequential-color driving technique. Otherwise, for backlight-free flexible LC displays, flexible reflective devices of twisted guest-host nematic LC and cholesteric LC were discussed with molecular-aligned polymer walls. Singlesubstrate device structure and fabrication method using self-standing polymer-stabilized nematic LC film and polymer ceiling layer were also proposed for obtaining LC devices with excellent flexibility.

  18. Texas Experimental Tokamak, a plasma research facility: Technical progress report

    International Nuclear Information System (INIS)

    Wootton, A.J.

    1995-08-01

    In the year just past, the authors made major progress in understanding turbulence and transport in both core and edge. Development of the capability for turbulence measurements throughout the poloidal cross section and intelligent consideration of the observed asymmetries, played a critical role in this work. In their confinement studies, a limited plasma with strong, H-mode-like characteristics serendipitously appeared and received extensive study though a diverted H-mode remains elusive. In the plasma edge, they appear to be close to isolating a turbulence drive mechanism. These are major advances of benefit to the community at large, and they followed from incremental improvements in diagnostics, in the interpretation of the diagnostics, and in TEXT itself. Their general philosophy is that the understanding of plasma physics must be part of any intelligent fusion program, and that basic experimental research is the most important part of any such program. The work here demonstrates a continuing dedication to the problems of plasma transport which continue to plague the community and are an impediment to the design of future devices. They expect to show here that they approach this problem consistently, systematically, and effectively

  19. Production of ultrahigh magnetic fields. Technical progress report

    International Nuclear Information System (INIS)

    1985-01-01

    The objective was to produce and measure controlled ultrahigh magnetic fields by imploding a plasma in which a magnetic field has been entrained. The novel method for producing the ultrahigh fields using a gas-puff Z pinch was tested successfully and found to work as well as predicted in some respects and better in others, such as field amplification. Moreover, in testing this concept, we may have created the only megagauss facility in the world with a 3-minute repetition rate and long lifetime. Most megagauss facilities are single-shot, owing to material deformations or the use of explosives

  20. AHMCT Intelligent Roadway Information System (IRIS) technical support and testing

    Science.gov (United States)

    2011-12-31

    This report documents the research project AHMCT IRIS Technical Support and Testing, : performed under contract 65A0275, Task ID 1777. It presents an overview of the Intelligent : Roadway Information System (IRIS), and its design and function. ...

  1. Wind Energy Department: Scientific and technical progress 1999-2000

    DEFF Research Database (Denmark)

    2001-01-01

    The activities of the Wind Energy Department fall within boundary layer meteorology, atmospheric turbulence, aerodynamics, aero-acoustics, structural dynamics, machine and construction technology and design of power systems and power system controls. Theobjective is to develop methods for design......; test and siting of wind turbines; prediction of wind loads and wind resources as well as methods to determine the dispersion, transformation and effect of air pollution. The present report describes theorganisation of the department and presents selected scientific highlights and results from the two...

  2. Wind energy department: Scientific and technical progress 1999 - 2000

    International Nuclear Information System (INIS)

    Skrumsager, B.; Larsen, G.

    2001-01-01

    The activities of the Wind Energy Department fall within boundary layer meteorology, atmospheric turbulence, aerodynamics, aero-acoustics, structural dynamics, machine and construction technology and design of power systems and power system controls. The objective is to develop methods for design; test and siting of wind turbines; prediction of wind loads and wind resources as well as methods to determine the dispersion, transformation and effect of air pollution. The present report describes the organisation of the department and presents selected scientific highlights and results from the two-year period 1999-2000. (au)

  3. Rooftop PV system. Final technical progress report, Phase II

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    Under this four-year PV:BONUS Program, ECD and United Solar are developing and demonstrating two new lightweight flexible building integrated Photovoltaic (BIPV) modules specifically designed as exact replacements for conventional asphalt shingles and standing seam metal roofing. These modules can be economically and aesthetically integrated into new residential and commercial buildings, and address the even larger roofing replacement market. The modules are designed to be installed by roofing contractors without special training which minimizes the installation and balance of system costs. The modules will be fabricated from high-efficiency, multiple-junction a-Si alloy solar cells developed by ECD and United Solar. Under the Phase I Program, which ended in March 1994, we developed two different concept designs for rooftop PV modules: (1) the United Solar overlapping (asphalt shingle replacement) shingle-type modules and (2) the ECD metal roof-type modules. We also developed a plan for fabricating, testing and demonstrating these modules. Candidate demonstration sites for our rooftop PV modules were identified and preliminary engineering designs for these demonstrations were developed; a marketing study plan was also developed. The major objectives of the Phase II Program, which started in June 1994 was (1) to develop, test, and qualify these new rooftop modules; (2) to develop mechanical and electrical engineering specifications for the demonstration projects; and (3) to develop a marketing/commercialization plan.

  4. Technical progress in INPRO activities on modelling and innovation

    International Nuclear Information System (INIS)

    Villalibre, P.; Haas, E.; Khartabil, H.; Kim, S.; Korinny, A.; Usanov, V. and others

    2010-01-01

    Among the 31 Members of the 'International Project on Innovative Nuclear Reactors and Fuel Cycles' (INPRO) in April 2010, more than 20 are cooperating in the implementation of Collaborative Projects (CPs) related to the four substantive Programme Areas of the INPRO Action Plan. The purpose of the CPs is to contribute to the achievement of goals established in the programmatic areas. This paper presents progress status of several CPs dealing with Modelling and Innovation: - CP on Environmental Impact Benchmarking applicable to Nuclear Energy Systems under Normal Operation (ENV): A benchmark of codes and methods for determining radiation released during normal operation of nuclear facilities is performed by using established source term, release scenario, and target group (humans). - CP on Proliferation Resistance: Acquisition/Diversion Pathway Analysis (PRADA): 'PRADA' addresses the identification and analyses of high level pathways for the acquisition of weapons usable material, and makes recommendations for evaluating the multiplicity and robustness of barriers against proliferation. PRADA develops a case study based on DUPIC fuel cycle. The outcome from the project will support the assessment methodologies developed at GIF and INPRO. - CP on Global Architecture of Nuclear Energy Systems based on Thermal and Fast Reactors including Closed Fuel Cycle (GAINS): GAINS objective is to develop a methodological platform for assessing future nuclear energy systems taking into account the sustainable development, and to validate the results through sample analyses. High and moderate scenarios of nuclear energy demand and supply during the Century (5000 and 2500 GWe respectively in the year 2100) are being analysed using homogeneous and heterogeneous considerations. A non-geographic approach grouping the countries according to their planned use of nuclear energy has being established. - CP on Investigations of the 233 U/Th Fuel Cycle (ThFC): ThFC objective is to explore FC

  5. Potential well formation in electrostatic confinement devices. Technical progress report

    International Nuclear Information System (INIS)

    Cherrington, B.E.; Verdeyen, J.T.

    1975-01-01

    A large (2' diameter) spherical electrostatic confinement device has been constructed to test the feasibility of using inertial electrostatic forces to confine energetic plasmas capable of sustaining fusion reactions. Electron injection under high vacuum has produced negative wells that completely depress the potential in the center and approach the classical Langmuir virtual cathode. Electron injection into low pressure deuterium reproduces our previous results of an ion rich region within the negative well. Additional theoretical studies incorporating electrons with very narrow angular momentum (corresponding to trapped electrons in the center) has shown that an additional electron rich region (or ion rich if the polarities are reversed) can be produced within the ion rich region for presumably realistic ranges of parameters

  6. Quarterly technical progress report, October 1-December 30, 1983

    Energy Technology Data Exchange (ETDEWEB)

    1984-04-01

    Several new initiatives were begun in coal preparation, including a project to develop a liquid CO/sub 2/ coalescence process that will produce a superclean coal containing less than 1% ash. Another new project in this area is focusing on chemical coal cleaning for the removal of harmful trace elements, such as arsenic, lead, and zinc. Milestones were reached in both of our major electron beam flue gas cleanup projects. In the area of coal-water mixtures, our major industrial contracts are now approaching critical milestones. The analysis of our in-house combustion testing of micronized coal-water mixtures in PETC's 700-horsepower oil-designed boiler has been completed. By reducing the coal particle size from 90% minus 200 mesh down to 87% minus 19 microns, the carbon conversion efficiency increased from a level of 96% to 98%. Combustion tests with a commercially available CWM showed that combustion air enriched to 23% oxygen reduced the needed air preheat temperature from 370/sup 0/ to 200/sup 0/F. Work also got underway in the new projects selected last summer to investigate advanced direct liquefaction processes. At Kerr-McGee, three scoping runs on their 350 pound/day integrated bench-scale unit were successfully completed. The objective of these runs was to evaluate subbituminous coal process options in terms of catalyst performance, distillate yields, and generation of coke precursors. Cities Service began its project on the characterization of hydrogen donor solvents in two-stage liquefaction. 7 figures, 33 tables.

  7. Factors of progress in reading literacy test

    Directory of Open Access Journals (Sweden)

    Jovanović Vitomir

    2011-01-01

    Full Text Available The main goal of this study was to identify the factors which are most associated with the progress in reading literacy assessed in the PISA survey. In the preliminary sample, students from ten schools (N=235 were retested two years after the 2009 PISA original study. There were measured intrinsic and extrinsic motivation, school self-efficacy, epistemological beliefs, metacognitive strategies, socio-economic status, enjoyment and preference for reading and motivation and self-regulation. The examined factors explain 27% of the variance in reading literacy progress. Factors that contribute most to this progress are school self-efficacy, proper use of metacognitive strategies and low extrinsic motivation. Socio-economic status explained a negligible amount of variance, while some effect of type of school on progress in reading literacy (η2=7% was observed. Achievement in reading literacy is correlated with school marks. Students who attend secondary schools are more likely to make progress in reading literacy than those who attend vocational schools. An attempt was made to formulate the implications for education policy based on this research.

  8. Technical testing of portable isotope identification instruments

    International Nuclear Information System (INIS)

    Smith, D.E.

    2001-01-01

    . First generation portable isotope identifiers were identified and evaluated by U.S. Customs. Instruments from five vendors were put through a battery of tests according to delineated test procedures. The tests fell into five categories: Basic operation verification; Medical isotope identification; Individual isotope identification; Isotope pair identification; Dose rate calculation. The tests can be summarized as an initial verification of correct instrument operation (including whatever calibration procedure was specified by the vendor), followed by three different isotope identification tests designed to verify the instrument's ability to correctly identify 19 isotopes specified by U.S. Customs. The final test determined each instrument's ability to correctly display the dose rate from a wide energy range of gamma emitters. The individual isotope identification test and the isotope pair identification test were performed with three types of intervening shielding. The first of these three types used the minimum packaging needed for safe source handling and was, in general, thin plastic. This type of shielding is virtually identical to a bare radiation source. The second type of shielding used 2.7 mm of steel to simulate the wall of a typical transportainer (or sea-tainer). The third type of shielding used 6.94 mm of lead to simulate typical industrial packaging or, perhaps, an attempt by the shipper to conceal the source without unduly increasing the weight of the shipment. The isotopes tested were broadly categorized as: Special nuclear material (SNM), Medical, and Industrial. These included 17 gamma emitters, 1 beta emitter, and 1 neutron emitter. Each instrument was subjected to the following testing regimen: First, each instrument was calibrated according to vendor's procedures. Instrument size and weight were recorded. Next, the instrument's response to medical isotopes in their usual shipping containers was measured. This represents the most commonly occurring

  9. Institutional effectiveness of REDD+ MRV: Countries progress in implementing technical guidelines and good governance requirements

    NARCIS (Netherlands)

    Ochieng, R.M.; Visseren-Hamakers, Ingrid; Arts, B.; Brockhaus, M.; Herold, M.

    2016-01-01

    The UNFCCC requires REDD+ countries wishing to receive results-based payments to measure, report and verify (MRV) REDD+ impacts; and outlines technical guidelines and good governance requirements for MRV. This article examines institutional effectiveness of REDD+ MRV by assessing countries’ progress

  10. Studies in theoretical high energy particle physics: Technical progress report [February 1987-February 1988

    International Nuclear Information System (INIS)

    Sukhatme, U.P.; Keung, Wai-Yee; Kovacs, E.

    1988-02-01

    This is a technical progress report for grant No. FG02-84ER40173 for the period February 1987 to February 1988. Our research on supersymmetric quantum mechanics has yielded many interesting results. In particular, a systematic approach to the tunneling problem in double well potentials has been developed. Higgs boson related physics at the high energy hadron colliders has been extensively studied

  11. Amarillo National Resource Center for Plutonium. Quarterly technical progress report, May 1--July 31, 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    Progress is reported on research projects related to the following: Electronic resource library; Environment, safety, and health; Communication, education, training, and community involvement; Nuclear and other materials; and Reporting, evaluation, monitoring, and administration. Technical studies investigate remedial action of high explosives-contaminated lands, radioactive waste management, nondestructive assay methods, and plutonium processing, handling, and storage.

  12. Instrumentation of dynamic gas pulse loading system. Technical progress report, first quarter 1992

    Energy Technology Data Exchange (ETDEWEB)

    Mohaupt, H.

    1992-04-14

    The overall goal of this work is to further develop and field test a system of stimulating oil and gas wells, which increases the effective radius of the well bore so that more oil can flow into it, by recording pressure during the gas generation phase in real time so that fractures can be induced more predictably in the producing formation. Task 1: Complete the laboratory studies currently underway with the prototype model of the instrumentation currently being studied. Task 2: Perform field tests of the model in the Taft/Bakersfield area, utilizing operations closest to the engineers working on the project, and optimize the unit for various conditions encountered there. Task 3: Perform field test of the model in DGPL jobs which are scheduled in the mid-continent area, and optimize the unit for downhole conditions encountered there. Task 4: Analyze and summarize the results achieved during the complete test series, documenting the steps for usage of downhole instrumentation in the field, and compile data specifying use of the technology by others. Task 5: Prepare final report for DOE, and include also a report on the field tests completed. Describe and estimate the probability of the technology being commercialized and in what time span. The project has made substantial technical progress, though we are running about a month behind schedule. Expenditures are in line with the schedule. Increased widespread interest in the use of DGPL stimulation has kept us very busy. The computer modeling and test instrumentation developed under this program is already being applied to commercial operations.

  13. Technical progress faced with the challenges of the energy sector in the future

    International Nuclear Information System (INIS)

    Maillard, D.

    1999-01-01

    The colloquium organised by the Association of Energy Economists dealing with the theme 'Technical progress faced with the challenges of the energy sector in the future' takes place against a backdrop of ever-increasing initiatives in this field, for example at the World Energy Council or the International Energy Agency Faith in technical progress is widespread but should be supported by studies without any preconceived ideas. Research and development efforts must be fully supported, and in a climate of opening markets and liberalization the public authorities have a major role to pay. Historically, the markets have always been able to meet new needs thanks to technology, but the ambitious targets that the international community has set itself regarding the emission of greenhouse gases imply technical improvements and major investments. (authors)

  14. Stockholm international conference 2003 on geological repositories: Political and technical progress

    International Nuclear Information System (INIS)

    2004-01-01

    The conference reviewed global progress made as well as current perspectives on the activities to develop geologic repositories. The objectives were to review the progress in policy making as well as technical issues and to strengthen international co-operation on waste management and disposal issues. The first day of the conference addressed the policy aspects of geological repositories and the second day featured the more technical issues. Session 1: International progress in performing long-term safety studies and security of geological disposal were discussed and reviewed with examples from OECD/NEA, Belgium, Sweden, USA, Switzerland and Russia. Session 2: Views on stakeholder involvement and decision making process were presented by international organisations and national implementers from Japan, United Kingdom, Belgium and OECD/NEA. Session 3: Views on stakeholder involvement and decision making process were presented by regional and local stakeholders from France, Finland, Korea and Sweden. Session 4: International instruments assisting in the implementation of geological repositories were discussed, for example ICRP and IAEA/NEA safety documents, Joint Convention, Safeguard agreements, Nuclear Liability Conventions, etc. Session 5: The contribution of Research, Development and Demonstration was discussed with overviews of the progress achieved on scientific and technical issues over the past four years. Progress and key issues were presented from Switzerland, USA, Finland, Japan, Sweden and IAEA. Each of the papers and poster presentations have been analysed and indexed separately

  15. GT-MHR COMMERCIALZATION STUDY. TECHNICAL PROGRESS AND COST MANAGEMENT REPORT FOR THE PERIOD MAY 1 THROUGH MAY 31, 2003

    International Nuclear Information System (INIS)

    SHENOY, A.S.

    2003-01-01

    A271 GT-MHR COMMERCIALZATION STUDY TECHNICAL PROGRESS AND COST MANAGEMENT REPORT FOR THE PERIOD MAY 1 THROUGH MAY 31, 2003. Petten advised GA the start of the HFR-EU2 irradiation is being delayed until late July 2004. HFR-EU1 (pebble fuel) is also delayed until February/March 2004. The reason for the delays was implementation of new financial regulations at Petten that delayed the contracts for capsule fabrication. Review of the MHR-2 Fuel Product Specification was completed. Revision of the specification to incorporate the review results is in progress. Detailed test matrices have been drafted for capsule irradiation tests and for post-irradiation heating tests proposed for development and qualification of advanced coated-particle fuels capable of meeting anticipated VHTR fuel performance requirements

  16. Technical meeting on progress in managing, and limiting the consequences of events exceeding the design basis

    International Nuclear Information System (INIS)

    Fabian, H.

    2004-01-01

    The Technical Groups on 'Reactor Safety' and 'Thermodynamics and Fluid Dynamics' of the Kerntechnische Gesellschaft e.V. organized a joint technical meeting on 'Progress in Managing, and Limiting the Consequences of, Events Exceeding the Design Basis' at the FTU Training Center of the Karlsruhe Research Center. The topic chosen, the papers presented, the presenters, and the non-technical part of the program met with lively interest on the part of institutions in the nuclear field. These were the objectives of the technical meeting: - Establishing a forum for communicating relevant topics. - In-depth discussion of the main topic, i.e. the advanced development of reactor safety, research in the field, and its application, in twenty selected papers presented by speakers from different institutions. - Presentation of topical work in a nuclear technology institution, the Karlsruhe Research Center. (orig.) [de

  17. Power systems development facility. Quarterly technical progress report, July 1--September 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-31

    This quarterly technical progress report summarizes work completed during the Second Quarter of the Second Budget Period, July 1 through September 30, 1993, under the Department of Energy (DOE) Cooperative Agreement No. DE-FC21-90MC25140 entitled ``Hot Gas Cleanup Test Facility for Gasification and Pressurized Combustion.`` The objective of this project is to evaluate hot gas particle control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scaleup of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phased expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the existing Transport Reactor gas source and Hot Gas Cleanup Units: Carbonizer/Pressurized Circulating Fluidized Bed Gas Source. Hot Gas Cleanup Units to mate to all gas streams; Combustion Gas Turbine; and Fuel Cell and associated gas treatment. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF). The major emphasis during this reporting period was continuing the detailed design of the facility.

  18. International Technical Working Group Round Robin Tests

    Energy Technology Data Exchange (ETDEWEB)

    Dudder, Gordon B.; Hanlen, Richard C.; Herbillion, Georges M.

    2003-02-01

    The goal of nuclear forensics is to develop a preferred approach to support illicit trafficking investigations. This approach must be widely understood and accepted as credible. The principal objectives of the Round Robin Tests are to prioritize forensic techniques and methods, evaluate attribution capabilities, and examine the utility of database. The HEU (Highly Enriched Uranium) Round Robin, and previous Plutonium Round Robin, have made tremendous contributions to fulfilling these goals through a collaborative learning experience that resulted from the outstanding efforts of the nine participating internal laboratories. A prioritized list of techniques and methods has been developed based on this exercise. Current work is focused on the extent to which the techniques and methods can be generalized. The HEU Round Robin demonstrated a rather high level of capability to determine the important characteristics of the materials and processes using analytical methods. When this capability is combined with the appropriate knowledge/database, it results in a significant capability to attribute the source of the materials to a specific process or facility. A number of shortfalls were also identified in the current capabilities including procedures for non-nuclear forensics and the lack of a comprehensive network of data/knowledge bases. The results of the Round Robin will be used to develop guidelines or a ''recommended protocol'' to be made available to the interested authorities and countries to use in real cases.

  19. International Technical Working Group Round Robin Tests

    International Nuclear Information System (INIS)

    Dudder, Gordon B.; Hanlen, Richard C.; Herbillion, Georges M.

    2003-01-01

    The goal of nuclear forensics is to develop a preferred approach to support illicit trafficking investigations. This approach must be widely understood and accepted as credible. The principal objectives of the Round Robin Tests are to prioritize forensic techniques and methods, evaluate attribution capabilities, and examine the utility of database. The HEU (Highly Enriched Uranium) Round Robin, and previous Plutonium Round Robin, have made tremendous contributions to fulfilling these goals through a collaborative learning experience that resulted from the outstanding efforts of the nine participating internal laboratories. A prioritized list of techniques and methods has been developed based on this exercise. Current work is focused on the extent to which the techniques and methods can be generalized. The HEU Round Robin demonstrated a rather high level of capability to determine the important characteristics of the materials and processes using analytical methods. When this capability is combined with the appropriate knowledge/database, it results in a significant capability to attribute the source of the materials to a specific process or facility. A number of shortfalls were also identified in the current capabilities including procedures for non-nuclear forensics and the lack of a comprehensive network of data/knowledge bases. The results of the Round Robin will be used to develop guidelines or a ''recommended protocol'' to be made available to the interested authorities and countries to use in real cases

  20. Survey of experimental tests about progressive distortion

    International Nuclear Information System (INIS)

    Clement, Gerard.

    1981-02-01

    A procedure for evaluation of progressive distorsion experimental data has been set up in CEA. This procedure based on the effective primary stress concept, permits the establishment of a simple design rule. Various published experimental data have been used for verification, validation and generalization of design rule proposed. This rule is compared with existing codified rules (3 Sm, BREE, O'DONNEL and POROWSKI) [fr

  1. Total Factor Productivity Growth, Technical Progress & Efficiency Change in Vietnam Coal Industry - Nonparametric Approach

    Science.gov (United States)

    Phuong, Vu Hung

    2018-03-01

    This research applies Data Envelopment Analysis (DEA) approach to analyze Total Factor Productivity (TFP) and efficiency changes in Vietnam coal mining industry from 2007 to 2013. The TFP of Vietnam coal mining companies decreased due to slow technological progress and unimproved efficiency. The decadence of technical efficiency in many enterprises proved that the coal mining industry has a large potential to increase productivity through technical efficiency improvement. Enhancing human resource training, technology and research & development investment could help the industry to improve efficiency and productivity in Vietnam coal mining industry.

  2. Recent progress in shear punch testing

    International Nuclear Information System (INIS)

    Hamilton, M.L.; Toloczko, M.B.; Lucas, G.E.

    1994-09-01

    The shear punch test was developed in response to the needs of the materials development community for small-scale mechanical properties tests. Such tests will be of great importance when a fusion neutron simulation device is built, since such a device is expected to have a limited irradiation volume. The shear punch test blanks a circular disk from a fixed sheet metal specimen, specifically a TEM disk. Load-displacement data generated during the test can be related to uniaxial tensile properties such as yield and ultimate strength. Shear punch and tensile tests were performed at room temperature on a number of unirradiated aluminum, copper, vanadium, and stainless steel alloys and on several irradiated aluminum alloys. Recent results discussed here suggest that the relationship between shear punch strength and tensile strength varies with alloy class, although the relationship determined for the unirradiated condition remains valid for the irradiated aluminum alloys

  3. 12 tesla test coil. Annual progress report

    International Nuclear Information System (INIS)

    1979-01-01

    The Plasma Fusion Center at MIT has been charged with responsibility for the design, development, fabrication and test operation of a Niobium-3-Tin Superconducting Test Coil. Research is described on DOE's 12 tesla coil demonstration program in which several one-meter diameter superconducting test coils will be inserted and tested in DOE's High Field Test Facility at the Lawrence Livermore Laboratories. The work was initiated at the start of FY 79. FY 79 saw the completion of our Preliminary Design and the initiation of three (3) subcontracts: (1) Westinghouse review of the Preliminary Design, (II) Supercon, Inc. development of a tubular copper matrix, Nb 3 Sn Superconductor and (III) Airco optimization of the LCP-W Nb 3 Sn superconductor for 12T service. In addition, Airco was charged with the production of a 1000 foot length of model 15,000A conductor. Coil winding exercises were initiated at the Everson Electric Company

  4. Productivity Change, Technical Progress, and Relative Efficiency Change in the Public Accounting Industry

    OpenAIRE

    Rajiv D. Banker; Hsihui Chang; Ram Natarajan

    2005-01-01

    We present evidence on components of productivity change in the public accounting industry toward the end of the 20th century. Using revenue and human resource data from 64 of the 100 largest public accounting firms in the United States for the 1995--1999 period, we analyze productivity change, technical progress, and relative efficiency change over time. The average public accounting firm experienced a productivity growth of 9.5% between 1995 and 1999. We find support for the hypothesis that...

  5. Decontamination Systems Information and Research Program. Quarterly technical progress report, January 1--March 31, 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-05-01

    West Virginia University (WVU) and the US DOE Morgantown Energy Technology Center (METC) entered into a Cooperative Agreement on August 29, 1992 entitled ``Decontamination Systems Information and Research Programs.`` Stipulated within the Agreement is the requirement that WVU submit to METC a series of Technical Progress Reports on a quarterly basis. This report comprises the first Quarterly Technical Progress Report for Year 2 of the Agreement. This report reflects the progress and/or efforts performed on the sixteen (16) technical projects encompassed by the Year 2 Agreement for the period of January 1 through March 31, 1994. In situ bioremediation of chlorinated organic solvents; Microbial enrichment for enhancing in-situ biodegradation of hazardous organic wastes; Treatment of volatile organic compounds (VOCs) using biofilters; Drain-enhanced soil flushing (DESF) for organic contaminants removal; Chemical destruction of chlorinated organic compounds; Remediation of hazardous sites with steam reforming; Soil decontamination with a packed flotation column; Use of granular activated carbon columns for the simultaneous removal of organics, heavy metals, and radionuclides; Monolayer and multilayer self-assembled polyion films for gas-phase chemical sensors; Compact mercuric iodide detector technology development; Evaluation of IR and mass spectrometric techniques for on-site monitoring of volatile organic compounds; A systematic database of the state of hazardous waste clean-up technologies; Dust control methods for insitu nuclear and hazardous waste handling; Winfield Lock and Dam remediation; and Socio-economic assessment of alternative environmental restoration technologies.

  6. GPHS-RTGs in support of the Cassini RTG Program. Semi annual technical progress report, September 26, 1994--April 2, 1995

    International Nuclear Information System (INIS)

    1995-01-01

    The technical progress achieved during the period 26 September 1994 through 2 April 1995 on Contract DE-AC03-91SF18852 Radioisotope Thermoelectric Generators and Ancillary Activities is described herein. Monthly technical activity for the period 27 February 1995 through 2 April 1995 is included in this progress report. The report addresses tasks, including: spacecraft integration and liaison; engineering support; safety; qualified unicouple production; ETG Fabrication, assembly, and test; ground support equipment; RTG shipping and launch support; designs, reviews, and mission applications; project management, quality assurance, reliability, contract changes, CAGO acquisition (operating funds), and CAGO maintenance and repair; and CAGO acquisition (capital funds)

  7. Technical concept for a Greater Confinement Disposal test facility

    International Nuclear Information System (INIS)

    Hunter, P.H.

    1982-01-01

    For the past two years, Ford, Bacon and Davis has been performing technical services for the Department of Energy at the Nevada Test Site in specific development of defense low-level waste management concepts for greater confinement disposal concept with particular application to arid sites. The investigations have included the development of Criteria for Greater Confinement Disposal, NVO-234, which was published in May of 1981 and the draft of the technical concept for Greater Confinement Disposal, with the latest draft published in November 1981. The final draft of the technical concept and design specifications are expected to be published imminently. The document is prerequisite to the actual construction and implementation of the demonstration facility this fiscal year. The GCD Criteria Document, NVO-234 is considered to contain information complimentary and compatible with that being developed for the reserved section 10 CFR 61.51b of the NRCs proposed licensing rule for low level waste disposal facilities

  8. Recent progress of the advanced test accelerator

    International Nuclear Information System (INIS)

    Prono, D.S.

    1985-01-01

    The Advanced Test Accelerator (ATA) of Lawrence Livermore National Laboratory is a linear induction accelerator whose electron beam parameters are 10 kA, 50 MeV, and 70 ns. This accelerator structure basically is a 2.5 MeV injector followed by 190 identical induction accelerator cores each of which incrementally adds 250 kV to the electron beam as it threads the center of the core. Recent work on beam stability, beam emittance and beam brightness is reported

  9. Wave basin model tests of technical-biological bank protection

    Science.gov (United States)

    Eisenmann, J.

    2012-04-01

    Sloped embankments of inland waterways are usually protected from erosion and other negative im-pacts of ship-induced hydraulic loads by technical revetments consisting of riprap. Concerning the dimensioning of such bank protection there are several design rules available, e.g. the "Principles for the Design of Bank and Bottom Protection for Inland Waterways" or the Code of Practice "Use of Standard Construction Methods for Bank and Bottom Protection on Waterways" issued by the BAW (Federal Waterways Engineering and Research Institute). Since the European Water Framework Directive has been put into action special emphasis was put on natural banks. Therefore the application of technical-biological bank protection is favoured. Currently design principles for technical-biological bank protection on inland waterways are missing. The existing experiences mainly refer to flowing waters with no or low ship-induced hydraulic loads on the banks. Since 2004 the Federal Waterways Engineering and Research Institute has been tracking the re-search and development project "Alternative Technical-Biological Bank Protection on Inland Water-ways" in company with the Federal Institute of Hydrology. The investigation to date includes the ex-amination of waterway sections where technical- biological bank protection is applied locally. For the development of design rules for technical-biological bank protection investigations shall be carried out in a next step, considering the mechanics and resilience of technical-biological bank protection with special attention to ship-induced hydraulic loads. The presentation gives a short introduction into hydraulic loads at inland waterways and their bank protection. More in detail model tests of a willow brush mattress as a technical-biological bank protec-tion in a wave basin are explained. Within the scope of these tests the brush mattresses were ex-posed to wave impacts to determine their resilience towards hydraulic loads. Since the

  10. Research in elementary particle physics: Technical progress report, June 1, 1987-May 31, 1988

    International Nuclear Information System (INIS)

    Kirsch, L.E.; Schnitzer, H.J.; Abbott, L.F.; Bensinger, J.R.; Blocker, C.A.

    1988-01-01

    The main topics discussed in the progress report: electron/photon algorithm groups; W and Z analysis; heavy quark analysis; gas gain monitoring; database upgrade; CDF test beam studies; string theory; cosmology; and neutral networks

  11. Experimental Facilities Division/User Program Division technical progress report 1999-2000

    International Nuclear Information System (INIS)

    2001-01-01

    In October 1999, the two divisions of the Advanced Photon Source (APS), the Accelerator Systems Division (ASD) and the Experimental Facilities Division (XFD), were reorganized into four divisions (see high-level APS organizational chart, Fig. 1.1). In addition to ASD and XFD, two new divisions were created, the APS Operations Division (AOD), to oversee APS operations, and the User Program Division (UPD), to serve the APS user community by developing and maintaining the highest quality user technical and administration support. Previous XFD Progress Reports (ANL/APS/TB-30 and ANL/APS/TB-34) covered a much broader base, including APS user administrative support and what was previously XFD operations (front ends, interlocks, etc.) This Progress Report summarizes the main scientific and technical activities of XFD, and the technical support, research and development (R and D) activities of UPD from October 1998 through November 2000. The report is divided into four major sections, (1) Introduction, (2) SRI-CAT Beamlines, Technical Developments, and Scientific Applications, (3) User Technical Support, and (4) Major Plans for the Future. Sections 2 and 3 describe the technical activities and research accomplishments of the XFD and UPD personnel in supporting the synchrotron radiation instrumentation (SRI) collaborative access team (CAT) and the general APS user community. Also included in this report is a comprehensive list of publications (Appendix 1) and presentations (Appendix 2) by XFD and UPD staff during the time period covered by this report. The organization of section 2, SRI CAT Beamlines, Technical Developments, and Scientific Applications has been made along scientific techniques/disciplines and not ''geographical'' boundaries of the sectors in which the work was performed. Therefore items under the subsection X-ray Imaging and Microfocusing could have been (and were) performed on several different beamlines by staff in different divisions. The management of

  12. The influence of technical testing methods on perceptions of constructions

    International Nuclear Information System (INIS)

    Oestberg, Gustaf

    2002-01-01

    In principle, methods of testing the reliability and safety of constructions are designed with the aim of representing critical conditions for their use. Because of variations within technical systems, including the one for which a certain test was once developed, the validity of the method also varies. The adoption of a standardized test for different applications had to be based on the assumption that the test deals adequately with a real situation. As a consequence of this acceptance of a trustworthy relationship between test and reality, an imprint of the former on the latter occurs. This effect may even cause the perception of a reality to be defined by the corresponding test. Examples of such an influence may be found in the field of materials testing. Related phenomena can be dealt with by reference to current concepts of cognitive science and psychology of the perception of images

  13. Flexible electronic feedback using the virtues of progress testing

    NARCIS (Netherlands)

    Muijtjens, A.M.; Timmermans, I.; Donkers, J.; Peperkamp, R.; Medema, H.; Cohen-Schotanus, J.; Thoben, A.; Wenink, A.C.; van der Vleuten, C.P.

    2010-01-01

    The potential richness of the feedback for learners and teachers is one of the educational advantages of progress tests (PTs). Every test administration yields information on a student's knowledge level in each sub-domain of the test (cross-sectional information), and it adds a next point to the

  14. Computational model for simulation small testing launcher, technical solution

    Energy Technology Data Exchange (ETDEWEB)

    Chelaru, Teodor-Viorel, E-mail: teodor.chelaru@upb.ro [University POLITEHNICA of Bucharest - Research Center for Aeronautics and Space, Str. Ghe Polizu, nr. 1, Bucharest, Sector 1 (Romania); Cristian, Barbu, E-mail: barbucr@mta.ro [Military Technical Academy, Romania, B-dul. George Coşbuc, nr. 81-83, Bucharest, Sector 5 (Romania); Chelaru, Adrian, E-mail: achelaru@incas.ro [INCAS -National Institute for Aerospace Research Elie Carafoli, B-dul Iuliu Maniu 220, 061126, Bucharest, Sector 6 (Romania)

    2014-12-10

    The purpose of this paper is to present some aspects regarding the computational model and technical solutions for multistage suborbital launcher for testing (SLT) used to test spatial equipment and scientific measurements. The computational model consists in numerical simulation of SLT evolution for different start conditions. The launcher model presented will be with six degrees of freedom (6DOF) and variable mass. The results analysed will be the flight parameters and ballistic performances. The discussions area will focus around the technical possibility to realize a small multi-stage launcher, by recycling military rocket motors. From technical point of view, the paper is focused on national project 'Suborbital Launcher for Testing' (SLT), which is based on hybrid propulsion and control systems, obtained through an original design. Therefore, while classical suborbital sounding rockets are unguided and they use as propulsion solid fuel motor having an uncontrolled ballistic flight, SLT project is introducing a different approach, by proposing the creation of a guided suborbital launcher, which is basically a satellite launcher at a smaller scale, containing its main subsystems. This is why the project itself can be considered an intermediary step in the development of a wider range of launching systems based on hybrid propulsion technology, which may have a major impact in the future European launchers programs. SLT project, as it is shown in the title, has two major objectives: first, a short term objective, which consists in obtaining a suborbital launching system which will be able to go into service in a predictable period of time, and a long term objective that consists in the development and testing of some unconventional sub-systems which will be integrated later in the satellite launcher as a part of the European space program. This is why the technical content of the project must be carried out beyond the range of the existing suborbital

  15. Technical progress report for the quarter 1 October-31 December 1980

    International Nuclear Information System (INIS)

    1981-01-01

    This report describes the technical accomplishments on the commercial nuclear waste management programs and on the geologic disposal of nuclear wastes. The program is organized into eight tasks: systems, waste package, site, repository, regulatory and institutional, test facilities and excavations, land acquisition, and program management

  16. Technical progress report for the quarter 1 October-31 December 1980

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    This report describes the technical accomplishments on the commercial nuclear waste management programs and on the geologic disposal of nuclear wastes. The program is organized into eight tasks: systems, waste package, site, repository, regulatory and institutional, test facilities and excavations, land acquisition, and program management. (DLC)

  17. Volatiles combustion in fluidized beds. Technical progress report, 4 March 1993--3 June 1993

    Energy Technology Data Exchange (ETDEWEB)

    Hesketh, R.P.

    1993-09-01

    The goal of this project is to investigate the conditions in which volatiles will burn within both the dense and freeboard regions of fluidized beds. Experiments using a fluidized bed operated at incipient fluidization will be performed to characterize the effect of particle surface area, initial fuel concentration, and particle type on the inhibition of volatiles within a fluidized bed. The work conducted during the period 4 March, 1993 through 3 June, 1993 is reported in this technical progress report. The work during this time period consists primarily of the startup and trouble shooting of the fluidized bed reactor and gas phase modeling of methane and propane.

  18. National Council on Radiation Protection and Measurements semiannual technical progress report, March 1989--August 1989

    International Nuclear Information System (INIS)

    Ney, W.R.

    1991-01-01

    This semiannual technical progress report is for the period 1 March 1989 through 31 August 1989. This National Council on Radiation Protection and Measurements (NCRP) program is designed to provide recommendations for radiation protection based on scientific principles. During this period several reports were published covering the topics of occupational radiation exposure, medical exposure, radon control, dosimetry, and radiation protection standards. Accomplishments of various committees are also reported; including the committees on dental x-ray protection, radiation safety in uranium mining and milling, ALARA, instrumentation, records maintenance, occupational exposures of medical personnel, emergency planning, and others. (SM)

  19. Technical progress and efficiency changes in football teams participating in the UEFA Champions League

    Directory of Open Access Journals (Sweden)

    Lucía Isabel García Cebrián

    2015-09-01

    Full Text Available This paper commits to calculate and analyze productivy levels and its components for teams that participated in the UEFA Champions League between 2003 and 2012. It will pursue three objectives: 1 evaluate resources usage, 2 analyze the productivity levels of the football teams and the sports results, and 3 see the influence of participation experience in reference to productivity and sports results. Using Malmquist Productivity Index, the results reflect a lack of consistent progression of efficiency, productivity, and technical change. This competition does not reward the efficient usage of resources and there is not a conclusive relationshop between permanence in the competition and productivity.

  20. Western Research Institute: Annual technical progress report, October 1987--September 1988

    Energy Technology Data Exchange (ETDEWEB)

    1988-12-01

    This report describes the technical progress made by the Western Research Institute of the University of Wyoming Research Institute of the University of Wyoming Research Corporation on work performed for the period October 1, 1987 through September 30, 1988. This research involves five resource areas: oil shale, tar sand, underground coal gasification, advanced process technology, and advanced fuels research. Under the terms of the cooperative agreement, an annual project plan has been approved by DOE. The work reported herein reflects the implementation of the research in the plan and follows the structure used therein. 49 refs., 32 figs., 87 tabs.

  1. Decontamination Systems Information and Research Program. Quarterly technical progress report, January 1--March 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-04-01

    This reports reports the progress/efforts performed on six technical projects: 1. systematic assessment of the state of hazardous waste clean-up technologies; 2. site remediation technologies (SRT):drain- enhanced soil flushing for organic contaminants removal; 3. SRT: in situ bio-remediation of organic contaminants; 4. excavation systems for hazardous waste sites: dust control methods for in-situ nuclear waste handling; 5. chemical destruction of polychlorinated biphenyls; and 6. development of organic sensors: monolayer and multilayer self-assembled films for chemical sensors.

  2. Nuclear structure theory. Annual technical progress report, October 1, 1976--September 30, 1977

    International Nuclear Information System (INIS)

    French, J.B.; Koltun, D.S.

    1977-01-01

    This report summarizes progress during the past year in the following areas of nuclear structure and reaction theory: (1) statistical spectroscopy, including giant resonances for beta and electromagnetic excitation and sum rules (including inverse-energy-weighted sum rules), statistical methods of truncating shell model spaces and renormalization of operators, study of state labelling and ''chains'' of groups, evaluation of fluctuation measures, technical aspects of operator averaging; (2) meson interactions with nuclei, including scattering and absorption of mesons by nuclei (general methods), models for absorption, single- and double-charge exchange of pions, role of rho mesons

  3. GT-MHR COMMERCIALZATION STUDY. TECHNICAL PROGRESS AND COST MANAGEMENT REPORT FOR THE PERIOD JUNE 1 THROUGH JUNE 30, 2003

    International Nuclear Information System (INIS)

    SHENOY, A.S.

    2003-01-01

    A271 GT-MHR COMMERCIALZATION STUDY TECHNICAL PROGRESS AND COST MANAGEMENT REPORT FOR THE PERIOD JUNE 1 THROUGH JUNE 30, 2003. Petten was provided with irradiation dimensional change data for both fuel compacts and H-451 graphite for design of the graphite sleeves that hold the fuel compacts to be irradiated in HFR-EU2. The Fuel Sample Product Specification for the Fuel Performance Irradiation Test Capsule MHR-2 was completed and approved. A Work Breakdown Structure was prepared for the development and qualification of advanced coated-particle fuels capable of meeting anticipated fuel performance requirements and work was initiated on preparation of schedules and a cost estimates for the test matrices

  4. GT-MHR COMMERCIALIZATION STUDY TECHNICAL PROGRESS AND COST MANAGEMENT REPORT FOR THE PERIOD AUGUST 1 THROUGH AUGUST 31, 2003

    International Nuclear Information System (INIS)

    Shenoy, A.S.

    2003-01-01

    OAK A271 GT-MHR COMERCIALiZATION STUDY TECHNICAL PROGRESS AND COST MANAGEMENT REPORT FOR THE PERIOD AUGUST 1 THROUGH AUGUST 31, 2003. In the process of fabricating the MHR-1 irradiation test capsule, Petten has advised that three thermocouples (out of 24) and the Self Powered Neutron detector were damaged during high temperature brazing with the upper capsule lid. Procurement of new TCs and SPN is in process but there will be a delay in the irradiation test of about nine weeks. Startup of the irradiation is now projected to be July or August 2004. In preparation for performing the nuclear design analysis activities required by the advanced fuel studies task, a complete 3-D nuclear design analysis is first being performed of the GT-MHR reference design. This will serve as the baseline for studies of the advanced fuel nuclear design performance

  5. The progress test of medicine: the Dutch experience

    NARCIS (Netherlands)

    Tio, R.A.; Schutte, B.; Meiboom, A.A.; Greidanus, J.; Dubois, E.A.; Bremers, A.J.

    2016-01-01

    Progress testing in the Netherlands has a long history. It was first introduced at one medical school which had a problem-based learning (PBL) curriculum from the start. Later, other schools with and without PBL curricula joined. At present, approximately 10,000 students sit a test every three

  6. Technical baseline description for in situ vitrification laboratory test equipment

    International Nuclear Information System (INIS)

    Beard, K.V.; Bonnenberg, R.W.; Watson, L.R.

    1991-09-01

    IN situ vitrification (ISV) has been identified as possible waste treatment technology. ISV was developed by Pacific Northwest Laboratory (PNL), Richland, Washington, as a thermal treatment process to treat contaminated soils in place. The process, which electrically melts and dissolves soils and associated inorganic materials, simultaneously destroys and/or removes organic contaminants while incorporating inorganic contaminants into a stable, glass-like residual product. This Technical Baseline Description has been prepared to provide high level descriptions of the design of the Laboratory Test model, including all design modifications and safety improvements made to data. Furthermore, the Technical Baseline Description provides a basic overview of the interface documents for configuration management, program management interfaces, safety, quality, and security requirements. 8 figs

  7. Testing the performance of technical trading rules in the Chinese markets based on superior predictive test

    Science.gov (United States)

    Wang, Shan; Jiang, Zhi-Qiang; Li, Sai-Ping; Zhou, Wei-Xing

    2015-12-01

    Technical trading rules have a long history of being used by practitioners in financial markets. The profitable ability and efficiency of technical trading rules are yet controversial. In this paper, we test the performance of more than seven thousand traditional technical trading rules on the Shanghai Securities Composite Index (SSCI) from May 21, 1992 through June 30, 2013 and China Securities Index 300 (CSI 300) from April 8, 2005 through June 30, 2013 to check whether an effective trading strategy could be found by using the performance measurements based on the return and Sharpe ratio. To correct for the influence of the data-snooping effect, we adopt the Superior Predictive Ability test to evaluate if there exists a trading rule that can significantly outperform the benchmark. The result shows that for SSCI, technical trading rules offer significant profitability, while for CSI 300, this ability is lost. We further partition the SSCI into two sub-series and find that the efficiency of technical trading in sub-series, which have exactly the same spanning period as that of CSI 300, is severely weakened. By testing the trading rules on both indexes with a five-year moving window, we find that during the financial bubble from 2005 to 2007, the effectiveness of technical trading rules is greatly improved. This is consistent with the predictive ability of technical trading rules which appears when the market is less efficient.

  8. Progress Toward Replacing Animals in Toxicity Testing for Cosmetics

    OpenAIRE

    Nye, Marisa B.

    2006-01-01

    In the 1980’s, animal rights activists successfully motivated the cosmetic industry to begin researching alternatives to animal tests. The European Union has taken action to stimulate development and validation of alternatives to animal testing through the Sixth and Seventh Amendments to the Cosmetics Directive. In this paper, I will briefly describe the history of the search for alternatives to animal testing for cosmetics. I will then discuss the progress that has been ma...

  9. Hydrogen production by supercritical water gasification of biomass. Phase 1 -- Technical and business feasibility study, technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    The nine-month Phase 1 feasibility study was directed toward the application of supercritical water gasification (SCWG) for the economical production and end use of hydrogen from renewable energy sources such as sewage sludge, pulp waste, agricultural wastes, and ultimately the combustible portion of municipal solid waste. Unique in comparison to other gasifier systems, the properties of supercritical water (SCW) are ideal for processing biowastes with high moisture content or contain toxic or hazardous contaminants. During Phase I, an end-to-end SCWG system was evaluated. A range of process options was initially considered for each of the key subsystems. This was followed by tests of sewage sludge feed preparation, pumping and gasification in the SCW pilot plant facility. Based on the initial process review and successful pilot-scale testing, engineering evaluations were performed that defined a baseline system for the production, storage and end use of hydrogen. The results compare favorably with alternative biomass gasifiers currently being developed. The results were then discussed with regional wastewater treatment facility operators to gain their perspective on the proposed commercial SCWG systems and to help define the potential market. Finally, the technical and business plans were developed based on perceived market needs and the projected capital and operating costs of SCWG units. The result is a three-year plan for further development, culminating in a follow-on demonstration test of a 5 MT/day system at a local wastewater treatment plant.

  10. Technical concept for a greater-confinement-disposal test facility

    International Nuclear Information System (INIS)

    Hunter, P.H.

    1982-01-01

    Greater confinement disposal (GCO) has been defined by the National Low-Level Waste Program as the disposal of low-level waste in such a manner as to provide greater containment of radiation, reduce potential for migration or dispersion or radionuclides, and provide greater protection from inadvertent human and biological intrusions in order to protect the public health and safety. This paper discusses: the need for GCD; definition of GCD; advantages and disadvantages of GCD; relative dose impacts of GCD versus shallow land disposal; types of waste compatible with GCD; objectives of GCD borehole demonstration test; engineering and technical issues; and factors affecting performance of the greater confinement disposal facility

  11. Surgical resident technical skill self-evaluation: increased precision with training progression.

    Science.gov (United States)

    Quick, Jacob A; Kudav, Vishal; Doty, Jennifer; Crane, Megan; Bukoski, Alex D; Bennett, Bethany J; Barnes, Stephen L

    2017-10-01

    Surgical resident ability to accurately evaluate one's own skill level is an important part of educational growth. We aimed to determine if differences exist between self and observer technical skill evaluation of surgical residents performing a single procedure. We prospectively enrolled 14 categorical general surgery residents (six post-graduate year [PGY] 1-2, three PGY 3, and five PGY 4-5). Over a 6-month period, following each laparoscopic cholecystectomy, residents and seven faculty each completed the Objective Structured Assessment of Technical Skills (OSATS). Spearman's coefficient was calculated for three groups: senior (PGY 4-5), PGY3, and junior (PGY 1-2). Rho (ρ) values greater than 0.8 were considered well correlated. Of the 125 paired assessments (resident-faculty each evaluating the same case), 58 were completed for senior residents, 54 for PGY3 residents, and 13 for junior residents. Using the mean from all OSATS categories, trainee self-evaluations correlated well to faculty (senior ρ 0.97, PGY3 ρ 0.9, junior ρ 0.9). When specific OSATS categories were analyzed, junior residents exhibited poor correlation in categories of respect for tissue (ρ -0.5), instrument handling (ρ 0.71), operative flow (ρ 0.41), use of assistants (ρ 0.05), procedural knowledge (ρ 0.32), and overall comfort with the procedure (ρ 0.73). PGY3 residents lacked correlation in two OSATS categories, operative flow (ρ 0.7) and procedural knowledge (ρ 0.2). Senior resident self-evaluations exhibited strong correlations to observers in all areas. Surgical residents improve technical skill self-awareness with progressive training. Less-experienced trainees have a tendency to over-or-underestimate technical skill. Copyright © 2017 Elsevier Inc. All rights reserved.

  12. Microwave plasma source for neutral-beam injection systems. Quarterly technical progress report

    International Nuclear Information System (INIS)

    1981-01-01

    The overall program is described and the technical and programmatic reasons for the decision to pursue both the RFI and ECH sources into the current hydrogen test stage is discussed. We consider the general characteristics of plasma sources in the parameter regime of interest for neutral beam applications. The operatonal characteristics, advantages and potential problems of RFI and ECH sources are discussed. In these latter two sections we rely heavily on experience derived from developing RFI and ECH ion engine sources for NASA

  13. Experimental studies of elementary particle interactions at high energies: Technical progress report

    International Nuclear Information System (INIS)

    1987-01-01

    This paper discusses progress of experiments at CERN and Fermilab. At CERN, data accumulation and analysis is discussed for the UA-6 experiment, which involves proton-antiproton collisions. At Fermilab, the testing of a collider detector for the Tevatron is discussed

  14. Modeling the impacts of climate change and technical progress on the wheat yield in inland China: An autoregressive distributed lag approach.

    Science.gov (United States)

    Zhai, Shiyan; Song, Genxin; Qin, Yaochen; Ye, Xinyue; Lee, Jay

    2017-01-01

    This study aims to evaluate the impacts of climate change and technical progress on the wheat yield per unit area from 1970 to 2014 in Henan, the largest agricultural province in China, using an autoregressive distributed lag approach. The bounded F-test for cointegration among the model variables yielded evidence of a long-run relationship among climate change, technical progress, and the wheat yield per unit area. In the long run, agricultural machinery and fertilizer use both had significantly positive impacts on the per unit area wheat yield. A 1% increase in the aggregate quantity of fertilizer use increased the wheat yield by 0.19%. Additionally, a 1% increase in machine use increased the wheat yield by 0.21%. In contrast, precipitation during the wheat growth period (from emergence to maturity, consisting of the period from last October to June) led to a decrease in the wheat yield per unit area. In the short run, the coefficient of the aggregate quantity of fertilizer used was negative. Land size had a significantly positive impact on the per unit area wheat yield in the short run. There was no significant short-run or long-run impact of temperature on the wheat yield per unit area in Henan Province. The results of our analysis suggest that climate change had a weak impact on the wheat yield, while technical progress played an important role in increasing the wheat yield per unit area. The results of this study have implications for national and local agriculture policies under climate change. To design well-targeted agriculture adaptation policies for the future and to reduce the adverse effects of climate change on the wheat yield, climate change and technical progress factors should be considered simultaneously. In addition, adaptive measures associated with technical progress should be given more attention.

  15. Modeling the impacts of climate change and technical progress on the wheat yield in inland China: An autoregressive distributed lag approach.

    Directory of Open Access Journals (Sweden)

    Shiyan Zhai

    Full Text Available This study aims to evaluate the impacts of climate change and technical progress on the wheat yield per unit area from 1970 to 2014 in Henan, the largest agricultural province in China, using an autoregressive distributed lag approach. The bounded F-test for cointegration among the model variables yielded evidence of a long-run relationship among climate change, technical progress, and the wheat yield per unit area. In the long run, agricultural machinery and fertilizer use both had significantly positive impacts on the per unit area wheat yield. A 1% increase in the aggregate quantity of fertilizer use increased the wheat yield by 0.19%. Additionally, a 1% increase in machine use increased the wheat yield by 0.21%. In contrast, precipitation during the wheat growth period (from emergence to maturity, consisting of the period from last October to June led to a decrease in the wheat yield per unit area. In the short run, the coefficient of the aggregate quantity of fertilizer used was negative. Land size had a significantly positive impact on the per unit area wheat yield in the short run. There was no significant short-run or long-run impact of temperature on the wheat yield per unit area in Henan Province. The results of our analysis suggest that climate change had a weak impact on the wheat yield, while technical progress played an important role in increasing the wheat yield per unit area. The results of this study have implications for national and local agriculture policies under climate change. To design well-targeted agriculture adaptation policies for the future and to reduce the adverse effects of climate change on the wheat yield, climate change and technical progress factors should be considered simultaneously. In addition, adaptive measures associated with technical progress should be given more attention.

  16. Nuclear structure theory. Annual technical progress report, July 1, 1975--September 30, 1976

    International Nuclear Information System (INIS)

    French, J.B.; Koltun, D.S.

    1976-01-01

    This report summarizes progress during the past year in the following areas of nuclear structure and reaction theory: Meson interactions with nucleons and nuclei, including elastic and inelastic scattering of pions, three-body theories of scattering and absorption of pions by deuterons, π-p bremsstrahlung, and multiple-excitation models for meson absorption by heavier nuclei. Studies of the inverse scattering problem including 1 S 0 nucleon-nucleon scattering; the relativistic two-body problem, particularly for relativistic effects at low energies: the unitary-pole expansion in nucleon-nucleon scattering with hard-core interactions. Statistical spectroscopy including: strength distributions and sum rules(both energy weighted and inverse energy weighted) for nuclear excitations; fluctuations and correlations in spectra, strengths and expectation values; studies of Garvey-Kelson and similar mass relationships; spectroscopy in huge spaces including spectral methods for renormalization of the interaction and for using (two + three)-body Skyrme interactions; technical aspects of operator averaging

  17. The U.S. nuclear waste management program - technical progress at Yucca Mountain

    Energy Technology Data Exchange (ETDEWEB)

    Barrett, L.H. [U.S. Department of Energy (United States)

    2001-07-01

    This paper discusses the current status of a national program being developed by the U.S. Department of Energy for the management of spent nuclear fuel and high-level radioactive waste produced by civilian nuclear power generation and defense-related activities. In 1987 the U.S. Congress directed the Department to characterize the Yucca Mountain site in Nevada and determine its suitability for development of a geologic repository. This paper will focus on the technical progress that has been made after more than 15 years of scientific and engineering investigations at Yucca Mountain, and the remaining work that is being done to support a decision on whether to recommend the site for development of a geologic repository. (author)

  18. GPHS-RTGs in support of the Cassini Mission. Semi annual technical progress report, 1 April 1996--29 September 1996

    International Nuclear Information System (INIS)

    1996-01-01

    This technical progress report discusses work on the Radioisotope Generators and Ancillary Activities for the Cassini spacecraft. The Cassini spacecraft is expected to launch in October 1997, and will explore Saturn and its moons. This progress report discusses issues in: spacecraft integration and liason, engineering support, safety, qualified unicouple fabrication, ETG fabrication and testing, ground support equipment, RTG shipping and launch support, designs, reviews and mission application. Safety analysis of the RTGs during reentry and launch accidents are covered. This report covers the period of April 1 to September 29, 1996

  19. Technical Progress Report on Application and Development of Appropriate Tools and Technologies for Cost-Effective Carbon Sequestration

    Energy Technology Data Exchange (ETDEWEB)

    Bill Stanley; Patrick Gonzalez; Sandra Brown; Jenny Henman; Ben Poulter; Sarah Woodhouse Murdock; Neil Sampson; Tim Pearson; Sarah Walker; Zoe Kant; Miguel Calmon; Gilberto Tiepolo

    2006-06-30

    The Nature Conservancy is participating in a Cooperative Agreement with the Department of Energy (DOE) National Energy Technology Laboratory (NETL) to explore the compatibility of carbon sequestration in terrestrial ecosystems and the conservation of biodiversity. The title of the research project is ''Application and Development of Appropriate Tools and Technologies for Cost-Effective Carbon Sequestration''. The objectives of the project are to: (1) improve carbon offset estimates produced in both the planning and implementation phases of projects; (2) build valid and standardized approaches to estimate project carbon benefits at a reasonable cost; and (3) lay the groundwork for implementing cost-effective projects, providing new testing ground for biodiversity protection and restoration projects that store additional atmospheric carbon. This Technical Progress Report discusses preliminary results of the six specific tasks that The Nature Conservancy is undertaking to answer research needs while facilitating the development of real projects with measurable greenhouse gas reductions. The research described in this report occurred between April 1st and July 30th 2006. The specific tasks discussed include: Task 1: carbon inventory advancements; Task 2: emerging technologies for remote sensing of terrestrial carbon; Task 3: baseline method development; Task 4: third-party technical advisory panel meetings; Task 5: new project feasibility studies; and Task 6: development of new project software screening tool. Work is being carried out in Brazil, Belize, Chile, Peru and the USA.

  20. Progresso tecnico, forme di mercato e disoccupazione. ( Technical progress, market forms and unemployment

    Directory of Open Access Journals (Sweden)

    A. ASIMAKOPULOS A.

    2013-12-01

    Full Text Available Lo scopo del presente lavoro è triplice . Il primo obiettivo è quello di sottolineare l'importanza delle intuizioni da trovare nel lavoro di Sylos Labini . Il secondo scopo è quello di espandere su di essa distinguendo tra i diversi tipi di progresso tecnico . Infine , il terzo obiettivo è quello di commentare il confronto di Labini di Ricardo e Keynes sulla possibilità di disoccupazione tecnologica . Per quanto riguarda la sua descrizione del progresso tecnologico come " risparmio di lavoro " , l'autore mostra che una descrizione più completa sarebbe più utile per i suoi scopiThe purpose of the present paper is threefold. The first purpose is to emphasise the importance of the insights to be found in Sylos Labini’s work. The second purpose is to expand upon it by distinguishing  between the different types of technical progress. Finally, the third purpose is to comment on Labini’s comparison of Ricardo and Keynes on the possibility of technological unemployment. Regarding his description of technological progress as “labour saving”, the author shows that a more comprehensive description would be more useful for his purposes.JEL: E24, J64, O33

  1. The effects of environmental regulation and technical progress on CO2 Kuznets curve: An evidence from China

    International Nuclear Information System (INIS)

    Yin, Jianhua; Zheng, Mingzheng; Chen, Jian

    2015-01-01

    Based on environmental Kuznets curve theory, a panel data model which takes environmental regulation and technical progress as its moderating factors was developed to analyse the institutional and technical factors that affect the path of low-carbon economic development. The results indicated that there was a CO 2 emission Kuznets curve seen in China. Environmental regulation had a significant moderating effect on the curve, and the inflection of CO 2 emissions could come substantially earlier under stricter environmental regulation. Meanwhile, the impact of technical progress on the low-carbon economic development path had a longer hysteresis effect but restrained CO 2 emission during its increasing stage and accelerated its downward trend during the decreasing stage which was conducive to emission reduction. Strict environmental regulation could force the high-carbon emitting industries to transfer from the eastern regions to the central or the western regions of China, which would make the CO 2 Kuznets curve higher in its increasing stage and lower in its decreasing stage than that under looser regulation. Furthermore, energy efficiency, energy structure, and industrial structure exerted a significant direct impact on CO 2 emissions; we should consider the above factors as essential in the quest for low-carbon economic development. - Highlights: • Estimate moderating effect of environmental regulation and technical progress on EKC. • There was a CO 2 emission Kuznets curve in effect in China. • Environmental regulation presents significant moderating effect on EKC. • Technical progress moderates the relationship between income and CO 2 emissions

  2. Progress of the Hanford Bulk Vitrification Project ICVTM Testing Program

    International Nuclear Information System (INIS)

    Witwer, K.S.; Woolery, D.W.; Dysland, E.J.

    2006-01-01

    In June 2004, the Bulk Vitrification Project was initiated with the intent to engineer, construct and operate a full-scale bulk vitrification pilot-plant to treat low-activity tank waste from Hanford tank 241-S-109. The project, managed by CH2M HILL Hanford Group, Inc., and performed by AMEC Earth and Environmental, Inc. (AMEC), will develop and operate a full-scale demonstration facility to exhibit the effectiveness of the bulk vitrification process under actual operating conditions. Since project initiation, testing has been undertaken using crucible-scale, 1/6 linear (engineering) scale, and full-scale vitrification equipment. Crucible-scale testing, coupled with engineering-scale testing, helps establish process limitations of selected glass formulations. Full-scale testing provides critical design verification of the In Container Vitrification (ICV) TM process both prior to and during operation of the demonstration facility. Beginning in late 2004, several full-scale tests have been performed at AMEC's test site, located adjacent to the U.S. Department of Energy's Hanford Site, in Richland, WA. Early testing involved verification of melt startup methodology, followed by subsequent full-melt testing to validate critical design parameters and demonstrate the 'Bottom-Up, Feed While Melt' process. As testing has progressed, design improvements have been identified and incorporated into each successive test. Full scale testing at AMEC's test site is currently scheduled to complete in 2006, with continued full-scale operational testing at the demonstration facility on the Hanford Site starting in 2007. Additional engineering scale testing will validate recommended glass formulations that have been provided by the Pacific Northwest National Laboratory (PNNL). This testing is expected to continue through 2006. This paper discusses the progress of the full-scale and engineering scale testing performed to date. Crucible-scale testing, a critical step in developing

  3. Progress and Strategies for Testing of Materials for Solar Panels

    Energy Technology Data Exchange (ETDEWEB)

    Kurtz, Sarah

    2017-04-25

    Accelerated testing is key to confident launch of a new product. However, for new products like solar panels, the best approach is not always clear. The challenge for materials manufacturers is that test times can be long. Also, small-coupon testing may not predict the behavior in the full-size module, but testing of the full-size module is too expensive. As a result, solar panel test standards like IEC 61215 are useful, but are not sufficient. Material manufacturers have needed to define their own test protocols. This presentation will review some historical data (e.g., data show that manufacturers are making great progress toward reducing encapsulant discoloration) and describe advances in material testing (for example, new techniques are being demonstrated on how to more quantitatively assess adhesion, detect tendency for delamination, and understand how encapsulant properties affect other properties like cracking of cells). The International PV Quality Assurance Task Force has been researching climate-specific weathering tests toward the goal of defining international standards that would simplify qualification and quality assurance testing for materials. The status of these tests and the strategies for how to organize these standards to best meet the needs of the industry will be discussed.

  4. Influence of PBL with open-book tests on knowledge retention measured with progress tests

    NARCIS (Netherlands)

    Heijne-Penninga, M.; Kuks, J. B. M.; Hofman, W. H. A.; Muijtjens, A. M. M.; Cohen-Schotanus, J.

    The influence of problem-based learning (PBL) and open-book tests on long-term knowledge retention is unclear and subject of discussion. Hypotheses were that PBL as well as open-book tests positively affect long-term knowledge retention. Four progress test results of fifth and sixth-year medical

  5. ROLLER RIG TESTING AT THE CZECH TECHNICAL UNIVERSITY

    Directory of Open Access Journals (Sweden)

    J. Kalivoda

    2016-08-01

    Full Text Available Purpose. Although the advancements in computer simulation technology have paved way to provide very reliable simulation results, track tests still play an essential role during the process of development and homologation of any railway vehicle. On the other hand, track tests depend on weather conditions, are difficult to organize and are not suitable for testing vehicles in critical situations. On a roller rig, the tested vehicle is longitudinally fixed and a track is replaced by rotating rollers. Such device offer testing of railway vehicle running dynamics in safe and stable laboratory environment. The purpose of an article is to investigate and describe roller rig testing at the Czech technical university in Prague (CTU. Methodology. In the paper it is shown the history of development of the scaled CTU roller rig from the earlier stages until the current projects for which the CTU roller rig is utilized for. The current design of the experimental bogie, roller rig, sensors instrumentation and types of experiments conducted at the CTU roller rig are described in more detail. Findings. Although the differences in vehicle behaviour on a track and a scaled model on a roller rig are not negligible, scaled roller rig experiments are found as a relatively inexpensive way for verification and demonstration of computer simulations results. They are especially useful for verification of multibody system simulations (MBS of entirely new running gear concepts. Originality. The CTU roller rig is currently used for the experiments with active controlled wheelset guidance. According to simulations results published in many papers such systems offer, in principle, better performance compared to conventional passive vehicles. However, utilization and testing of active controlled wheelset guidance on vehicles is still rare. CTU roller rig serves as a tool to verify computer simulations and demonstrate benefits of active wheelset guidance. Practical value

  6. Final Technical Progress Report: Development of Low-Cost Suspension Heliostat; December 7, 2011 - December 6, 2012

    Energy Technology Data Exchange (ETDEWEB)

    Bender, W.

    2013-01-01

    Final technical progress report of SunShot Incubator Solaflect Energy. The project succeeded in demonstrating that the Solaflect Suspension Heliostat design is viable for large-scale CSP installations. Canting accuracy is acceptable and is continually improving as Solaflect improves its understanding of this design. Cost reduction initiatives were successful, and there are still many opportunities for further development and further cost reduction.

  7. Generation and focusing of pulsed intense ion beams. Technical progress report, 20 August 1981-30 September 1982

    International Nuclear Information System (INIS)

    Hammer, D.A.; Kusse, B.R.; Sudan, R.N.

    1983-07-01

    The progress on this contract is described in two parts. The first deals with the technical operation of the LION accelerator which is the exact equivalent to one line of PBFA-I. The second part is concerned with the experimental results on the ion diode mounted at the front end of the LION accelerator

  8. Impact of Environmental Regulation and Technical Progress on Industrial Carbon Productivity: An Approach Based on Proxy Measure

    Directory of Open Access Journals (Sweden)

    Huan Zhang

    2016-08-01

    Full Text Available This research aims to study the main influencing factors of China’s industrial carbon productivity by incorporating environmental regulation and technical progress into an econometric model. The paper focuses on data from 35 of China’s industrial sectors and covers the period from 2006 to 2014, in order to examine the impact of environmental regulation and technical progress on carbon productivity. Methods applied include panel fixed effect model, panel random effect model and two stage least squares with instrumental variables (IV-2SLS. The effect of environmental regulation and technical progress has industrial heterogeneity. The paper subdivides industrial sectors into capital and technology intensive, resource intensive and labor intensive sectors according to factor intensiveness. The estimation results of the subgroups have uncovered that for capital and technology intensive and resource intensive sectors, environmental regulation has a more significant impact than technical progress; while for labor intensive sectors, innovation more significantly influences carbon productivity. In addition, foreign direct investment (FDI and industrialization level facilitate improving carbon productivity for the full sample. By contrast, industrial structure inhibits the overall industrial carbon productivity. The industry-specific results indicate that for capital and technology intensive sectors, optimizing of the industrial structure can improve carbon productivity; for resource intensive sectors, FDI and energy consumption structure should be emphasized more; for labor intensive sectors, industrialization levels help enhance carbon productivity. Finally the industrial sector-specific policy suggestions are proposed.

  9. Flexible electronic feedback using the virtues of progress testing.

    Science.gov (United States)

    Muijtjens, Arno M M; Timmermans, Ilske; Donkers, Jeroen; Peperkamp, Robert; Medema, Harro; Cohen-Schotanus, Janke; Thoben, Arnold; Wenink, Arnold C G; van der Vleuten, Cees P M

    2010-01-01

    The potential richness of the feedback for learners and teachers is one of the educational advantages of progress tests (PTs). Every test administration yields information on a student's knowledge level in each sub-domain of the test (cross-sectional information), and it adds a next point to the corresponding knowledge growth curve (longitudinal information). Traditional paper-based feedback has severe limitations and requires considerable effort from the learners to give meaning to the data. We reasoned that the PT data should be flexibly accessible in all pathways and with any available comparison data, according to the personal interest of the learner. For that purpose, a web-based tool (Progress test Feedback, the ProF system) was developed. This article presents the principles and features of the generated feedback and shows how it can be used. In addition to enhancement of the feedback, the ProF database of longitudinal PT-data also provides new opportunities for research on knowledge growth, and these are currently being explored.

  10. Decontamination Systems Information and Research Program. Quarterly technical progress report, July 1--September 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-10-01

    Progress reports are presented for the following projects: systematic assessment of the state of hazardous waste clean-up technologies; site remediation technologies--drain-enhanced soil flushing (DESF) for organic contaminants removal; excavation systems for hazardous waste sites; chemical destruction of polychlorinated biphenyls; development of organic sensors--monolayer and multilayer self-assembled films for chemical sensors; Winfield Lock and Dam remediation; Winfield cleanup survey; assessment of technologies for hazardous waste site remediation--non-treatment technologies and pilot scale test facility implementation; assessment of environmental remediation storage technology; assessment of environmental remediation excavation technology; assessment of environmental remediation monitoring technology; and remediation of hazardous sites with steam reforming.

  11. Decontamination Systems Information and Research Program. Quarterly technical progress report, July 1--September 30, 1993

    International Nuclear Information System (INIS)

    1993-10-01

    Progress reports are presented for the following projects: systematic assessment of the state of hazardous waste clean-up technologies; site remediation technologies--drain-enhanced soil flushing (DESF) for organic contaminants removal; excavation systems for hazardous waste sites; chemical destruction of polychlorinated biphenyls; development of organic sensors--monolayer and multilayer self-assembled films for chemical sensors; Winfield Lock and Dam remediation; Winfield cleanup survey; assessment of technologies for hazardous waste site remediation--non-treatment technologies and pilot scale test facility implementation; assessment of environmental remediation storage technology; assessment of environmental remediation excavation technology; assessment of environmental remediation monitoring technology; and remediation of hazardous sites with steam reforming

  12. Experimental tests of general relativity: recent progress and future directions

    International Nuclear Information System (INIS)

    Turyshev, S G

    2009-01-01

    Einstein's general theory of relativity is the standard theory of gravity, especially where the needs of astronomy, astrophysics, cosmology, and fundamental physics are concerned. As such, this theory is used for many practical purposes involving spacecraft navigation, geodesy, and time transfer. We review the foundations of general relativity, discuss recent progress in tests of relativistic gravity, and present motivations for the new generation of high-accuracy tests of new physics beyond general relativity. Space-based experiments in fundamental physics are presently capable of uniquely addressing important questions related to the fundamental laws of nature. We discuss the advances in our understanding of fundamental physics that are anticipated in the near future and evaluate the discovery potential of a number of recently proposed space-based gravitational experiments. (reviews of topical problems)

  13. Progress on qualification testing methodology study of electric cables

    International Nuclear Information System (INIS)

    Yoshida, K.; Seguchi, T.; Okada, S.; Ito, M.; Kusama, Y.; Yagi, T.; Yoshikawa, M.

    1983-01-01

    Many instrumental, control and power cables are installed in nuclear power plants, and these cables contain a large amount of organic polymers as insulating and jacketing materials. They are exposed to radiation at high dose rate, steam at high temperature and chemical (or water) spray simultaneously when a LOCA occurs. Under such conditions, the polymers tend to lose their original properties. For reactor safety, the cables should be functional even if they are subjected to a loss-of-coolant accident (LOCA) at the end of their intended service life. In Japan, cable manufacturers qualify their cables according to the proposed test standard issued from IEEJ in 1982, but the standard still has many unsolved problems or uncertainties which have been dealt with tentatively through the manufacturer-user's agreement. The objectives of this research are to study the methodologies for qualification testing of electric wires and cables, and to provide the improved technical bases for modification of the standard. Research activities are divided into the Accident (LOCA) Testing Methodology and the Accelerated Aging Methodology

  14. Technical progress report, Contracts DE-AC02-81ER40014, 40015 and 40016

    International Nuclear Information System (INIS)

    1981-01-01

    This Progress Report summarizes work carried out at the Nuclear Physics Laboratory of the University of Colorado from November 1, 1980 through July 31, 1981, under contracts between the University of Colorado and the United States Department of Energy. The shorter report period of nine months is due to a change to an earlier submission date this year for our proposal for support to begin February 1, 1982. Cyclotron operation, research, and development have been supported under contract DE-AC02-81ER40014. The AVF cyclotron has continued to provide reliable and versatile beams of protons, deuterons, 3 He and 4 He. A wide variety of research results in direct reactions, nuclear structure, and compound reaction mechanisms can be noted in this Progress Report, correlated in many cases to current problems in intermediate energy physics. Theoretical work on nuclear reactions, carried out under contract DE-AC02-81ER40015, has been well matched to our experimental programs in low and intermediate energy physics. One important result has been the recasting of the DWBA in an eikonal expansion suited to high energy reactions. Our efforts in intermediate energy physics, under contract DE-AC02-81ER40016, have emphasized pion scattering studies at LAMPF and TRIUMF and proton induced charge exchange reactions at IUCF. Data for an important test of hadronic charge symmetry have been completed at two energies, using elastic pion-deuteron scattering

  15. Research in elementary particle physics. Technical progress report, June 1, 1985-May 31, 1986

    International Nuclear Information System (INIS)

    Kirsch, L.E.; Schnitzer, H.J.; Bensinger, J.R.; Abbott, L.F.; Blocker, C.A.

    1986-01-01

    Progress is reported in both experimental and theoretical elementary particle research. Experimental activities include: construction of the Forward Electromagnetic Shower Counters for the Collider Detector at Fermilab (CDF); a test run in the CDF, involving observation of a small number of proton-antiproton collisions; design of a self-contained single wire proportional chamber with pressure and temperature sensing for monitoring the gain of gases used by various components of the CDF; data acquisition, and calibration. Also included are a search for a dibaryon of strangeness=-1; hyperon weak radiative decay. Theoretical research is reported in the areas of quantum field theory, string theory, elementary particle phenomenology, cosmology, field theory in curved spacetimes, and cosmology. 34 refs

  16. Savannah River Plant, Works Technical Department monthly progress report for March 1956

    International Nuclear Information System (INIS)

    1956-01-01

    This document details activities of the Works Technical Department during the month of March 1956. It covers reactor technology, separations technology, engineering assistance and heavy water technology

  17. Ion rings for magnetic fusion. Technical progress report, August 1, 1993--June 1, 1994

    International Nuclear Information System (INIS)

    Sudan, R.N.

    1994-01-01

    In Our Proposal ''Ion Rings for Magnetic Fusion'' of January 6, 1993, Stage I of our Proposed Program plan (the 12 months) consisted of the following tasks: Experiments on the existing ion ring experimental system IREX to test a new magnetically-controlled anode plasma source (MAP) for the ion beam diode injector; numerical simulations of ion ring formation to optimize design parameters for the field reversed ion ring experiment (FIREX) to be built and operated in Stage II; and designing the power supply for the FIREX injector and the magnetic field system using results for A and B. During the past 7 1/2 months our work has progressed according to the above plan. In addition to testing the MAP diode on IREX we have tested the EMFAPS (evaporating metal film anode plasma source) anode on the Sandia National Laboratories funded LION pulsed power generator. As a result of these experiments, described this paper, we have arrived at the conclusion that EMFAPS anode for the ion at present because the MAP diode beam diode injector is our preferred choice for is still in an early stage of development

  18. Technical specification upgrading at the Fast Flux Test Facility (FFTF)

    International Nuclear Information System (INIS)

    Baird, Q.L.; Franz, G.R.; Absher, K.R.

    1985-01-01

    The FFTF Technical Specifications were generated in 1977 and 1978 following submittal of the FSAR in 1976. A phased implementation program served to prepare the specifications for each stage of the plant startup with the complete specifications approved and implemented late in 1980 for the first ascent to full power. In January, 1983 WHC undertook an upgrading effort to implement changes to the FFTF technical specifications. This program has been pursued with appropriate attention to the CFR and industry standards and practice. Examples of these changes, discussion of the methods and planned activities for the future will be presented. Technical data will be provided to support the impact of specific limits. The benefits of changes and the criteria for change will be elaborated

  19. Small scale tests on the progressive retreat of soil slopes

    Science.gov (United States)

    Voulgari, Chrysoula; Utili, Stefano; Castellanza, Riccardo

    2015-04-01

    In this paper, the influence due to the presence of cracks on the morphologic evolution of natural cliffs subject to progressive retreat induced by weathering is investigated through small scale laboratory tests. Weathering turns hard rocks into soft rocks that maintain the structure of the intact rocks, but are characterised by higher void ratios and reduced bond strengths; soft rocks are transformed into granular soils generally called residual soils. A number of landslides develop in slopes due to weathering which results in the progressive retrogression of the slope face and the further degradation within the weathering zone. Cracks, that are widely present, can be a result of weathering and they can cause a significant decrease in their stability, as they provide preferential flow channels which increase the soil permeability and decrease the soil strength. The geological models employed until now are mainly empirical. Several researchers have tried to study the stability of slopes through experimental procedures. Centrifuge modelling is widely used to investigate the failure of slopes. Small scale tests are also an important approach, in order to study the behaviour of a slope under certain conditions, such as the existence of water, as they allow the observation of the infiltration processes, the movement of the weathering front, deformation and failure. However, the deformation response of a slope subject to weathering is not yet thoroughly clarified. In this work, a set of experiments were conducted to investigate weathering induced successive landslides. Weathering was applied to the slope model by wetting the slope crest through a rainfall simulator device. The moisture content of the soil during the tests was monitored by soil moisture sensors that were buried inside the slope model. High resolution cameras were recording the behaviour of the slope model. GeoPIV was used to analyse the frames and obtain the deformations of the slope model during the

  20. GPHS-RTGs in support of the Cassini mission. Semi annual technical progress report, 2 October 1995--31 March 1996

    International Nuclear Information System (INIS)

    1996-01-01

    The technical progress achieved during the period 2 October 1995 through 31 March 1996 on Contract No. DE-AC03-91SF18852, Radioisotope Generators and Ancillary Activities is described herein. This report is organized by the program task structure as follows: spacecraft integration and liaison; engineering support; safety; qualified unicouple fabrication; ETG fabrication, assembly, and test; ground support equipment (GSE); RTG shipping and launch support; designs, reviews, and mission applications; project management, quality assurance and reliability, contract changes, non-capital CAGO acquisition, and CAGO maintenance; contract acquired government-owned property (CAGO) acquisition; and program calendars

  1. Decomposing productivity growth allowing efficiency gains and price-induced technical progress

    NARCIS (Netherlands)

    Oude Lansink, A.G.J.M.; Silva, E.; Stefanou, S.

    2000-01-01

    Time- and firm-specific output technical efficiency measures are generated within a price-induced technological change framework. The firm-specific production frontier incorporates past prices as an argument encouraging innovation and a time trend to account for exogenous technical change. The

  2. LMFBR flexible pipe joint development program. Annual technical progress report, government fiscal year 1977

    International Nuclear Information System (INIS)

    1978-01-01

    Currently, the ASME Boiler and Pressure Vessel Code does not allow the use of flexible pipe joints (bellows) in Section III, Class 1 reactor primary piping systems. Studies have shown that the primary piping loops of LMFBR's could be simplified by using these joints. This simplification translates directly into shorter primary piping runs and reduced costs for the primary piping system. Further cost savings result through reduced vault sizes and reduced containment building diameter. In addition, the use of flexible joints localizes the motions from thermally-induced piping growth into components which are specifically designed to accommodate this motion. This reduces the stress levels in the piping system and its components. It is thus economically and structurally important that flexible piping joints be available to the LMFBR designer. The overall objective of the Flexible Joint Program is to provide this availability. This will be accomplished through the development of ASME rules which allow the appropriate use of such joints in Section III, Class 1 piping systems and through the development and demonstration of construction methods which satisfy these rules. The rule development includes analytic and testing methodology formulations which will be supported by subscale bellows testing. The construction development and demonstration encompass the design, fabrication, and in-sodium testing of prototypical LMFBR plant-size flexible pipe joints which meet all ASME rule requirements. The satisfactory completion of these developmental goals will result in an approved flexible pipe joint design for the LMFBR. Progress is summarized in the following efforts undertaken during 1977 to accomplish these goals: (1) code case support, (2) engineering and design, (3) material development, (4) testing, and (5) manufacturing development

  3. Dual curvature acoustically damped concentrating collector. Semiannual technical progress report, June 1-December 1, 1978

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-12-01

    The project's first objective is to establish, analytically, the cost and performance of design choices within the boundaries of the basic proposed concept. With these cost and performance measures as a guide, the second project objective is to design a cost-effective Dual Curvature collector module and collector field array. The third objective is to establish technical and economic concept feasibility through prototype fabrication and test. The final objective is to define the Dual Curvature collector commercialization requirements. The Dual Curvature collector uses a unique reflector module consisting of a reflective film that is tensioned on a reflector support frame. The tensioned membrane (film) surface approximates a hyperbolic paraboloid that is capable of linear focusing when the surface tracks the sun's apparent motion in one axis. The reflective film can be backed by polystyrene foam with an air space between the film and the foam surfaces. This provides damping of the reflector surface to minimize the effect of wind gusts and physical impacts. The baseline collector is intended to operate at a concentration of ten (10) or greater with a nominal absorber temperature of 150/sup 0/C (300/sup 0/F). The Component Research and Analysis tasks which lead to the selection of a baseline collector configuration are discussed. Also, some preliminary results of the Collector Module Design task are presented.

  4. Student Perceptions of the Progress Test in Two Settings and the Implications for Test Deployment

    Science.gov (United States)

    Wade, Louise; Harrison, Chris; Hollands, James; Mattick, Karen; Ricketts, Chris; Wass, Val

    2012-01-01

    Background: The Progress Test (PT) was developed to assess student learning within integrated curricula. Whilst it is effective in promoting and rewarding deep approaches to learning in some settings, we hypothesised that implementation of the curriculum (design and assessment) may impact on students' preparation for the PT and their learning.…

  5. Coal to SNG: Technical progress, modeling and system optimization through exergy analysis

    International Nuclear Information System (INIS)

    Li, Sheng; Ji, Xiaozhou; Zhang, Xiaosong; Gao, Lin; Jin, Hongguang

    2014-01-01

    Highlights: • Technical progresses of coal to SNG technologies are reported. • The entire coal to SNG system is modeled. • Coupling between SNG production and power generation is investigated. • Breakthrough points for further energy saving are determined. • System performance is optimized based on the first and second laws of thermodynamics. - Abstract: For both energy security and CO 2 emission reduction, synthetic natural gas (SNG) production from coal is an important path to implement clean coal technologies in China. In this paper, an overview of the progress of coal to SNG technologies, including the development of catalysts, reactor designs, synthesis processes, and systems integration, is provided. The coal to SNG system is modeled, the coupling between SNG production and power generation is investigated, the breakthrough points for further energy savings are determined, and the system performance is optimized based on the first and the second laws of thermodynamics. From the viewpoint of the first law of thermodynamics, the energy conversion efficiency of coal to SNG system can reach 59.8%. To reduce the plant auxiliary power, the breakthrough points are the development of low-energy-consumption oxygen production technology and gas purification technology or seeking new oxidants for coal gasification instead of oxygen. From the viewpoint of the second law of thermodynamics, the major exergy destruction in a coal to SNG system occurs in the coal gasification unit, SNG synthesis unit and the raw syngas cooling process. How to reduce the exergy destruction in these units is the key to energy savings and system performance enhancement. The conversion ratio of the first SNG synthesis reactor and the split ratio of the recycle gas are key factors that determine the performance of both the SNG synthesis process and the whole plant. A “turning point” phenomenon is observed: when the split ratio is higher than 0.90, the exergy destruction of the SNG

  6. Recent Progress in the Development of Diagnostic Tests for Malaria.

    Science.gov (United States)

    Krampa, Francis D; Aniweh, Yaw; Awandare, Gordon A; Kanyong, Prosper

    2017-09-19

    The impact of malaria on global health has continually prompted the need to develop effective diagnostic strategies. In malaria endemic regions, routine diagnosis is hampered by technical and infrastructural challenges to laboratories. These laboratories lack standard facilities, expertise or diagnostic supplies; thus, therapy is administered based on clinical or self-diagnosis. There is the need for accurate diagnosis of malaria due to the continuous increase in the cost of medication, and the emergence and spread of drug resistant strains. However, the widely utilized Giemsa-stained microscopy and immunochromatographic tests for malaria are liable to several drawbacks, including inadequate sensitivity and false-positive outcomes. Alternative methods that offer improvements in performance are either expensive, have longer turnaround time or require a level of expertise that makes them unsuitable for point-of-care (POC) applications. These gaps necessitate exploration of more efficient detection techniques with the potential of POC applications, especially in resource-limited settings. This minireview discusses some of the recent trends and new approaches that are seeking to improve the clinical diagnosis of malaria.

  7. Recent Progress in the Development of Diagnostic Tests for Malaria

    Directory of Open Access Journals (Sweden)

    Francis D. Krampa

    2017-09-01

    Full Text Available The impact of malaria on global health has continually prompted the need to develop effective diagnostic strategies. In malaria endemic regions, routine diagnosis is hampered by technical and infrastructural challenges to laboratories. These laboratories lack standard facilities, expertise or diagnostic supplies; thus, therapy is administered based on clinical or self-diagnosis. There is the need for accurate diagnosis of malaria due to the continuous increase in the cost of medication, and the emergence and spread of drug resistant strains. However, the widely utilized Giemsa-stained microscopy and immunochromatographic tests for malaria are liable to several drawbacks, including inadequate sensitivity and false-positive outcomes. Alternative methods that offer improvements in performance are either expensive, have longer turnaround time or require a level of expertise that makes them unsuitable for point-of-care (POC applications. These gaps necessitate exploration of more efficient detection techniques with the potential of POC applications, especially in resource-limited settings. This minireview discusses some of the recent trends and new approaches that are seeking to improve the clinical diagnosis of malaria.

  8. Preliminary Design Progress of the HCCR TBM for ITER testing

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dong Won; Park, Sung Dae; Kim, Dong Jun; Jin, Hyung Gon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Ahn, Mu-Young [National Fusion Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    Korea has designed a helium cooled ceramic reflector (HCCR) test blanket module (TBM) including the TBM-shield, which is called the TBM-set, to be tested in ITER, a Nuclear Facility INB-174. Through the conceptual design review (CDR), its design integrity was successfully demonstrated at the conceptual design level at various loads. After CD approval, preliminary design (PD) was started and the progress is introduced in the present study. After PD review and approval, final design and then fabrication will be started. The main purpose of PD is to design the TBM-set according to the fabrication aspect and more detailed design for interfaces with ITER machine, such as installed TBM port plug and frame. With these considering, PD of TBM-set was started. PD for HCCR TBM has been performed (so far v0.24) from the CD model. FW, BZ, SW, TES/NAS, BM, and connecting support design were performed through the analyses, if necessary. The manufacturability was the main concern for PD model development. Thermal hydraulic analysis will be performed to evaluate the temperature and pressure drop in TBM-set. The structural integrity of TBM-set will be confirmed with combined various loads condition.

  9. Savannah River Plant Works Technical Department monthly progress report for May 1958: Deleted Version

    Energy Technology Data Exchange (ETDEWEB)

    1958-06-17

    This progress report by the Atomic Energy Division of the Savannah River Plant covers: Reactor Technology; Separation Technology; Engineering Assistance; Health Physics; and General Laboratory Work. (JT)

  10. A Simple extension of Dematerialization Theory: Incorporation of Technical Progress and the Rebound Effect

    OpenAIRE

    Magee, Christopher L.; Devezas, Tessaleno C.

    2016-01-01

    Dematerialization is the reduction in the quantity of materials needed to produce something useful over time. Dematerialization fundamentally derives from ongoing increases in technical performance but it can be counteracted by demand rebound - increases in usage because of increased value (or decreased cost) that also results from increasing technical performance. A major question then is to what extent technological performance improvement can offset and is offsetting continuously increasin...

  11. Solvent refined coal (SRC) process. Quarterly technical progress report, January 1980-March 1980. [In process streams

    Energy Technology Data Exchange (ETDEWEB)

    1981-01-01

    This report summarizes the progress of the Solvent Refined Coal (SRC) project at the SRC Pilot Plant in Fort Lewis, Wahsington, and the Process Development Unit (P-99) in Harmarville, Pennsylvania. After the remaining runs of the slurry preheater survey test program were completed January 14, the Fort Lewis Pilot Plant was shut down to inspect Slurry Preheater B and to insulate the coil for future testing at higher rates of heat flux. Radiographic inspection of the coil showed that the welds at the pressure taps and the immersion thermowells did not meet design specifications. Slurry Preheater A was used during the first 12 days of February while weld repairs and modifications to Slurry Preheater B were completed. Two attempts to complete a material balance run on Powhatan No. 6 Mine coal were attempted but neither was successful. Slurry Preheater B was in service the remainder of the quarter. The start of a series of runs at higher heat flux was delayed because of plugging in both the slurry and the hydrogen flow metering systems. Three baseline runs and three slurry runs of the high heat flux program were completed before the plant was shut down March 12 for repair of the Inert Gas Unit. Attempts to complete a fourth slurry run at high heat flux were unsuccessful because of problems with the coal feed handling and the vortex mix systems. Process Development Unit (P-99) completed three of the four runs designed to study the effect of dissolver L/D ratio. The fourth was under way at the end of the period. SRC yield correlations have been developed that include coal properties as independent variables. A preliminary ranking of coals according to their reactivity in PDU P-99 has been made. Techniques for studying coking phenomenona are now in place.

  12. Technical justifications for the tests and criteria in the waste form technical position appendix on cement stabilization

    International Nuclear Information System (INIS)

    Siskind, B.; Cowgill, M.G.

    1992-01-01

    As part of its technical assistance to the Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) developed a background document for the cement stabilization appendix, Appendix A, to Rev. 1 of the Technical Position on Waste Form (TP). Here we present an overview of this background document, which provides technical justification for the stability tests to be performed on cement-stabilized waste forms and for the criteria posed in each test, especially for those tests which have been changed from their counterparts in the May 1983 Rev. 0 TP. We address guidelines for procedures from Appendix A which are considered in less detail or not at all in the Rev. 0 of the TP, namely, qualification specimen preparation (mixing, curing, storage), statistical sampling and analysis, process control program specimen preparation and examination, and surveillance specimens. For each waste form qualification test, criterion or procedural guidelines, we consider the reason for its inclusion in Appendix A, the changes from Rev. 0 of the TP (if applicable), and a discussion of the justification or rationale for these changes

  13. Technical justifications for the tests and criteria in the waste form Technical position appendix on cement stabilization

    International Nuclear Information System (INIS)

    Siskind, B.; Cowgill, M.G.

    1992-01-01

    As part of its technical assistance to the Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) developed a background document for the cement stabilization appendix. Appendix A, to Rev. 1 of the Technical Position on Waste Form (TP). Here we present an overview of this background document, which provides technical justification for the stability tests to be performed on cement-stabilized waste forms and for the criteria posed in each test) especially for those tests which have been changed from their counterparts in the May 1983 Rev. 0 TP. We address guidelines for procedures from Appendix A which are considered in less detail or not at all in the Rev. 0 of the TP, namely, qualification specimen preparation (mixing, curing, storage), statistical sampling and analysis, process control program specimen preparation and examination, and surveillance specimens. For each waste form qualification test, criterion or procedural guideline, we consider the reason for its inclusion in Appendix A, the changes from Rev. 0 of the TP (if applicable), and a discussion of the justification or rationale for these changes. (author)

  14. The Impacts of Technical Progress on Sulfur Dioxide Kuznets Curve in China: A Spatial Panel Data Approach

    Directory of Open Access Journals (Sweden)

    Zhimin Zhou

    2017-04-01

    Full Text Available This paper aims to reveal the nexus for sulfur dioxide (SO2 emission and income, as well as the effects of technical progress on SO2 emission in China based on environment Kuznets curve (EKC hypothesis. The spatial panel technique is used in case the coefficient estimates are biased due to the negligence of spatial dependence. With the provincial panel data of China from 2004 to 2014, this is the first research that finds an inverse N-trajectory of the relationship between SO2 emission and economic growth and confirms the beneficial impacts of technical advancement on SO2 emission abatement. The empirical results also suggest that the industrial structure change is an important driving force of the SO2 EKC. In addition, the direct and spillover effects of determinants on sulfur emission are clarified and estimated by a correct approach. Finally, we check the stability of our conclusions on the EKC shape for SO2 and technical progress effects when controlling for different variables and specifications, through which we find the turning points are sensitive to variables selections.

  15. Savannah River Ecology Laboratory, Annual Technical Progress Report of Ecological Research, June 30, 2002

    Energy Technology Data Exchange (ETDEWEB)

    Paul M. Bertsch, (Director)

    2002-06-30

    The Savannah River Ecology Laboratory (SREL) is a research unit of The University of Georgia (UGA) and has been conducting ecological research on the Savannah River Site (SRS) near Aiken, South Carolina for 50 years. The overall mission of the Laboratory is to acquire and communicate knowledge of ecological processes and principles. SREL conducts fundamental and applied ecological research, as well as education and outreach programs, under a Cooperative Agreement with the U.S. Department of Energy (DOE). The Laboratory's research mission during the 2002 fiscal year was fulfilled with the publication of 76 journal articles and book chapters by faculty, technical staff, students, and visiting scientists. An additional 50 journal articles have been submitted or are in press. Other noteworthy events took place as faculty members, staff, and graduate students received awards. These are described in the section titled Special Accomplishments of Faculty, Staff, Students, and Administration on page 51. Notable scientific accomplishments include work conducted on contaminant transport, stable isotopes, sandhills ecology, and phytoremediation: (1) A collaborative study between Dr. Tom Hinton at SREL and scientists at SRTC demonstrated the feasibility of using illite clay to sequester 137Cs in sediments along the P and R reactor cooling canal system, where approximately 3,000 acres of land are contaminated. Overall, the study showed significant decreases in cesium concentrations and bioavailability following the addition of illite with no sign of harm to the ecosystem. While the cesium remains sequestered from the biosphere, its radioactivity decays and the process progresses from contaminant immobilization to remediation. (2) SREL's stable isotope laboratory is now fully functional. Stable isotope distributions in nature can provide important insights into many historical and current environmental processes. Dr. Christopher Romanek is leading SREL's research

  16. High-Efficiency Nitride-Based Solid-State Lighting. Final Technical Progress Report

    International Nuclear Information System (INIS)

    Paul T. Fini; Shuji Nakamura

    2005-01-01

    In this final technical progress report we summarize research accomplished during Department of Energy contract DE-FC26-01NT41203, entitled ''High-Efficiency Nitride-Based Solid-State Lighting''. Two teams, from the University of California at Santa Barbara (Principle Investigator: Dr. Shuji Nakamura) and the Lighting Research Center at Rensselaer Polytechnic Institute (led by Dr. N. Narendran), pursued the goals of this contract from thin film growth, characterization, and packaging/luminaire design standpoints. The UCSB team initially pursued the development of blue gallium nitride (GaN)-based vertical-cavity surface-emitting lasers, as well as ultraviolet GaN-based light emitting diodes (LEDs). In Year 2, the emphasis shifted to resonant-cavity light emitting diodes, also known as micro-cavity LEDs when extremely thin device cavities are fabricated. These devices have very directional emission and higher light extraction efficiency than conventional LEDs. Via the optimization of thin-film growth and refinement of device processing, we decreased the total cavity thickness to less than 1 (micro)m, such that micro-cavity effects were clearly observed and a light extraction efficiency of over 10% was reached. We also began the development of photonic crystals for increased light extraction, in particular for so-called ''guided modes'' which would otherwise propagate laterally in the device and be re-absorbed. Finally, we pursued the growth of smooth, high-quality nonpolar a-plane and m-plane GaN films, as well as blue light emitting diodes on these novel films. Initial nonpolar LEDs showed the expected behavior of negligible peak wavelength shift with increasing drive current. M-plane LEDs in particular show promise, as unpackaged devices had unsaturated optical output power of ∼ 3 mW at 200 mA drive current. The LRC's tasks were aimed at developing the subcomponents necessary for packaging UCSB's light emitting diodes, and packaging them to produce a white light

  17. Savannah River Ecology Laboratory, Annual Technical Progress Report of Ecological Research, June 30, 2002

    International Nuclear Information System (INIS)

    Paul M. Bertsch,

    2002-01-01

    The Savannah River Ecology Laboratory (SREL) is a research unit of The University of Georgia (UGA) and has been conducting ecological research on the Savannah River Site (SRS) near Aiken, South Carolina for 50 years. The overall mission of the Laboratory is to acquire and communicate knowledge of ecological processes and principles. SREL conducts fundamental and applied ecological research, as well as education and outreach programs, under a Cooperative Agreement with the U.S. Department of Energy (DOE). The Laboratory's research mission during the 2002 fiscal year was fulfilled with the publication of 76 journal articles and book chapters by faculty, technical staff, students, and visiting scientists. An additional 50 journal articles have been submitted or are in press. Other noteworthy events took place as faculty members, staff, and graduate students received awards. These are described in the section titled Special Accomplishments of Faculty, Staff, Students, and Administration on page 51. Notable scientific accomplishments include work conducted on contaminant transport, stable isotopes, sandhills ecology, and phytoremediation: (1) A collaborative study between Dr. Tom Hinton at SREL and scientists at SRTC demonstrated the feasibility of using illite clay to sequester 137Cs in sediments along the P and R reactor cooling canal system, where approximately 3, 000 acres of land are contaminated. Overall, the study showed significant decreases in cesium concentrations and bioavailability following the addition of illite with no sign of harm to the ecosystem. While the cesium remains sequestered from the biosphere, its radioactivity decays and the process progresses from contaminant immobilization to remediation. (2) SREL's stable isotope laboratory is now fully functional. Stable isotope distributions in nature can provide important insights into many historical and current environmental processes. Dr. Christopher Romanek is leading SREL's research in this area

  18. Technical management on commissioning test of nuclear heating reactor

    International Nuclear Information System (INIS)

    Zhang Yajun; Su Qingshan

    1999-01-01

    The commissioning is the last construction stage of a nuclear heating project. The commissioning quality will directly affect on the safe operation and availability of the heating reactor. The author presents the whole test process until the completion of the test report from the point of test documents, including the preparation and execution of the test, the management of the various unexpected events during the test. And it will be emphatically discussed that the managing procedures of the various unexpected events during the test, including temporary control change, setpoint change, unexpected events and design change

  19. Theoretical particle physics. Technical progress report, May 1, 1985-April 30, 1986

    International Nuclear Information System (INIS)

    Gottlieb, S.A.; Hendry, A.W.; Kostelecky, V.A.; Lichtenberg, D.B.

    1986-05-01

    Research activities during this past year included theoretical work in lattice gauge theory, EMC effect, supersymmetry and supergravity, weak interactions including CP violation, and superstrings. Progress in all these areas is reported

  20. Symbol manipulation by computer applied to plasma physics. Technical progress report 2

    International Nuclear Information System (INIS)

    Rosen, B.

    1977-09-01

    Progress has been made in automating the calculation of parametric processes analytically by computer. The computations are performed automatically to lowest order quickly and efficiently. Work has started on a method for solving the nonlinear differential equations describing interacting modes

  1. University of Florida, University research program in robotics. Annual technical progress report

    International Nuclear Information System (INIS)

    Crane, C.D. III; Tulenko, J.S.

    1994-05-01

    Progress is reported in the areas of environmental hardening, database, world modeling, vision, man-machine interface, advanced liquid metal reactor inspection robot, and articulated transporter/manipulator system (ATMS) development

  2. Amarillo National Resource Center for Plutonium. Quarterly technical progress report, May 1, 1997--July 31, 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    Progress summaries are provided from the Amarillo National Center for Plutonium. Programs include the plutonium information resource center, environment, public health, and safety, education and training, nuclear and other material studies.

  3. Research in elementary particle physics. Technical progress report, June 1, 1983-May 31, 1984

    International Nuclear Information System (INIS)

    Kirsch, L.E.; Schnitzer, H.J.; Bensinger, J.R.; Abbott, L.F.

    1984-01-01

    Under this contract, research has been performed on both the theoretical and experimental properties of elementary particles. A brief description of the work which is either in progress or has been completed is given. Publications are listed

  4. University of Florida, University research program in robotics. Annual technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    Crane, C.D. III; Tulenko, J.S.

    1994-05-01

    Progress is reported in the areas of environmental hardening, database, world modeling, vision, man-machine interface, advanced liquid metal reactor inspection robot, and articulated transporter/manipulator system (ATMS) development.

  5. Atmospheric Effects of Nuclear Energy Centers (AENEC) Program. Annual technical progress report, July 1975--September 1976

    International Nuclear Information System (INIS)

    Patrinos, A.A.; Hoffman, H.W.

    1977-04-01

    The Technical Memorandum contains information of a preliminary nature from the six participants of the Program describing their activities and presenting the results obtained during the reporting period. The birth of the Program, its definition and evolution are described, and a complete breakdown of responsibilities and tasks assigned to the six AENEC participants is presented

  6. The Michigan high-level radioactive waste program: Final technical progress report

    International Nuclear Information System (INIS)

    1987-01-01

    This report comprises the state of Michigan's final technical report on the location of a proposed high-level radioactive waste disposal site. Included are a list of Michigan's efforts to review the DOE proposal and a detailed report on the application of geographic information systems analysis techniques to the review process

  7. Developing Technical Writing Skills in the Physical Chemistry Laboratory: A Progressive Approach Employing Peer Review

    Science.gov (United States)

    Gragson, Derek E.; Hagen, John P.

    2010-01-01

    Writing formal "journal-style" lab reports is often one of the requirements chemistry and biochemistry students encounter in the physical chemistry laboratory. Helping students improve their technical writing skills is the primary reason this type of writing is a requirement in the physical chemistry laboratory. Developing these skills is an…

  8. I-NERI QUARTERLY TECHNICAL PROGRESS REPORT - JANUARY 1 - MARCH 31, 2005

    International Nuclear Information System (INIS)

    Chang Oh

    2005-01-01

    codes. The three categories of experiments were performed in the facility; (1) upper pool cooling trip test, (2) LOFC experiment, (3) emissivity measurement experiment. (C) Prof. NO continued Task 3. (Prof NO) The experimental work of air ingress is going on without any concern: Geometry and size effect test has been completed. The conversion factor for internal surface area was obtained through this experiment. Burn-off test was performed and the uniformity of internal reaction was confirmed. (D) INEEL engineers continued to extend the diffusion model for multiple chemical species and made some calculations. (E) Prof. Lee and Martin at University of Michigan continued to analyze the effect of the stochastic fuel on the neutronic analysis and have initiated fuel depletion calculations for the VHTGR core. Progress during the past quarter includes: Further analysis of stochastic fuel geometry; Preliminary Monte Carlo depletion of full-core VHTGR; and Installation of MCNP5 on Unix cluster

  9. Uncertainty Analysis of Resistance Tests in Ata Nutku Ship Model Testing Laboratory of Istanbul Technical University

    Directory of Open Access Journals (Sweden)

    Cihad DELEN

    2015-12-01

    Full Text Available In this study, some systematical resistance tests, where were performed in Ata Nutku Ship Model Testing Laboratory of Istanbul Technical University (ITU, have been included in order to determine the uncertainties. Experiments which are conducted in the framework of mathematical and physical rules for the solution of engineering problems, measurements, calculations include uncertainty. To question the reliability of the obtained values, the existing uncertainties should be expressed as quantities. The uncertainty of a measurement system is not known if the results do not carry a universal value. On the other hand, resistance is one of the most important parameters that should be considered in the process of ship design. Ship resistance during the design phase of a ship cannot be determined precisely and reliably due to the uncertainty resources in determining the resistance value that are taken into account. This case may cause negative effects to provide the required specifications in the latter design steps. The uncertainty arising from the resistance test has been estimated and compared for a displacement type ship and high speed marine vehicles according to ITTC 2002 and ITTC 2014 regulations which are related to the uncertainty analysis methods. Also, the advantages and disadvantages of both ITTC uncertainty analysis methods have been discussed.

  10. Incremental Validity of New Computerized Aptitude Tests for Predicting Training Performance in Nine Navy Technical Schools

    National Research Council Canada - National Science Library

    Wolfe, John H; Larson, Gerald E; Alderton, David L

    2006-01-01

    During their second week of basic training, 4,989 Navy recruits assigned to one of nine technical training schools were administered a battery of six experimental computerized aptitude tests measuring four constructs...

  11. Integrated corridor management initiative : demonstration phase evaluation - Dallas technical capability analysis test plan.

    Science.gov (United States)

    This report presents the test plan for conducting the Technical Capability Analysis for the United States : Department of Transportation (U.S. DOT) evaluation of the Dallas U.S. 75 Integrated Corridor : Management (ICM) Initiative Demonstration. The ...

  12. Integrated corridor management initiative : demonstration phase evaluation, San Diego technical capability analysis test plan.

    Science.gov (United States)

    2012-08-01

    This report presents the test plan for conducting the Technical Capability Analysis for the United States Department of Transportation (U.S. DOT) evaluation of the San Diego Integrated Corridor Management (ICM) Initiative Demonstration. The ICM proje...

  13. Joint ACE ground penetrating radar antenna test facility at the Technical University of Denmark

    DEFF Research Database (Denmark)

    Lenler-Eriksen, Hans-Rudolph; Meincke, Peter; Sarri, A.

    2005-01-01

    A ground penetrating radar (GPR) antenna test facility, established within the ACE network at the Technical University of Denmark (DTU), is described. Examples of results from the facility obtained from measurements of eight different GPR antennas are presented.......A ground penetrating radar (GPR) antenna test facility, established within the ACE network at the Technical University of Denmark (DTU), is described. Examples of results from the facility obtained from measurements of eight different GPR antennas are presented....

  14. Independent technical review of the Bin and Alcove test programs at the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1993-12-01

    This Independent Technical Review (ITR) assessed the need for and technical validity of the proposed Bin and Alcove test programs using TRU-waste at the WIPP site. The ITR Team recommends that the planned Bin and Alcove tests be abandoned, and that new activities be initiated in support of the WIPP regulatory compliance processes. Recommendations in this report offer an alternate path for expeditiously attaining disposal certification and permitting

  15. A systematic assessment of the state of hazardous waste clean-up technologies. Quarterly technical progress report, April 1--June 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Berg, M.T.; Reed, B.E.; Gabr, M.

    1993-07-01

    West Virginia University (WVU) and the US DOE Morgantown Energy Technology Center (METC) entered into a Cooperative Agreement on August 29, 1992 entitled ``Decontamination Systems Information and Research Programs.`` Stipulated within the Agreement is the requirement that WVU submit to METC a series of Technical Progress Report for Year 1 of the Agreement. This report reflects the progress and/or efforts performed on the following nine technical projects encompassed by the Year 1 Agreement for the period of April 1 through June 30, 1993: Systematic assessment of the state of hazardous waste clean-up technologies; site remediation technologies -- drain-enhanced soil flushing (DESF) for organic contaminants removal; site remediation technologies -- in situ bioremediation of organic contaminants; excavation systems for hazardous waste sites; chemical destruction of polychlorinated biphenyls; development of organic sensors -- monolayer and multilayer self-assembled films for chemical sensors; Winfield lock and dam remediation; Assessments of Technologies for hazardous waste site remediation -- non-treatment technologies and pilot scale test facility implementation; and remediation of hazardous sites with stream reforming.

  16. Corrosion performance tests for reinforcing steel in concrete : technical report.

    Science.gov (United States)

    2009-10-01

    The existing test method used to assess the corrosion performance of reinforcing steel embedded in : concrete, mainly ASTM G 109, is labor intensive, time consuming, slow to provide comparative results, : and can be expensive. However, with corrosion...

  17. Association Euratom - Risø National Laboratory, Technical University of Denmark - Annual Progress Report 2007

    DEFF Research Database (Denmark)

    Michelsen, Poul; Korsholm, Søren Bang; Juul Rasmussen, Jens

    The programme of the Research Unit of the Fusion Association Euratom - Risø National Laboratory, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the pla......The programme of the Research Unit of the Fusion Association Euratom - Risø National Laboratory, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction...... phased out during 2007. Minor activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2007....

  18. Optically pumped polarized 23Na vapor target for use in polarized ion source. Technical progress report

    International Nuclear Information System (INIS)

    Anderson, L.W.

    1984-01-01

    We are currently measuring relaxation times in an optically pumped 23 Na vapor target. Our research is directed toward improvements in the optically pumped Na vapor targets used for the production of polarized H - ions. In this progress report we review the properties of the optically pumped polarized H - ion source and especially the optically pumped Na vapor target employed in this source as well as discussing the progress of our research on relaxation times in an optically pumped Na vapor target. 30 references, 6 figures, 3 tables

  19. Experimental Program Final Technical Progress Report: 15 February 2007 to 30 September 2012

    Energy Technology Data Exchange (ETDEWEB)

    Kinney, Edward R. [University of Colorado, Boulder, CO

    2014-09-12

    This is the final technical report of the grant DE-FG02-04ER41301 to the University of Colorado at Boulder entitled "Intermediate Energy Nuclear Physics" and describes the results of our funded activities during the period 15 February 2007 to 30 September 2012. These activities were primarily carried out at Fermilab, RHIC, and the German lab DESY. Significant advances in these experiments were carried out by members of the Colorado group and are described in detail.

  20. Association Euratom - DTU, Technical University of Denmark, Department of Physics - Annual Progress Report 2011

    DEFF Research Database (Denmark)

    The programme of the Research Unit of the Fusion Association Euratom – DTU, Technical University of Denmark (until 31-12- 2011: Association Euratom – Risø DTU) covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport...... temperature superconductors. Other activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2011....

  1. Technical committee on transport package test standards, Tokyo, Japan, 28 September - 2 October 1981

    International Nuclear Information System (INIS)

    Ek, P.

    The Technical Committee looked into the following tasks: a) the additional 200 m water immersion test for packages designed for irradiated fuel when the activity exceeds 10 6 Ci; b) the proposed addition of a crush test for light weight Type B and fissile materials packages; c) the proposed new text for thermal test

  2. Technical bases for establishing a salt test facility

    International Nuclear Information System (INIS)

    1985-05-01

    The need for a testing facility in which radioactive materials may be used in an underground salt environment is explored. No such facility is currently available in salt deposits in the United States. A salt test facility (STF) would demonstrate the feasibility of safely storing radioactive waste in salt and would provide data needed to support the design, construction, licensing, and operation of a radioactive waste repository in salt. Nineteen issues that could affect long-term isolation of waste materials in a salt repository are identified from the most pertinent recent literature. The issues are assigned an overall priority and a priority relative to the activities of the STF. Individual tests recommended for performance in the STF to resolve the 19 issues are described and organized under three groups: waste package performance, repository design and operation, and site characterization and evaluation. The requirements for a salt test facility are given in the form of functional criteria, and the approach that will be used in the design, execution, interpretation, and reporting of tests is discussed

  3. Index to Nuclear Safety: a technical progress review by chrology, permuted title, and author, Volume 11(1) through Volume 20(6)

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W B; Passiakos, M

    1980-06-01

    This index to Nuclear Safety, a bimonthly technical progress review, covers articles published in Nuclear Safety, Volume II, No. 1 (January-February 1970), through Volume 20, No. 6 (November-December 1979). It is divided into three sections: a chronological list of articles (including abstracts) followed by a permuted-title (KWIC) index and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center (NSIC), covers all safety aspects of nuclear power reactors and associated facilities. Over 600 technical articles published in Nuclear Safety in the last ten years are listed in this index.

  4. Accelerator research studies. Technical progress report, July 1, 1985-June 30, 1986

    International Nuclear Information System (INIS)

    1986-01-01

    Progress is reported in these areas: study of instabilities and emittance growth in periodic focusing systems for intense beams; study of collective ion acceleration by intense electron beams and pulse powered plasma focus; and study of microwave sources and parameter scaling for high-frequency linacs

  5. Accelerator research studies: Technical progress report, June 1, 1988--May 31, 1989

    International Nuclear Information System (INIS)

    1989-01-01

    This report discusses research progress in the following general topics: Study of transport and longitudinal compression of intense, high-brightness beams; study of collective ion acceleration by intense electron beams and pulse powered plasma focus; and study of microwave sources and parameter scaling for high-frequency electron-positron supercollider linacs

  6. High beta and second stability region transport and stability analysis: Technical progress report

    International Nuclear Information System (INIS)

    Hughes, M.H.; Phillips, M.W.

    1995-03-01

    This report summarizes MHD equilibrium and stability studies carried out at Northrop Grumman's Advanced Technology and Development Center during the 12 month period starting March 1, 1994. Progress is reported in both ideal and resistive MHD modeling of TFTR plasmas. The development of codes to calculate the significant effects of highly anisotropic pressure distributions is discussed along with results from this model

  7. Chemistry of gaseous lower-valent actinide halides. Technical progress report

    International Nuclear Information System (INIS)

    Hildenbrand, D.L.

    1984-01-01

    Objective is to provide thermochemical data for key actinide halide and oxyhalide systems. Progress is reported on bond dissociation energies of gaseous ThCl 4 , ThCl 3 , ThCl 2 , and ThCl; bond dissociation energies of ruthenium fluorides; and mass spectroscopy of UF 6

  8. Savannah River Ecology Laboratory annual technical progress report of ecological research, period ending July 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Vaitkus, M.R.; Wein, G.R. [eds.; Johnson, G.

    1993-11-01

    This progress report gives an overview of research programs at the Savannah River Site. Topics include; environmental operations support, wood stork foraging and breeding, defense waste processing, environmental stresses, alterations in the environment due to pollutants, wetland ecology, biodiversity, pond drawdown studies, and environmental toxicology.

  9. High beta and second stability region transport and stability analysis. Technical progress report

    International Nuclear Information System (INIS)

    Hughes, M.H.; Phillips, M.W.

    1994-09-01

    This report summarizes MHD equilibrium and stability studies carried out at Grumman's Corporate Research Center during the 6 month period starting March 1, 1994. Progress is reported in both ideal and resistive MHD modeling of TFTR plasmas. The development of codes to calculate the significant effects of highly anisotropic pressure distributions is discussed along with initial results from this model

  10. The Development of K-8 Progress Monitoring Measures in Mathematics for Use with the 2% and General Education Populations: Grade 1. Technical Report # 0919

    Science.gov (United States)

    Alonzo, Julie; Tindal, Gerald

    2009-01-01

    In this technical report, we describe the development and piloting of a series of mathematics progress monitoring measures intended for use with students in grade 1. These measures, available as part of easyCBM [TM], an online progress monitoring assessment system, were developed in 2008 and administered to approximately 2800 students from schools…

  11. The Development of K-8 Progress Monitoring Measures in Mathematics for Use with the 2% and General Education Populations: Kindergarten. Technical Report # 0921

    Science.gov (United States)

    Alonzo, Julie; Tindal, Gerald

    2009-01-01

    In this technical report, we describe the development and piloting of a series of mathematics progress monitoring measures intended for use with students in kindergarten. These measures, available as part of easyCBM[TM], an online progress monitoring assessment system, were developed in 2008 and administered to approximately 2800 students from…

  12. The Development of K-8 Progress Monitoring Measures in Mathematics for Use with the 2% and General Education Populations: Grade 3. Technical Report # 09-02

    Science.gov (United States)

    Alonzo, Julie; Lai, Cheng Fei; Tindal, Gerald

    2009-01-01

    In this technical report, we describe the development and piloting of a series of mathematics progress monitoring measures intended for use with students in grades kindergarten through eighth grade. These measures, available as part of easyCBM[TM], an online progress monitoring assessment system, were developed in 2007 and 2008 and administered to…

  13. The Development of K-8 Progress Monitoring Measures in Mathematics for Use with the 2% and General Education Populations: Grade 5. Technical Report # 09-01

    Science.gov (United States)

    Lai, Cheng Fei; Alonzo, Julie; Tindal, Gerald

    2009-01-01

    In this technical report, we describe the development and piloting of a series of mathematics progress monitoring measures intended for use with students in grades kindergarten through eighth grade. These measures, available as part of easyCBM[TM], an online progress monitoring assessment system, were developed in 2007 and 2008 and administered to…

  14. The Development of K-8 Progress Monitoring Measures in Mathematics for Use with the 2% and General Education Populations: Grade 2. Technical Report # 0920

    Science.gov (United States)

    Alonzo, Julie; Lai, Cheng Fei; Tindal, Gerald

    2009-01-01

    In this technical report, we describe the development and piloting of a series of mathematics progress monitoring measures intended for use with students in grades kindergarten through eighth grade. These measures, available as part of easyCBM[TM], an online progress monitoring assessment system, were developed in 2007 and 2008 and administered to…

  15. The Development of K-8 Progress Monitoring Measures in Mathematics for Use with the 2% and General Education Populations: Grade 7. Technical Report 0908

    Science.gov (United States)

    Lai, Cheng Fei; Alonzo, Julie; Tindal, Gerald

    2009-01-01

    In this technical report, we describe the development and piloting of a series of mathematics progress monitoring measures intended for use with students in grades kindergarten through eighth grade. These measures, available as part of easyCBM[TM], an online progress monitoring assessment system, were developed in 2007 and 2008 and administered to…

  16. The Development of K-8 Progress Monitoring Measures in Mathematics for Use with the 2% and General Education Populations: Grade 4. Technical Report # 09-03

    Science.gov (United States)

    Alonzo, Julie; Lai, Cheng Fei; Tindal, Gerald

    2009-01-01

    In this technical report, we describe the development and piloting of a series of mathematics progress monitoring measures intended for use with students in grades kindergarten through eighth grade. These measures, available as part of easyCBM[TM], an online progress monitoring assessment system, were developed in 2007 and 2008 and administered to…

  17. The Development of K-8 Progress Monitoring Measures in Mathematics for Use with the 2% and General Education Populations: Grade 8. Technical Report # 09-04

    Science.gov (United States)

    Lai, Cheng Fei; Alonzo, Julie; Tindal, Gerald

    2009-01-01

    In this technical report, we describe the development and piloting of a series of mathematics progress monitoring measures intended for use with students in grades kindergarten through eighth grade. These measures, available as part of easyCBM[TM], an online progress monitoring assessment system, were developed in 2007 and 2008 and administered to…

  18. The KEEP Phone Discrimination Test. Technical Report No. 64.

    Science.gov (United States)

    Smith, Kenneth; And Others

    The urban, ethnically Hawaiian child typically experiences great difficulty in learning to read English. In order to determine whether phonological confusion is a source of dialectical interference, the Kamehameha Early Education Program (KEEP) Phone Discrimination Test (KPDT) was developed for the one hundred twelve students in the KEEP school…

  19. Technical and management considerations in conducting type B shipping container tests

    International Nuclear Information System (INIS)

    Whitney, M.A.; Leader, D.R.; Phipps, D.P.

    1994-01-01

    The Code of Federal Regulations (CFR) mandate that type B shipping containers are capable of surviving specific drop tests. One approach for demonstrating compliance to the CFRs is to drop test a shipping container. This paper will discuss the technical and management considerations in conducting such drop tests on the 9975 family of shipping containers. For both technical and management considerations this paper will comment on loading the shipping container, dropping the shopping container, and examination of the shipping container after the drop tests

  20. Association Euratom - DTU, Technical University of Denmark, Department of Physics - Annual Progress Report 2012

    DEFF Research Database (Denmark)

    The programme of the Research Unit of the Fusion Association Euratom – DTU, Technical University of Denmark covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium...... and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. Within fusion technology there are activities on fusion materials research (Tungsten and ODSFS). Other activities are system analysis...

  1. Association Euratom - DTU, Technical University of Denmark, Department of Physics - Annual Progress Report 2013

    DEFF Research Database (Denmark)

    The programme of the Research Unit of the Fusion Association Euratom – DTU, Technical University of Denmark covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium...... and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. Within fusion technology there are activities on fusion materials research (Tungsten and ODSFS). Other activities are system analysis...

  2. [Review of draft Crystalline Repository Project reports]: Technical progress report, CY 1985-1986

    International Nuclear Information System (INIS)

    1986-01-01

    During the period (CY 1985-86) of this report, the Wisconsin Radioactive Waste Review Board provided technical services under the contract with DOE. These included Participation in the development of variables and screening techniques that would be used in identifying those rock bodies in the Area Recommendation Report (ARR); reviewing and commenting on the report and developing a procedure in which local residents could have input into the process; sought resumption of negotiations with DOE on a full Consultation and Cooperation (CandC) agreement; and Participating in workshops and provided comments on two major DOE transportation documents, ''Transportation Business Plan: Strategy Options Document,'' and ''Transportation Institutional Plan.''

  3. Aerospace Technology: Technical Data and Information on Foreign Test Facilities

    Science.gov (United States)

    1990-06-22

    referred to in English as the German Aerospace Research Establishment. Foreign acronyms and names with their translations are included in the list of...Unique Characteristics: None Applications/Current Programs: In 1963, the first in a long series of nozzle tests were conducted for SNECMA’s ATAR 9C and...HP compressor RB- 199, IP compressor RB- 199, transonic compressor (single-stage), transonic compressor (six-stage), and ATAR compressor. Turbine

  4. The clinical testing of male gonad shields. Technical report

    International Nuclear Information System (INIS)

    Church, W.W.; Burnett, B.M.

    1975-11-01

    Two types of male gonad shields, designed for use with support garments, were tested in a number of hospitals and clinics throughout the United States. The clinical evaluation consisted of: (1) measuring dose reduction with thermoluminescent dosimeters; and (2) determining acceptability of the shields for routine use in x-ray facilities, through the use of survey forms completed by patients, technologists, and facilities. The shields proved to provide a basis for a very satisfactory male gonad shield program

  5. The clinical testing of male gonad shields. Technical report

    Energy Technology Data Exchange (ETDEWEB)

    Church, W.W.; Burnett, B.M.

    1975-11-01

    Two types of male gonad shields, designed for use with support garments, were tested in a number of hospitals and clinics throughout the United States. The clinical evaluation consisted of: (1) measuring dose reduction with thermoluminescent dosimeters; and (2) determining acceptability of the shields for routine use in x-ray facilities, through the use of survey forms completed by patients, technologists, and facilities. The shields proved to provide a basis for a very satisfactory male gonad shield program. (GRA)

  6. New imaging systems in nuclear medicine. Technical progress report, July 1, 1975--March 15, 1976

    International Nuclear Information System (INIS)

    Brownell, G.L.

    1976-01-01

    This progress report covers four areas: development of positron instrumentation, development of NUMEDICS computer system and software, application of cyclotron-produced isotopes ( 11 C, 68 Ga, 13 N, 15 O, and 82 Rb), and application of the NUMEDICS computer system in nuclear medicine. The development of transverse section positron imaging has had a significant impact and a positron camera was designed specifically for transverse section imaging of heart and lungs. The computer net (NUMEDICS II) is progressing rapidly in design and software development. Clinical studies have demonstrated the feasibility of measuring cerebral blood flow using a variety of positron emitting radiopharmaceuticals and oxygen utilization using 15 O 2 . Rubidium-82 also appears to be a promising agent for measurement of cerebral blood flow

  7. Nuclear structure theory. Technical progress report, September 1, 1982-August 31, 1984

    International Nuclear Information System (INIS)

    French, J.B.; Koltun, D.S.

    1984-01-01

    Research progress is reported. Spectral Averaging studies are outlined including the theory of level densities for interacting nucleons, the properties of single-particle nuclear excitations, spectral distributions for fixed symmetries, and applications to the secular behavior of fluctuation measures in complex nuclei. Collective States research is described, in particular the boson-fermion symmetries which are related to the U(5) limit of the interacting boson model. Nuclear Reaction studies are described including the statistical theory of pion absorption, direct reactions at intermediate energies, and the properties of the off-shell πN t-matrix. Progress is reported on the quark theory of nuclear matter and the construction of models for a Fermi fluid which, near the nuclear ground state, is a fluid of nucleons composed of quarks, and, at high densities or temperatures, is a quark fluid. Applications of formal scattering theory to the study of phase-conjugate optics are discussed. Publications are listed

  8. AFR spent fuel storage program. Technical progress report, January 1981-March 1981

    International Nuclear Information System (INIS)

    1981-01-01

    Work on this project is focused on developing design and licensing information for the model facility. Deliverables were submitted to DOE for facility modification, security design, and licensing documentation. Work is essentially complete on the high-density rack design with deliverable planned for April 30, 1981. A continuing program for completion of design and licensing information development was initiated by AGNS in February 1981. Progress to date is satisfactory

  9. U.C. Davis high energy particle physics research: Technical progress report -- 1990

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-12-31

    Summaries of progress made for this period is given for each of the following areas: (1) Task A--Experiment, H1 detector at DESY; (2) Task C--Experiment, AMY detector at KEK; (3) Task D--Experiment, fixed target detectors at Fermilab; (4) Task F--Experiment, PEP detector at SLAC and pixel detector; (5) Task B--Theory, particle physics; and (6) Task E--Theory, particle physics.

  10. Nuclear structure theory. Annual technical progress report, October 1, 1979-August 31, 1980

    International Nuclear Information System (INIS)

    French, J.B.; Koltun, D.S.

    1980-01-01

    This report summarizes progress during the past year in the following areas of nuclear structure and reaction theory: statistical spectroscopy (including random matrix methods, with applications to fluctuations in spectra and in strength distributions, and to problems of ergodicity; group symmetries in spectral-distribution theory; electromagnetic and β transitions); meson scattering and absorption by nuclei (including general scattering theory with absorption, multiple scattering theory and its reactive content, statistical theory of absorption); and meson currents in electromagnetic transitions

  11. Nuclear methods in chemical kinetics. Technical progress report, April 1, 1978--March 31, 1979

    International Nuclear Information System (INIS)

    1979-01-01

    Significant progress was achieved in the following products: (1) gas phase thermal F-to-HF reactions; (II) gas phase thermal 18 F olefinic addition reactions; (III) steady state hot atom kinetic theory; (IV) moderator effects on nuclear recoil 18 F substitution reactions; and (V) new experimental methodology. New work has been initiated upon the development of a realisitic potential form of kinetic collision theory

  12. High energy particle physics at Purdue. Annual technical progress report, March 1982-March 1983

    International Nuclear Information System (INIS)

    Gaidos, J.A.; Koltick, D.S.; Loeffler, F.J.

    1983-01-01

    Progress is reported in these areas: a study of electron-positron annihilation using the High Resolution Spectrometer at SLAC; proton decay; extensive muon showers; gamma ray astronomy; the DUMAND project; theoretical work on fundamental problems in electromagnetic, weak, strong, and gravitational interactions; chi production by hadrons; p-nucleus interactions; development of the Collider Detector at Fermilab; and study of the observed hadrons as the relativistic bound states of baryons and antibaryons

  13. Deep vadose zone remediation: technical and policy challenges, opportunities, and progress in achieving cleanup endpoints

    International Nuclear Information System (INIS)

    Wellman, D.M.; Freshley, M.D.; Truex, M.J.; Lee, M.H.

    2013-01-01

    Current requirements for site remediation and closure are standards-based and are often overly conservative, costly, and in some cases, technically impractical. Use of risk-informed alternate endpoints provides a means to achieve remediation goals that are permitted by regulations and are protective of human health and the environment. Alternate endpoints enable the establishment of a path for cleanup that may include intermediate remedial milestones and transition points and/or regulatory alternatives to standards-based remediation. A framework is presented that is centered around developing and refining conceptual models in conjunction with assessing risks and potential endpoints as part of a system-based assessment that integrates site data with scientific understanding of processes that control the distribution and transport of contaminants in the subsurface and pathways to receptors. This system-based assessment and subsequent implementation of the remediation strategy with appropriate monitoring are targeted at providing a holistic approach to addressing risks to human health and the environment. This holistic approach also enables effective predictive analysis of contaminant behavior to provide defensible criteria and data for making long-term decisions. Developing and implementing an alternate endpoint-based approach for remediation and waste site closure presents a number of challenges and opportunities. Categories of these challenges include scientific and technical, regulatory, institutional, and budget and resource allocation issues. Opportunities exist for developing and implementing systems-based approaches with respect to supportive characterization, monitoring, predictive modeling, and remediation approaches. (authors)

  14. Deep vadose zone remediation: technical and policy challenges, opportunities, and progress in achieving cleanup endpoints

    Energy Technology Data Exchange (ETDEWEB)

    Wellman, D.M.; Freshley, M.D.; Truex, M.J.; Lee, M.H. [Pacific Northwest National Laboratory, Richland, Washington (United States)

    2013-07-01

    Current requirements for site remediation and closure are standards-based and are often overly conservative, costly, and in some cases, technically impractical. Use of risk-informed alternate endpoints provides a means to achieve remediation goals that are permitted by regulations and are protective of human health and the environment. Alternate endpoints enable the establishment of a path for cleanup that may include intermediate remedial milestones and transition points and/or regulatory alternatives to standards-based remediation. A framework is presented that is centered around developing and refining conceptual models in conjunction with assessing risks and potential endpoints as part of a system-based assessment that integrates site data with scientific understanding of processes that control the distribution and transport of contaminants in the subsurface and pathways to receptors. This system-based assessment and subsequent implementation of the remediation strategy with appropriate monitoring are targeted at providing a holistic approach to addressing risks to human health and the environment. This holistic approach also enables effective predictive analysis of contaminant behavior to provide defensible criteria and data for making long-term decisions. Developing and implementing an alternate endpoint-based approach for remediation and waste site closure presents a number of challenges and opportunities. Categories of these challenges include scientific and technical, regulatory, institutional, and budget and resource allocation issues. Opportunities exist for developing and implementing systems-based approaches with respect to supportive characterization, monitoring, predictive modeling, and remediation approaches. (authors)

  15. Technical concept for rock mechanics tests, Climax Granite, NTS

    International Nuclear Information System (INIS)

    Hearst, J.R.

    1979-02-01

    If we are to believe our predictions of the thermomechanical behavior of the material surrounding a nuclear waste repository in granite, we must test the computational methods used in making the predictions. If thermal loadings appropriate to a real repository are used, thermally induced displacements and strains are quite small, and available geotechnical instrumentation is only marginally able to measure these effects to the accuracy desired to make thorough tests of the predictions. We outline a three-step program to address these issues. (1) Conduct experiments in which the thermal loading is large compared to that induced by a real repository. This will permit us to make accurate measurements with available instrumentation. (2) Simultaneously, develop improved instrumentation that will enable us to make accurate measurements of motions induced by thermal loadings appropriate to a real repository. (3) Finally, conduct a second set of experiments, with the improved instrumentation and thermal loading similar to that of a real repository in granite. If we can predict the effects of this thermal loading to a few percent over distances of tens of meters for time periods of a few years, and demonstrate that these predictions are correct, we can have reasonable confidence that, using the same methods, we can predict the behavior over thousands of meters for hundreds of years to an order of magnitude. That accuracy should be satisfactory for those distances and times

  16. Phase 1 space fission propulsion system testing and development progress

    International Nuclear Information System (INIS)

    Van Dyke, Melissa; Houts, Mike; Godfroy, Tom; Dickens, Ricky; Poston, David; Kapernick, Rick; Reid, Bob; Salvail, Pat; Ring, Peter

    2002-01-01

    Successful development of space fission systems requires an extensive program of affordable and realistic testing. In addition to tests related to design/development of the fission system, realistic testing of the actual flight unit must also be performed. If the system is designed to operate within established radiation damage and fuel burn up limits while simultaneously being designed to allow close simulation of heat from fission using resistance heaters, high confidence in fission system performance and lifetime can be attained through a series of non-nuclear tests. The Safe Affordable Fission Engine (SAFE) test series, whose ultimate goal is the demonstration of a 300 kW flight configuration system, has demonstrated that realistic testing can be performed using non-nuclear methods. This test series, carried out in collaboration with other NASA centers, other government agencies, industry, and universities, successfully completed a testing program with a 30 kWt core. Stirling engine, and ion engine configuration. Additionally, a 100 kWt core is in fabrication and appropriate test facilities are being reconfigured. This paper describes the current SAFE non-nuclear tests, which includes test article descriptions, test results and conclusions, and future test plans

  17. Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark. Annual progress report 2010

    Energy Technology Data Exchange (ETDEWEB)

    Korsholm, S.B.; Michelsen, P.K.; Rasmussen, J.J.; Westergaard, C.M. (eds.)

    2011-04-15

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. Within fusion technology there are activities related to development of high temperature superconductors. Other activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2010. (Author)

  18. Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark. Annual progress report 2009

    International Nuclear Information System (INIS)

    Korsholm, S.B.; Michelsen, P.K.; Rasmussen, J.J.; Westergaard, C.M.

    2010-04-01

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. Within fusion technology there are activities related to development of high temperature superconductors. Minor activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2009. (Author)

  19. Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark. Annual progress report 2009

    Energy Technology Data Exchange (ETDEWEB)

    Korsholm, S B; Michelsen, P K; Rasmussen, J J; Westergaard, C M [eds.

    2010-04-15

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. Within fusion technology there are activities related to development of high temperature superconductors. Minor activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2009. (Author)

  20. Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark. Annual progress report 2008

    Energy Technology Data Exchange (ETDEWEB)

    Korsholm, S.B.; Michelsen, P.K.; Rasmussen, J.J.; Westergaard, C.M. (eds.)

    2009-04-15

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. New activities in technology related to development of high temperature superconductors have been initiated in 2008. Minor activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2008. (Author)

  1. Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark. Annual progress report 2008

    International Nuclear Information System (INIS)

    Korsholm, S.B.; Michelsen, P.K.; Rasmussen, J.J.; Westergaard, C.M.

    2009-04-01

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. New activities in technology related to development of high temperature superconductors have been initiated in 2008. Minor activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2008. (Author)

  2. Progress report [of] Technical Physics and Prototype Engineering Division, April 1982 - March 1984

    International Nuclear Information System (INIS)

    Ramamurthi, S.S.; Chaudhry, Ramesh

    1985-01-01

    The work done by the Technical Physics and Prototype Engineering Division of the Bhabha Atomic Research Centre (BARC) at Bombay during the period from April 1982 to March 1984 is described in the form of summaries. The main thrust of the work of the Division is towards designing, developing, fabricating and if needed, producing on a large scale various instruments, equipment and components required for the programmes of the BARC and the Department of Atomic Energy. The summaries describing the work are grouped under the headings:(1) vacuum, (2) surface analysis, (3) mass spectrometry, (4) electronics, (5) cryogenics, (6) crystals and detectors, (7) glass technology and devices, and (8) optoelectronics. A list of publications of the staff-members of the Division during the report period is given. (M.G.B.)

  3. Association Euratom - Risoe National Laboratory, Technical Univ. of Denmark. Annual progress report 2007

    International Nuclear Information System (INIS)

    Michelsen, P.K.; Korsholm, S.B.; Rasmussen, J.J.

    2008-04-01

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. The activities in technology on investigations of radiation damage of fusion reactor materials have been phased out during 2007. Minor activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2007. (Author)

  4. Association Euratom - Risoe National Laboratory, Technical Univ. of Denmark. Annual progress report 2007

    Energy Technology Data Exchange (ETDEWEB)

    Michelsen, P.K.; Korsholm, S.B.; Rasmussen, J.J. (eds.)

    2008-04-15

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. The activities in technology on investigations of radiation damage of fusion reactor materials have been phased out during 2007. Minor activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2007. (Author)

  5. Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark. Annual progress report 2010

    International Nuclear Information System (INIS)

    Korsholm, S.B.; Michelsen, P.K.; Rasmussen, J.J.; Westergaard, C.M.

    2011-04-01

    The programme of the Research Unit of the Fusion Association Euratom - Risoe National Laboratory for Sustainable Energy, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its interaction with the plasma equilibrium and particles. The effort includes both first principles based modelling, and experimental observations of turbulence and of fast ion dynamics by collective Thomson scattering. Within fusion technology there are activities related to development of high temperature superconductors. Other activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2010. (Author)

  6. Fusion programs in applied plasma physics. Technical progress report, July 11, 1992--May 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-07-01

    This report summarizes the progress made in theoretical and experimental research funded by US Department of Energy Grant No. DE-FG03-92ER54150, during the period July 11, 1992 through May 31, 1993. Four main tasks are reported: applied plasma physics theory, alpha particle diagnostic, edge and current density diagnostic, and plasma rotation drive. The report also discusses the research plans for the theory and experimental programs for the next grant year. Reports and publications supported by the grant during this period are listed in the final section.

  7. Salt repository project: Technical progress report for the quarter 1 April--30 June 1987

    International Nuclear Information System (INIS)

    1987-01-01

    This document reports the progress being made each quarter on the development of a geologic repository in salt for the permanent disposal of high-level nuclear waste. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Nuclear Waste Isolation, a prime contractor of the US Department of Energy (DOE) Salt Repository Project Office. The studies include work by other DOE prime contractors and by contractors to the Office of Nuclear Waste Isolation

  8. Nuclear structure theory. Annual technical progress report, October 1, 1978-September 30, 1979

    International Nuclear Information System (INIS)

    French, J.B.; Koltun, D.S.

    1979-01-01

    This report summarizes progress during the past year in the following areas of nuclear structure and reaction theory: Statistical spectroscopy, including: Random matrix methods, with applications to fluctuations in spectra and in strength distributions, and to problems of ergodicity; Group symmetries in spectral-distribution theory; Electromagnetic and β transitions. Meson scattering and absorption by nuclei, including: general scattering theory with absorption, multiple scattering theory and its reactive content, statistical theory of absorption, theory of the absorption operator (πNN vertex), theory of πN scattering. A list of publications is included

  9. Combined macroscopic and microscopic approach to the fracture of metals. Technical progress report

    International Nuclear Information System (INIS)

    Asaro, R.J.; Gurland, J.; Needleman, A.; Rice, R.J.

    1979-06-01

    Progress is reported on microscopic fracture mechanisms, including studies of void and crack initiation in steels in the absence and presence of hydrogen, the effects of hydrogen on ductile fracture in medium and high carbon steels; elastic--plastic crack growth including the quasi-stable growth of cracks in ductile solids under increasing load and conditions of instability; and elevated temperature rupture including analysis of the stress field near a crack tip in an elastic-nonlinear viscous material under tensile load as well as the processes of diffusion, and cavitation of grain boundaries in plastically creeping materials

  10. Theoretical nuclear physics. Task B. Technical progress report, August 1, 1982-September 30, 1983

    International Nuclear Information System (INIS)

    1983-01-01

    Progress is reported on the following studies: (a) double delta interactions in pion double charge exchange; (b) isovector correlations in pion-nucleus scattering; (c) nuclear structure effects in pion single charge exchange; (d) a perspective on sequential transfer reactions; (e) inelastic and charge exchange scattering theory; (f) magnitude of the first order DWBA description of the two nuclear transfer reactions; (g) nonlocality effects on deuteron transfer reactions; (h) evaluation of external radial integrals in inelastic electron scattering; (i) experimental observables as a function of Dirac invariant amplitudes; (j) Dirac shell-model wavefunctions in inelastic electron scattering; and (k) impulse approximation Dirac theory of inelastic proton nucleus collective excitations. Publications are listed

  11. High energy particle physics at Purdue. Annual technical progress report, March 1983-March 1984

    International Nuclear Information System (INIS)

    Gaidos, J.A.; Koltick, D.S.; Loeffler, F.J.

    1984-01-01

    Progress is reported in these areas: a study of electron-positron annihilation using the High Resolution Spectrometer; experimental study of proton decay; gamma ray astrophysics; the DUMAND project; fundamental problems in the theory of gravitational, electromagnetic, weak, and strong interactions; chi production by hadrons; study of collective phenomena; search for the onset of collective phenonmena; work on the Collider Detector at Fermilab; search for a deconfined quark-gluon phase of strongly interacting matter at the FNAL proton-antiproton collider; and development of an electrodeless drift chamber

  12. Physics of correlated systems. Technical progress report, December 1996 - June 1999

    International Nuclear Information System (INIS)

    Greene, C.H.

    1999-01-01

    During the current funding period, which covers a period of approximately 2.5 years, the authors have tackled a number of challenging problems that involve nonperturbative particle-particle interactions in two qualitatively different areas: electron-electron interactions in photoionization and photodetachment, and atom-atom interactions in Bose-Einstein condensates. The following discusses the progress achieved in these different areas. The emphasis in this summary will concentrate on approximately the last year of research accomplishments, although the bibliography below includes all research publications that were supported during the time period of this grant

  13. Plasma physics research (Tokapole II). Technical progress report, October 1, 1981-December 31, 1983

    International Nuclear Information System (INIS)

    1983-01-01

    Progress during the 27-month period, October 1, 1981 to December 31, 1983 on Tokapole II research is described. Tokapole II is a 4-node poloidal divertor tokamak that can also be run as an octupole. Research during this period has concentrated on studies of discharges with safety factor q less than one and on the identification of the shear Alfven wave resonance. Other topics include measurements of the loop voltage reduction through ECRH startup, plasma gun refueling, fluctuations and transport, pumped limiter studies, plasma-wall interactions, diagnostic development, polarization of electron cyclotron emission, and poloidal ohmic heating

  14. Nuclear structure theory. Annual technical progress report, October 1, 1977--September 30, 1978

    International Nuclear Information System (INIS)

    French, J.B.; Koltun, D.S.

    1978-01-01

    Progress during the past year in the following areas of nuclear structure and reaction theory is summarized: statistical spectroscopy, including random matrix methods, with applications to fluctuations in spectra and in strength distributions, and to problems of erogodicity; group symmetries in spectral distribution theory; effective interactions; statistical reaction theory, applied to ''deep inelastic'' collisions of heavy ions, and to pion absorption by nuclei; meson scattering and absorption by nuclei, including general scattering theory with absorption, multiple scattering theory and its reactive content, models for absorption, theory of the absorption operator (πNN vertex), theory of πN scattering. A list of publications is included

  15. Salt Repository Project technical progress report for the quarter 1 January--31 March 1987

    International Nuclear Information System (INIS)

    1988-03-01

    This document reports the progress being made each quarter on the development of a geologic repository in salt for the permanent disposal of high-level nuclear waste. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Nuclear Waste Isolation, a prime contractor of the US Department of energy (DOE) Salt Repository Project Office. The studies include work by other DOE prime contractors and by contractors to the Office of Nuclear Waste Isolation. 23 refs., 1 fig

  16. Nuclear structure theory. Annual technical progress report, September 1, 1980-August 31, 1981

    International Nuclear Information System (INIS)

    French, J.B.; Koltun, D.S.

    1981-01-01

    This report summarizes progress during the past year in the following areas of nuclear structure and reaction theory: (1) statistical spectroscopy, including: random matrix methods, with applications to fluctuations in spectra and in strength distributions; group symmetries in spectral-distribution theory; electromagnetic and β transitions, limits to time-reversal symmetry breaking in the nucleon-nucleon interaction; (2) meson scattering and absorption by nuclei, including: general scattering theory with absorption, multiple scattering theory and its reactive content, statistical theory of absorption; and (3) meson currents in electromagnetic transitions

  17. Thermionic cogeneration burner assessment study. Third quarterly technical progress report, April-June, 1983

    Energy Technology Data Exchange (ETDEWEB)

    1983-01-01

    The specific tasks of this study are to mathematically model the thermionic cogeneration burner, experimentally confirm the projected energy flows in a thermal mock-up, make a cost estimate of the burner, including manufacturing, installation and maintenance, review industries in general and determine what groups of industries would be able to use the electrical power generated in the process, select one or more industries out of those for an in-depth study, including determination of the performance required for a thermionic cogeneration system to be competitive in that industry. Progress is reported. (WHK)

  18. ENLUB - 12 Months Technical Report WP3: Development of simulative tests

    DEFF Research Database (Denmark)

    Zhang, Wenqi

    A draw bead test has been developed at the Department of Manufacturing Engineering, The Technical University of Denmark. The purpose of the test equipment is to simulate an actual situation in industry where draw beads are applied to constrain movement of sheet material particular in stretch...

  19. Use of "t"-Test and ANOVA in Career-Technical Education Research

    Science.gov (United States)

    Rojewski, Jay W.; Lee, In Heok; Gemici, Sinan

    2012-01-01

    Use of t-tests and analysis of variance (ANOVA) procedures in published research from three scholarly journals in career and technical education (CTE) during a recent 5-year period was examined. Information on post hoc analyses, reporting of effect size, alpha adjustments to account for multiple tests, power, and examination of assumptions…

  20. Superconducting fault current limiter. Fifth quarterly technical progress report, August 8, 1978-November 7, 1979

    Energy Technology Data Exchange (ETDEWEB)

    1979-01-01

    Progress in the development of fault current limiters for superconducting power transmission systems is reported. The analysis and design of a magnetically switched resistive device and the experimental program were emphasized and reported. A transient heat transfer model was developed which indicates the parameters which are important in determining the thermal heating and recovery of the superconduting film. Designs for the switching coil and the S/C element were also carried out and are reported. A four-pole magnetic coil is recommended; this generates a magnetic field which is nearly perpendicular to spiral or helical S/C film geometrics. A spirally-designed, 3000 ohm limiter is shown to be able to fit within a .5 to 1m inner radius, .05 to .03 m wide, 1.3 to 3.9 m long annualr region. The experimental program has included work on materials development and on prepartion of the switching and thermal recovery experimental facility. The material development program has uncovered several serious short-comings of NbN as the S/C film material. Macroscopic holes and surface debris, and microscopic imperfections reduce the critical current density below the expected value and, in addition, cause nonuniform switching. Reasons for these effects are postulated, and a continuing, vigorous materials program is suggested in hopes of alleviating these problems. Virtually all of the experimental equipment had been installed, and so the magnetic switching and thermal recovery experiments can begin and progress during the next quarter. (LCL)

  1. An accelerator neutron source for BNCT. Technical progress report, 1 June 1993--31 May 1994

    International Nuclear Information System (INIS)

    Blue, T.E.; Vafai, K.

    1994-02-01

    This is the progress report for the project entitled, ''An Accelerator Neutron Source for BNCT.'' The progress report is for the period from July 1, 1993 to date. The overall objective of our research project is to develop an Accelerator Epithermal Neutron Irradiation Facility (AENIF) for Boron Neutron Capture Therapy (BNCT). The AENIF consists of a 2.5 MeV high current proton accelerator, a lithium target to produce source neutrons, and a moderator/reflector assembly to obtain from the energetic source neutrons an epithermal neutron field suitable for BNCT treatments. Our project goals are to develop the non-accelerator components of the AENIF, and to specifically include in our development: (1) design, numerical simulation, and experimental verification of a target assembly which is capable of removing 75 kW of beam power; (2) re-optimization of the moderator assembly design based on in-phantom dose assessments using neutron spectra calculated in phantom and an energy-dependent neutron Relative Biological Effectiveness (RBE); (3) construction of a prototype moderator assembly and confirmation of its design by measurements; (4) design of the shielding of the accelerator and treatment rooms for an AENIF; and (5) design of a high energy beam transport system which is compatible with the shielding design and the thermal-hydraulic design

  2. Biochemical removal of HAP precursors from coal. Quarterly technical progress report, April--June 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    Analytical methods were finalized and all analyses completed on shake flask tests with Indiana No. 5 and Pittsburgh No. 8 coal. A column leaching-rotating biological contractor (RBC) unit was used to bioleach pyrite and hazardous air pollutant precursors from Pittsburgh No. 8 coal. Shake flask tests with Rosebud subbituminous coal were begun. In connection with upcoming slurry column reactor tests, coal was prepared and shipped to INEL, and a detailed work plan was developed for operation and sampling for the tests. A manuscript and poster was prepared for presentation at the PETC contractors conference.

  3. Bi-gas pilot plant operation. Technical progress report, 1 July 1980-30 September 1980

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-01-01

    The stainless steel process gas line from the gasifier to the gas washer was replaced with chrome molybdenum steel. Test G-13 was the longest to date and was characterized by smooth start-up and operation, long Stage I thermocouple life, and collection of much material balance data. Stress corrosion cracking in several areas of the process gas line delayed start-up of Test G-14 and a large part of the quarter was spent in replacing this piping. The results of test G-13 are described in detail. Conclusions for the test and recommendation are given, especially for burner modifications, prevention of calcium carbonate deposits, etc.

  4. Silicon ribbon growth by a capillary action shaping technique. Annual report (Quarterly technical progress report No. 9)

    Energy Technology Data Exchange (ETDEWEB)

    Schwuttke, G.H.; Ciszek, T.F.; Kran, A.

    1977-10-01

    Progress on the technological and economical assessment of ribbon growth of silicon by a capillary action shaping technique is reported. Progress in scale-up of the process from 50 mm to 100 mm ribbon widths is presented, the use of vitreous carbon as a crucible material is analyzed, and preliminary tests of CVD Si/sub 3/N/sub 4/ as a potential die material are reported. Diffusion length measurements by SEM, equipment and procedure for defect display under MOS structure in silicon ribbon for lifetime interpretation, and an assessment of ribbon technology are discussed. (WHK)

  5. The role of technical progress in the process of recalculating oil reserves; Le role du progres technique dans le processus de renouvellement des reserves petrolieres

    Energy Technology Data Exchange (ETDEWEB)

    Boulard, J.N. [Total/Fina/Institut Francais du Petrole (IFP), 92 - Rueil-Malmaison (France)

    1999-08-01

    Contrary to the concept of resources (which is essentially a geological one), the notion of reserves designates the quantities that are technically and economically recoverable. Beyond the production-related effect, the reserves therefore evolve over time in accordance with numerous technical and economic parameters. Among these parameters, it can be seen that technical progress plays a considerable role throughout the process of converting resources into reserves, including progress in the identification, accessibility and processing of the resources, and improvements in economic viability. After having tackled the problem of measuring the 'technical progress effects' and citing examples, we demonstrate that the evolution in oil reserves is subject to three types of impact. These are a quantitative impact by significantly improving the recovery rates or making it possible to identify hitherto undetectable oil fields, a qualitative impact by widening the resource base thanks to the adoption of new categories of oil (in particular the so-called 'unconventional' oils) and by carrying out the gradual substitution between these resources of differing qualities. There is also a dynamic impact, through the acceleration of resource availability. Through these three approaches, technical progress makes makes it possible to ensure continuity in oil supply and contributes significantly to the recalculation of reserves. It therefore acts as a compensating factor, counterbalancing the progressive depletion of resources. (author)

  6. ITER technology R and D progress report. Report by the Director. ITER technical advisory committee meeting, 25-27 June 2000, St. Petersburg

    International Nuclear Information System (INIS)

    2001-01-01

    The overall philosophy for the ITER design has been to use established approaches through detailed analysis and to validate their application to ITER through technology R and D, including fabrication of full scale or scalable models of key components. All this R and D work has been done for ITER under collaboration among the Home Teams, with a total resource of about 660 KIUA. R and D issues for ITER-FEAT are almost the same as for the 1998 ITER design. Major developments and fabrication have been completed and tests have significantly progressed. The technical output from the R and D validates the technologies and confirms the manufacturing techniques and quality assurance incorporated in the ITER design, and supports the manufacturing cost estimates for important key cost drivers. The testing of models is continuing to demonstrate their performance margin and/or to optimize their operational use. Their realisation offers insights useful for a possible future collaborative construction activity. Valuable and relevant experience has already been gained in the management of industrial scale, cross-party ventures. The successful progress of these projects increases confidence in the possibility of jointly constructing ITER in an international project framework. The R and D present status is summarized in the following: details are given in Chapters 2 and 3. Significant efforts and resources have been devoted to the Seven Large R and D Projects which cover all the major key components of the basic machine of ITER and their maintenance tools

  7. Recent Progress toward Microfluidic Quality Control Testing of Radiopharmaceuticals

    Directory of Open Access Journals (Sweden)

    Noel S. Ha

    2017-11-01

    Full Text Available Radiopharmaceuticals labeled with short-lived positron-emitting or gamma-emitting isotopes are injected into patients just prior to performing positron emission tomography (PET or single photon emission tomography (SPECT scans, respectively. These imaging modalities are widely used in clinical care, as well as in the development and evaluation of new therapies in clinical research. Prior to injection, these radiopharmaceuticals (tracers must undergo quality control (QC testing to ensure product purity, identity, and safety for human use. Quality tests can be broadly categorized as (i pharmaceutical tests, needed to ensure molecular identity, physiological compatibility and that no microbiological, pyrogenic, chemical, or particulate contamination is present in the final preparation; and (ii radioactive tests, needed to ensure proper dosing and that there are no radiochemical and radionuclidic impurities that could interfere with the biodistribution or imaging. Performing the required QC tests is cumbersome and time-consuming, and requires an array of expensive analytical chemistry equipment and significant dedicated lab space. Calibrations, day of use tests, and documentation create an additional burden. Furthermore, in contrast to ordinary pharmaceuticals, each batch of short-lived radiopharmaceuticals must be manufactured and tested within a short period of time to avoid significant losses due to radioactive decay. To meet these challenges, several efforts are underway to develop integrated QC testing instruments that automatically perform and document all of the required tests. More recently, microfluidic quality control systems have been gaining increasing attention due to vastly reduced sample and reagent consumption, shorter analysis times, higher detection sensitivity, increased multiplexing, and reduced instrumentation size. In this review, we describe each of the required QC tests and conventional testing methods, followed by a

  8. Management of gaseous radioactive wastes. Technical progress report, September 1, 1974--August 31, 1975

    International Nuclear Information System (INIS)

    First, M.W.

    1975-01-01

    Multi-ply absolute filter units were manufactured and are undergoing tests for penetration, loading, and heat resistance characteristics. All-metal fiber prefilters are under test with salt aerosols to investigate their particle retention characteristics at elevated temperatures and ability to protect downstream absolute filters from fire and smoke damage. (auth)

  9. Waste Isolation Safety Assessment Program. Technical progress report for FY-1978

    International Nuclear Information System (INIS)

    Brandstetter, A.; Harwell, M.A.; Howes, B.W.; Benson, G.L.; Bradley, D.J.; Raymond, J.R.; Serne, R.J.; Schilling, A.H.

    1979-07-01

    Associated with commercial nuclear power production in the United States is the generation of potentially hazardous radioactive wastes. The Department of Energy (DOE) is seeking to develop nuclear waste isolation systems in geologic formations that will preclude contact with the biosphere of waste radionuclides in concentrations which are sufficient to cause deleterious impact on humans or their environments. Comprehensive analyses of specific isolation systems are needed to assess the expectations of meeting that objective. The Waste Isolation Safety Assessment Program (WISAP) has been established at the Pacific Northwest Laboratory (operated by Battelle Memorial Institute) for developing the capability of making those analyses. Progress on the following tasks is reported: release scenario analysis, waste form release rate analysis, release consequence analysis, sorption-desorption analysis, and societal acceptance analysis

  10. Repository Technology Program: Technical progress report for the period May 29, 1986--June 30, 1987

    International Nuclear Information System (INIS)

    1988-10-01

    This document reports the progress made in the 13-month period from May 29, 1986--June 30, 1987, on the development of a second geologic repository in rocks other than those being considered for a first repository. Subsequent periods will be covered in reports to be issued on a semiannual basis. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Waste Technology Development (OWTD), a prime contractor of the US. Department of Energy (DOE) Repository Technology Program (RTP) Office in the Repository Technology and Transportation Division (RTTD) of the Office of Geologic Repositories (OGR). The studies include work by other DOE prime contractors and by contractors to the OWTD. 50 refs

  11. Waste Isolation Safety Assessment Program. Technical progress report for FY-1978

    Energy Technology Data Exchange (ETDEWEB)

    Brandstetter, A.; Harwell, M.A.; Howes, B.W.; Benson, G.L.; Bradley, D.J.; Raymond, J.R.; Serne, R.J.; Schilling, A.H.

    1979-07-01

    Associated with commercial nuclear power production in the United States is the generation of potentially hazardous radioactive wastes. The Department of Energy (DOE) is seeking to develop nuclear waste isolation systems in geologic formations that will preclude contact with the biosphere of waste radionuclides in concentrations which are sufficient to cause deleterious impact on humans or their environments. Comprehensive analyses of specific isolation systems are needed to assess the expectations of meeting that objective. The Waste Isolation Safety Assessment Program (WISAP) has been established at the Pacific Northwest Laboratory (operated by Battelle Memorial Institute) for developing the capability of making those analyses. Progress on the following tasks is reported: release scenario analysis, waste form release rate analysis, release consequence analysis, sorption-desorption analysis, and societal acceptance analysis. (DC)

  12. Texas Experimental Tokamak: A plasma research facility. Technical progress report, November 1, 1993--October 31, 1994

    Energy Technology Data Exchange (ETDEWEB)

    Wootton, A.J.

    1994-07-01

    The purpose is to operate and maintain TEXT Upgrade as a complete facility for applied tokamak physics in order to elucidate the mechanisms of working gas, impurity, and thermal transport in tokamaks and in particular to understand the role of turbulence. So that they can continue to study the physics that is most relevant to the fusion program, TEXT completed a significant device upgrade this year. The new capabilities of the device and new and innovative diagnostics were exploited in all main program areas including: (1) configuration studies; (2) electron cyclotron heating physics; (3) improved confinement modes; (4) edge physics/impurity studies; (5) central turbulence and transport; and (6) transient transport. Details of the progress in each of the research areas are described.

  13. Texas Experimental Tokamak: A plasma research facility. Technical progress report, November 1, 1993--October 31, 1994

    International Nuclear Information System (INIS)

    Wootton, A.J.

    1994-07-01

    The purpose is to operate and maintain TEXT Upgrade as a complete facility for applied tokamak physics in order to elucidate the mechanisms of working gas, impurity, and thermal transport in tokamaks and in particular to understand the role of turbulence. So that they can continue to study the physics that is most relevant to the fusion program, TEXT completed a significant device upgrade this year. The new capabilities of the device and new and innovative diagnostics were exploited in all main program areas including: (1) configuration studies; (2) electron cyclotron heating physics; (3) improved confinement modes; (4) edge physics/impurity studies; (5) central turbulence and transport; and (6) transient transport. Details of the progress in each of the research areas are described

  14. New imaging systems in nuclear medicine. Technical progress report, October 1, 1976--May 31, 1977

    International Nuclear Information System (INIS)

    Brownell, G.L.

    1977-01-01

    Work carried out on the development of instrumentation and techniques for positron scintigraphy is discussed. Progress in positron imaging instrumentation and applications is detailed. The assembly and initial evaluation of the new multicrystal positron camera, PC-II, has been completed. Images have been obtained in both two and three-dimensions which demonstrate the basic physical properties of the instrument. Successful measurements using transverse section imaging have been carried out on animals and human volunteers. Physiological investigation using PC-II is proceeding. A flexible and accurate computer program has been developed for transverse section reconstruction of data acquired by PC-II. This program makes it possible to reconstruct both the activity distribution and the distribution of absorption. The program has been developed in such a way that it can handle variations in the data collection procedure. Clinical studies using PC-I and PC-II are being carried on in areas of heart, lung and brain

  15. [Geothermal system temperature-depth database and model for data analysis]. 5. quarterly technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    Blackwell, D.D.

    1998-04-25

    During this first quarter of the second year of the contract activity has involved several different tasks. The author has continued to work on three tasks most intensively during this quarter: the task of implementing the data base for geothermal system temperature-depth, the maintenance of the WWW site with the heat flow and gradient data base, and finally the development of a modeling capability for analysis of the geothermal system exploration data. The author has completed the task of developing a data base template for geothermal system temperature-depth data that can be used in conjunction with the regional data base that he had already developed and is now implementing it. Progress is described.

  16. Radioecology of natural systems in Colorado. Thirteenth technical progress report, May 1, 1974--April 30, 1975

    International Nuclear Information System (INIS)

    Whicker, F.W.

    1975-01-01

    Progress is reported on studies on the behavior of fallout radionuclides ( 137 Cs and 90 Sr) in selected organisms and natural ecosystems in Colorado. Components of alpine tundra, montane forests, shortgrass plains, and freshwater lakes and streams are currently under investigation. A study on the effect of gut passage on the mean diameter of monodisperse PuO 2 microspheres was initiated. Studies on plutonium in the terrestrial environs of Rocky Flats were initiated in the summer of 1972. Soil movement measurements were conducted to bear on the question of plutonium stability in contaminated areas. The relative importance of root uptake versus aerial deposition was evaluated in the field utilizing a sod block transplant procedure. The study on radiation effects on shortgrass plains vegetation was continued with emphasis on long-term changes in community structure under chronic irradiation stress and recovery patterns. (U.S.)

  17. Nuclear structure theory. Annual technical progress report, 1 July 1974--30 June 1975

    International Nuclear Information System (INIS)

    French, J.B.; Koltun, D.S.

    1975-01-01

    Progress during the past year is summarized for the following areas of nuclear structure and reaction theory: Meson interactions with nucleons and nuclei, including inelastic scattering of pions, three-body theories of scattering and absorption of pions by deuterons, and π-p bremsstrahlung. Theory of the effective interaction, including behavior of the expansion in orders of the reaction matrix. Statistical spectroscopy including fluctuations in energy levels and excitation strengths, and sum rules and strength distributions for various excitation processes, including single-nucleon transfer, β decay and multipole giant resonances. Studies of the inverse scattering problem. Studies of nuclear symmetries, of nuclear clustering, and of general nuclear structure by α-transfer reactions, and of nuclear shapes by (d, 3 He) reactions. (U.S.)

  18. Scientific and technical progress in high-energy astrophysics at INPE

    International Nuclear Information System (INIS)

    Bui-Van, N.A.; Jayanthi, U.B.; Jardim, J.O.D.; Braga, J.; Santo, C.M.E.

    1984-01-01

    The recent advances in high-energy Astrophysics pertains to the study of compact objects in galactic nuclei, binary systems and pulsars. These aspects are best understood by the study of the emissions in X- and gamma rays of these objects through the temporal variation in flux and spectrum. The Southern Hemisphere offers some of the unique objects for investigations such as galactic center, the Vela pulsar etc. For high temporal and spectra resolution studies two telescopes 'GeLi' and 'Pulsar' were designed and constructed. To support these scientific activities, a program in balloon launching and data acquisition facilities has been developed since 1971. The 'Balloon Launching Center' of INPE has capacity to launch balloons of -850,000 m 3 with payloads weighting about 1,000 Kg. Taking advantage of these facilities, project 'Bantar', with the goal to measure the atmospheric gamma-ray radiation in the Antartic Region, is under progress. (Author) [pt

  19. Crystalline Repository Project: Technical progress report for the period October 1, 1982--May 28, 1986

    International Nuclear Information System (INIS)

    1988-11-01

    This document reports the progress made on the development of a second geologic repository in crystalline rocks during the duration of the Crystalline Repository Project from its inception in October 1982 to its termination in May 1986. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Waste Technology Development (OWTD), successor to the Office of Crystalline Repository Development. OWTD is a prime contractor of the US Department of Energy (DOE) Repository Technology Program Office, itself the successor to the Crystalline Repository Project Office. The studies include work by other DOE prime contractors and by contractors to the Office of Crystalline Repository Development. 151 refs

  20. Savannah River Ecology Laboratory. Annual technical progress report of ecological research

    International Nuclear Information System (INIS)

    Smith, M.H.

    1996-01-01

    The Savannah River Ecology Laboratory (SREL) is a research unit of the University of Georgia (UGA). The overall mission of the Laboratory is to acquire and communicate knowledge of ecological processes and principles. SREL conducts basic and applied ecological research, as well as education and outreach programs, under a contract with the U.S. Department of Energy (DOE) at the Savannah River Site (SRS) near Aiken, South Carolina. Significant accomplishments were made during the past year in the areas of research, education and service. The Laboratory's research mission was fulfilled with the publication of two books and 143 journal articles and book chapters by faculty, technical and students, and visiting scientists. An additional three books and about 80 journal articles currently are in press. Faculty, technician and students presented 193 lectures, scientific presentations, and posters to colleges and universities, including minority institutions. Dr. J Vaun McArthur organized and conducted the Third Annual SREL Symposium on the Environment: New Concepts in Strewn Ecology: An Integrative Approach. Dr. Michael Newman conducted a 5-day course titled Quantitative Methods in Ecotoxicology, and Dr. Brian Teppen of The Advanced Analytical Center for Environmental Sciences (AACES) taught a 3-day short course titled Introduction to Molecular Modeling of Environmental Systems. Dr. I. Lehr Brisbin co-hosted a meeting of the Crocodile Special Interest Group. Dr. Rebecca Sharitz attended four symposia in Japan during May and June 1996 and conducted meetings of the Executive Committee and Board of the International Association for Ecology (ENTECOL)

  1. Gas-Cooled Thermal Reactor Program. Semiannual technical progress report, October 1, 1982-March 3, 1983

    International Nuclear Information System (INIS)

    1983-06-01

    This report provides descriptions and results of the technical effort during the first half of FY 83 on the Gas-Cooled Thermal Reactor Program. The work on Integration and Management (WBS 01) includes the preparation of the Advanced Systems Concept Evaluation Plan and the Advanced Systems Technology Development Plan in addition to the program management activities. The Market Definition (WBS 03) efforts considered the application of the Modular Reactor System with reforming (MRS-R) to the production of methanol and ammonia and the refining of petroleum. Within the Plant Technology (WBS 13) task there were activities to develop anlytical methods for investigation of Coolant Transport Behavior and to define methods and criteria for High Temperature Structural Engineering design. In addition to the work on the advanced HTGR for process heat users, new activities were initiated in support of the HTGR-SC/C Lead plant Protect (WBS 30 and 31). The Plant Simulation task (WBS 31) was initiated to develop a computer code for simulation of plant operation and for plant transient systems analysis. The efforts on the advanced HTGR systems was performed under the Modular Systems task (WBS 41) to study the potential for multiple small reactors to provide lower costs, improved safety, and higher availability than the large monolithic core reactors

  2. Savannah River Ecology Laboratory. Annual technical progress report of ecological research

    Energy Technology Data Exchange (ETDEWEB)

    Smith, M.H.

    1996-07-31

    The Savannah River Ecology Laboratory (SREL) is a research unit of the University of Georgia (UGA). The overall mission of the Laboratory is to acquire and communicate knowledge of ecological processes and principles. SREL conducts basic and applied ecological research, as well as education and outreach programs, under a contract with the U.S. Department of Energy (DOE) at the Savannah River Site (SRS) near Aiken, South Carolina. Significant accomplishments were made during the past year in the areas of research, education and service. The Laboratory`s research mission was fulfilled with the publication of two books and 143 journal articles and book chapters by faculty, technical and students, and visiting scientists. An additional three books and about 80 journal articles currently are in press. Faculty, technician and students presented 193 lectures, scientific presentations, and posters to colleges and universities, including minority institutions. Dr. J Vaun McArthur organized and conducted the Third Annual SREL Symposium on the Environment: New Concepts in Strewn Ecology: An Integrative Approach. Dr. Michael Newman conducted a 5-day course titled Quantitative Methods in Ecotoxicology, and Dr. Brian Teppen of The Advanced Analytical Center for Environmental Sciences (AACES) taught a 3-day short course titled Introduction to Molecular Modeling of Environmental Systems. Dr. I. Lehr Brisbin co-hosted a meeting of the Crocodile Special Interest Group. Dr. Rebecca Sharitz attended four symposia in Japan during May and June 1996 and conducted meetings of the Executive Committee and Board of the International Association for Ecology (ENTECOL).

  3. Pulverized coal firing of aluminum melting furnaces. First annual technical progress report, May 1978-June 1979

    Energy Technology Data Exchange (ETDEWEB)

    West, C.E.; Hines, J.E.; Stewart, D.L. Jr.; Yu, H.

    1979-10-01

    The ultimate objective of this program is the commercial demonstration of an efficient, environmentally acceptable coal firing process suitable for implementation on melting furnaces throughout the aluminum industry. To achieve this goal, the program has been divided into two phases. Phase I has begun with the design and construction of a 350 lb/h (coal) staged slagging cyclone combustor (SSCC) attached to a 7-ft dia aluminum melting ladle furnace. Process development will culminate with a 1000 pph prototype SSCC firing a 40,000 lb capacity open hearth melting furnace at the Alcoa Laboratories. Phase II implementation is currently planned for Alcoa's Lafayette, IN, Works, where two of the ingot plant's five open hearth melting furnaces will be converted to utilize coal. In addition to confirmation of data gathered in Phase I, the effect of extended production schedule operation on equipment and efficiencies will be determined. This work would begin in 1982 pursuant to technical and economic evaluation of the process development at that time. A major design subcontract for assistance in the design of the SSCC is 80% completed.

  4. Low-level waste disposal site geotechnical subsidence corrective measures: technical progress

    International Nuclear Information System (INIS)

    Phillips, S.J.; Winterhalder, J.A.; Gilbert, T.W.

    1983-01-01

    A geotechnical test facility has been constructed at the Hanford Site Richland Site Richland, Washington. The purpose of this facility is to quantitatively evaluate the performance of alternative technologies to ameliorate geomechanical subsidence in solid waste burial structures. Alternatives to be tested include; accelerating mass ground surface impact, and two optional subsurface rod injection/withdrawal techniques. The alternatives involve the principle of dynamic consolidation of buried waste and matrix materials. A description of the geotechnical test facility, the monitoring instrumentation used therein, laboratory soil mechanics data evaluation, and facility baseline monitoring data are presented. 6 references, 5 figures

  5. In-place testing summary (1992). Progress report

    International Nuclear Information System (INIS)

    Martinez, V.A.; Barney, D.; Helland, G.; Kain, C.

    1994-09-01

    This report is the latest in a series of annual reports regarding the ongoing in-place testing program for high-efficiency filtration and chemical adsorber systems at the Los Alamos National Laboratory. This testing is conducted to maintain regulatory permits and to verify that the performance levels, installation, and function of these filtration systems have not deteriorated since the last operating cycle. Furthermore, the performance data obtained from the testing of high efficiency particulate air-filtered vacuums and negative pressure machines aid in the implementation and continuing activities of the asbestos management program at Los Alamos national Laboratory. In addition, this report provides an overview of the testing procedures used to conduct the in-place tests, a summary of the individual system performance, and any trend that has been observed since the last operating cycle

  6. A test to evaluate the physical impact on technical performance in soccer

    DEFF Research Database (Denmark)

    Rostgaard, Thomas; Iaia, F. Marcello; Simonsen, Dennis S.

    2008-01-01

    The aim of the study was to develop and examine a test for evaluation of the physical and technical capacity of soccer players. Fourteen youth elite (YE) and seven sub-elite (SE) players performed a physical and technical test (PT-test) consisting of 10 long kicks interspersed with intense......(-1), and 76 +/- 11 umol L(-1) at the end of the test, respectively. After the test muscle CP, glycogen and lactate was 52.9 +/- 6.6, 354 +/- 39, and 25.3 +/- 5.9 mmol kg(-1) d.w., respectively. In summary, the PT-test can be used to evaluate a soccer player's technical skills under conditions similar...... intermittent exercise. In addition, a control test (CON-test) without intense exercise was performed. In both cases, the test result was evaluated by the precision of the 10 kicks. The players also performed the Yo-Yo intermittent recovery test level 2 (Yo-Yo IR2). For the SE-players, blood samples were...

  7. Optimal design and routing of power lines; ecological, technical and economic perspectives (OPTIPOL). Progress report 2009

    Energy Technology Data Exchange (ETDEWEB)

    Bevanger, K.; Bartzke, G.; Broeseth, H.; Gjershaug, J.O.; Hanssen, F.; Jacobsen, K.-O.; Kvaloey, P.; May, R.; Nygaard, T.; Pedersen, H.C.; Reitan, O.; Refsnaes, S.; Stokke, S.; Vang, R.

    2009-12-15

    From 2009 inclusive, NINA has received economic support for research on power lines and wildlife from the Norwegian Research Council (NFR) through the RENERGI Programme. The project is named 'Optimal design and routing of power lines; ecological, technical and economic perspectives' (OPTIPOL). It is scheduled for 5 years (2009-1013) and is part of the activities within CEDREN, i.e. the Centre for environmental design of renewable energy (cf. http://www.cedren.no). With a grid close to 200 000 km overhead power-lines, the associated rights-of-way (ROW) affect huge land areas in Norway. The overall goal is to develop predict-ing tools for optimal routing of power lines from an environmental perspective and assess technical and economic solutions to minimize conflicts with wildlife and habitat conservation. Thus, the OPTIPOL rationale is based on the belief that the negative effects of electricity transmission and distribution can be reduced with respect to birds and mammals. OPTIPOL has several ambitious objectives, and is divided into sub-projects and specific tasks. From the first of November a PhD-student became part of the project, a position that will be held for 4 years. The main objective of the PhD-activities will be to assess how and why different wildlife species use deforested areas below power lines, evaluate possible positive and negative effects of power-line ROWs, and assess the possibilities for quality improvement. Another part of the project is dedicated the effects of linear structures on movement patterns and distribution in the landscape in native deer species. Here we will examine how different spatial scales influence the processes that guide movement patterns, and responses to linear structures. Another focus will be small game species, with mountain hare, capercaillie, black grouse and hazel grouse as model species. The main objective will be to assess the impact of transforming ROW habitats into attractive small-game foraging

  8. Republic of Poland; Technical Note on Stress Testing the Banking Sector

    OpenAIRE

    International Monetary Fund

    2013-01-01

    This Technical Note discusses results of stress testing of the banking sector in Poland. The Polish banking system is well capitalized and liquid, as confirmed by stress tests results. Polish banks are, in aggregate, resilient even under severe adverse scenarios. Some small banks could fail to meet minimum regulatory capital and liquidity requirements in these scenarios, but with little impact on the overall banking system. Tests showed that only small banks, together representing up to 30 pe...

  9. Possible checking of technical parameters in nondestructive materials and products testing

    International Nuclear Information System (INIS)

    Kesl, J.

    1987-01-01

    The requirements are summed up for partial technical parameters of instruments and facilities for nondestructive testing by ultrasound, radiography, by magnetic, capillary and electric induction methods. The requirements and procedures for testing instrument performance are presented for the individual methods as listed in domestic and foreign standards, specifications and promotional literature. The parameters to be tested and the methods of testing, including the testing and calibration instruments are shown in tables. The Czechoslovak standards are listed currently valid for nondestructive materials testing. (M.D.)

  10. Cascade Distillation Subsystem Development: Progress Toward a Distillation Comparison Test

    Science.gov (United States)

    Callahan, M. R.; Lubman, A.; Pickering, Karen D.

    2009-01-01

    Recovery of potable water from wastewater is essential for the success of long-duration manned missions to the Moon and Mars. Honeywell International and a team from NASA Johnson Space Center (JSC) are developing a wastewater processing subsystem that is based on centrifugal vacuum distillation. The wastewater processor, referred to as the Cascade Distillation Subsystem (CDS), utilizes an innovative and efficient multistage thermodynamic process to produce purified water. The rotary centrifugal design of the system also provides gas/liquid phase separation and liquid transport under microgravity conditions. A five-stage subsystem unit has been designed, built, delivered and integrated into the NASA JSC Advanced Water Recovery Systems Development Facility for performance testing. A major test objective of the project is to demonstrate the advancement of the CDS technology from the breadboard level to a subsystem level unit. An initial round of CDS performance testing was completed in fiscal year (FY) 2008. Based on FY08 testing, the system is now in development to support an Exploration Life Support (ELS) Project distillation comparison test expected to begin in early 2009. As part of the project objectives planned for FY09, the system will be reconfigured to support the ELS comparison test. The CDS will then be challenged with a series of human-gene-rated waste streams representative of those anticipated for a lunar outpost. This paper provides a description of the CDS technology, a status of the current project activities, and data on the system s performance to date.

  11. Solid State Sciences Committee (SSSC). Technical progress report, May 1, 1992--April 30, 1993

    International Nuclear Information System (INIS)

    Taylor, R.

    1995-01-01

    The Solid State Sciences Committee (SSSC) of the National Research Council (NRC) is charged with monitoring the health of the field of materials science in the United States. Accordingly, the Committee identifies and examines both broad and specific issues affecting the field. Regular meetings, teleconferences, briefings from agencies and the scientific community, the formation of study panels to prepare reports, and special forums are among the mechanisms used by the SSSC to meet its charge. This progress report presents a review of SSSC activities from May 1, 1992 through April 30, 1993. The details of prior activities are discussed in earlier reports. During the above period, the SSSC has continued to track and participate, when requested, in the development of a Federal initiative on advanced materials and processing. Specifically, the SSSC is presently planning the 1993 SSSC Forum (to be cosponsored with the National Materials Advisory Board (NMAB) and the Washington Materials Forum (WMF)). The thrust will be to highlight the Federal Advanced Materials and Processing Program (AMPP). In keeping with its charge to identify and highlight specific areas for scientific and technological opportunities, the SSSC continued to oversee the conduct of a study on biomolecular materials. Preliminary plans also were developed for a study on neutron science, however, further activity is pending. A proposed study on ultrasmall devices has been expanded and absorbed into a broader context; the BPA, with SSSC participation, is preparing to hold a program initiation meeting to evaluate the need for a study on information technology and hardware

  12. Advanced converter technology. Technical progress report, May 23, 1979-May 22, 1980

    Energy Technology Data Exchange (ETDEWEB)

    Banic, C. V.; Eckhouse, S. A.; Kornbrust, F. J.; Lipman, K.; Peterson, J. L.; Rosati, R. W.

    1980-01-01

    The overall objective of this program is to define an advanced converter system employing 1980's technology in all subsystem and component areas for use in electrochemical energy storage systems. Additional experimental effort will validate elements of the advanced commutation circuitry on a full-scale breadboard basis. Improved models of battery electrical characteristics are beng defined and experimental apparatus is being designed to measure these characteristics and to enable better definition of the battery-power conditioner interface. Improvement of energy-storage system performance through modification of battery converter characteristics will also be investigated. During this first year of the contract, a new more advanced concept for power conditioning based on a concept defined by United Technologies Corporation for fuel cell use was evaluated. This high switching frequency concept has the potential for significantly reducing the size and cost of battery plant power conditioners. As a result, the Department of Energy authorized redirection of the program to first evaluate this new concept and then to reorient the program to adopt this concept as the primary one. Progress is reported. (WHK)

  13. Exploratory research on solvent refined coal liquefaction. Annual technical progress report, January 1-December 31, 1979

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-09-01

    This report summarizes the progress of the Exploratory Research on Solvent Refined Coal Liquefaction project by The Pittsburg and Midway Coal Mining Co.'s Merriam Laboratory during 1979. In a series of experiments with varying feed gas composition, low levels (5 to 10 mole %) of carbon monoxide had little effect on the SRC II processing of Pittsburgh Seam coal (Powhatan No. 5 Mine) while higher levels (20 to 40 mole %) resulted in a general degradation of operability and reduced oil yields. Addition of finely divided (approx. 1 ..mu..m) pyrite to the reactive Powhatan coal had little effect on oil yields although the molecular weight of the distillation residue was apparently decreased. When finely divided pyrite and magnetite were added to the less reactive coals from the Loveridge and Blacksville No. 1 Mines (also Pittsburgh Seam), however, substantial increases in oil yields and product quality were obtained. In a comparison of upflow and downflow dissolver configurations with Powhatan coal in the SRC II mode, there was no difference in yields or product quality. A study characterizing specific reactors revealed a significantly higher conversion in the SRC I mode with a reactor approximating plug flow conditions compared to a completely backmixed reactor. In the SRC II mode there was only a slightly higher oil yield with the plug flow reactor.

  14. Supramolecular structures for photochemical energy conversion. Technical progress report, 1993--1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-06-01

    This research project is concerned with the design, synthesis and study by photochemical and spectroscopic methods of complex molecular devices that mimic some important aspects of photosynthetic electron and energy transfer. Properly engineered molecules of this type can functionally mimic photosynthetic light harvesting (singlet-singlet energy transfer between chromophores), photoprotection from light-initiated singlet oxygen damage (triplet-triplet energy transfer from chlorophylls to carotenoid polyenes), and, most importantly, photoinduced multistep electron transfer to generate charge-separated states that preserve some of the photon energy as chemical potential. During the last three years, progress has been made on several fronts, all of which are related to the overall goal. A biomimetic system based on carotenoid-porphyrin-quinone triads has been constructed that demonstrates photoinduced transmembrane charge separation which in turn drives transmembrane proton transfer. Another investigation has focused on the use of proton transfer reactions to stabilize the initial products of photoinduced electron transfer and thereby increase the yield of long-lived charge separation. A third study has investigated the influence of rigid molecular geometries and short donor-acceptor separations on photoinduced electron transfer reactions. Finally, generation and quenching of singlet molecular oxygen by chlorophyll aggregates has been studied. All four studies are described and results are discussed.

  15. Nuclear structure theory. Technical progress report, September 1, 1984-August 31, 1985

    International Nuclear Information System (INIS)

    French, J.B.; Koltun, D.S.

    1985-01-01

    This report summarizes progress in the following areas of research: Spectral Averaging, including the theory of level densities and partition functions for interacting nucleons, spectral distributions for fixed symmetries, general studies of distributions (in particular of strength distributions) considered as multivariate processes, and applications to the secular behavior of fluctuation measures; spectral and strength fluctuations, including study of the transitions between different fluctuation patterns (i.e., between different types of quantum chaos) as a conserved symmetry is gradually broken, application of these results to determining values of, or upper bounds for, the goodness of symmetries in complex nuclei, reduction of values or bounds to statements about the nuclear Hamiltonian, in particular for time-reversal symmetry, and specific studies of quantum chaos; statistical theory of pion absorption, including analysis of the (π,p) inclusive reaction; and quark theory of nuclear matter, involving development of models which show two limiting behaviors - that of a Fermi gas of nucleons (quark clusters) at low density and of a Fermi gas of quarks at high density. Both variational and exact solutions of one model have been found. 9 refs

  16. University of Colorado at Boulder Nuclear Physics Laboratory technical progress report

    International Nuclear Information System (INIS)

    Peterson, R.J.

    1991-01-01

    This report summarizes experimental work carried out between October 1, 1990, the closing of our Progress Report, and August 14, 1991 at the Nuclear Physics Laboratory of the University of Colorado, Boulder, under contract DE-FG02-ER40269 with the United States Department of Energy. This contract supports broadly based experimental work in intermediate energy nuclear physics. The program includes pion-nucleon studies at TRIUMF and LAMPF, inelastic pion scattering and charge exchange reactions at LAMPF, and nucleon charge exchange at LAMPF/NTOF. The first results of spin-transfer observables in the isovector (rvec p,rvec n) reaction are included in this report. Our data confirm the tentative result from (rvec p,rvec p') reactions that the nuclear isovector spin response shows neither longitudinal enhancement nor transverse queching. Our program in quasifree scattering of high energy pions shows solid evidence of isoscalar enhancement of the nuclear nonspin response. We include several comparisons of the quasifree scattering of different probes. Results from our efforts in the design of accelerator RF cavities are also included in this report

  17. Proton resonance spectroscopy. Quarterly technical progress report, December 1992--November 1995

    International Nuclear Information System (INIS)

    Shriner, J.F. Jr.

    1995-11-01

    Work on chaos in the low-lying levels of nuclei has continued on several fronts. The major effort has been study of the 29 Si(p,γ) reaction with the goal of establishing a complete level scheme for 30 P and analyzing the eigenvalue fluctuations for evidence of chaos. These measurements are in progress, and the current status is described. A related topic is the search for different signatures of chaos which do not require the extremely high degree of completeness and purity necessary for eigenvalue analyses; those efforts are discussed in Sections 2 and 3. The possibility of studying both parity violation and time-reversal invariance violation with charged particle resonances has been explored by performing calculations using experimentally measured resonance parameters. Large enhancements are indeed available; the results are discussed in Sections 4 and 5. Preparations for an experimental study of parity violation using these techniques are ongoing. An undergraduate project searching for experimental evidence of a parity dependence of level density is discussed in Section 6. A number of improvements to the operation of the TUNL KN accelerator have been implemented in the past three years. These are described in Section 7

  18. Proton resonance spectroscopy. Quarterly technical progress report, December 1992--November 1995

    Energy Technology Data Exchange (ETDEWEB)

    Shriner, J.F. Jr.

    1995-11-01

    Work on chaos in the low-lying levels of nuclei has continued on several fronts. The major effort has been study of the {sup 29}Si(p,{gamma}) reaction with the goal of establishing a complete level scheme for {sup 30}P and analyzing the eigenvalue fluctuations for evidence of chaos. These measurements are in progress, and the current status is described. A related topic is the search for different signatures of chaos which do not require the extremely high degree of completeness and purity necessary for eigenvalue analyses; those efforts are discussed in Sections 2 and 3. The possibility of studying both parity violation and time-reversal invariance violation with charged particle resonances has been explored by performing calculations using experimentally measured resonance parameters. Large enhancements are indeed available; the results are discussed in Sections 4 and 5. Preparations for an experimental study of parity violation using these techniques are ongoing. An undergraduate project searching for experimental evidence of a parity dependence of level density is discussed in Section 6. A number of improvements to the operation of the TUNL KN accelerator have been implemented in the past three years. These are described in Section 7.

  19. Technical progress report for UTSI/CFFF MHD program completion and related activity

    International Nuclear Information System (INIS)

    Chapman, James N.; Muehlhauser, Joel W.

    1998-01-01

    Routine preventive maintenance of the DOE Coal Fired Flow Facility (CFFF) is being performed. Modernization programs, funded under subcontract from Foster Wheeler Development Corporation by the DOE HIPPS Program, have been completed on the coal processing system, the data acquisition and control system and the control room. Late in the quarter, all work was stopped on maintenance of the CFFF at DOE instruction. Environmental restoration actions continued with monitoring of groundwater wells and holding pond effluent. Progress is reported on the approved groundwater remediation plan. Actions are underway to dispose of spent seed/ash mixtures and excess coal remaining from the MHD POC program. The status of five (5) High Temperature Superconductor (HTS) projects is reported. A summary is included of the results attained with sol-gel experiments with buffer layers and YBCO. The status of the cost/performance study of electron beam and PLD deposition is pre-sented. A summary of work performed in diagnostics for real time control of HTS processes is presented

  20. TECHNICAL PROGRESS REPORT FOR UTSI/CFFF MHD PROGRAM COMPLETION AND RELATED ACTIVITIES

    Energy Technology Data Exchange (ETDEWEB)

    DR. JAMES N. CHAPMAN; DR. JOEL W. MUEHLHAUSER

    1998-10-23

    Routine preventive maintenance of the DOE Coal Fired Flow Facility (CFFF) is being performed. Modernization programs, funded under subcontract from Foster Wheeler Development Corporation by the DOE HIPPS Program, have been completed on the coal processing system, the data acquisition and control system and the control room. Late in the quarter, all work was stopped on maintenance of the CFFF at DOE instruction. Environmental restoration actions continued with monitoring of groundwater wells and holding pond effluent. Progress is reported on the approved groundwater remediation plan. Actions are underway to dispose of spent seed/ash mixtures and excess coal remaining from the MHD POC program. The status of five (5) High Temperature Superconductor (HTS) projects is reported. A summary is included of the results attained with sol-gel experiments with buffer layers and YBCO. The status of the cost/performance study of electron beam and PLD deposition is pre-sented. A summary of work performed in diagnostics for real time control of HTS processes is presented.

  1. Nuclear structure theory: Technical progress report for period September 1, 1986-August 31, 1987

    International Nuclear Information System (INIS)

    French, J.B.; Koltun, D.S.

    1987-08-01

    This report summarizes progress in the following areas of research: (1) quark theory of nuclear matter, including further development of models in one-dimension with analytic solutions, numerical studies, bound properties, inclusion of spin and isospin degrees of freedom, excitation properties and response function; electron scattering, including application of sum rules to deeply inelastic scattering, and of quark models of nuclei; charge exchange in pion-nucleus reactions, including models of isotensor optical potential, optical theorem for double charge exchange, and coupled-channel calculations of single charge exchange; a unified theory of reaction dynamics and nuclear structure for intermediate energies, including diagrammatic formulation and development of appropriate computer programs; weak interactions: a study of the neutrino mass-matrix; bounds for time reversal noninvariance in the nucleon-nucleon interaction, obtained from spectral and strength fluctuations in complex nuclei, and separately from detailed balance in compound nuclear reactions. The relative sensitivities of the two methods are discussed; fluctuation measures for the two-dimensional harmonic oscillator; random matrices and symmetry-breaking in atomic spectra data; saturation effects for spectral measures in many-particle systems; and finally fluctuation-free statistical spectroscopy, applied to state densities and partition functions, including accurate absolute calculations of nuclear level spacings

  2. Technical progress report to the Department of Energy on the Solid State Sciences Committee (SSSC)

    International Nuclear Information System (INIS)

    1995-01-01

    The Solid State Sciences Committee (SSSC) of the National Research Council (NRC) is charged with monitoring the health of the field of materials science in the United States. Accordingly, the Committee identifies and examines both broad and specific issues affecting the field. Regular meetings, teleconferences, briefings from agencies and the scientific community, the formation of study panels to prepare reports, and special forums are among the mechanisms used by the SSSC to meet its charge. This progress report presents a review of SSSC activities from May 1, 1992 through April 30, 1993. The details of prior activities are discussed in earlier reports. During the above period, the SSSC has continued to track and participate, when requested, in the development of a Federal initiative on advanced materials and processing. Specifically, the SSSC is presently planning the 1993 SSSC Forum (to be cosponsored with the National Materials Advisory Board (NMAB) and the Washington Materials Forum (WNM)). The thrust will be to highlight the Federal Advanced Materials and Processing Program (AMPP). In keeping with its charge to identify and highlight specific areas for scientific and technological opportunities, the SSSC continued to oversee the conduct of a study on biomolecular materials. Preliminary plans also have been developed for studies on neutron scattering science, on ultrasmall devices, and on molecular routes to materials

  3. Instrumentation and process control for fossil demonstration plants. Quarterly technical progress report, April--June 1977

    Energy Technology Data Exchange (ETDEWEB)

    LeSage, L.G.

    1977-07-01

    Work has been performed on updating the study of the state-of-the-art of instrumentation for Fossil Demonstration Plants (FDP), development of mass-flow and other on-line instruments for FDP, process control analysis for FDP, and organization of a symposium on instrumentation and control for FDP. A Solids/Gas Flow Test Facility (S/GFTF) under construction for instrument development, testing, evaluation, and calibration is described. The development work for several mass-flow and other on-line instruments is described: acoustic flowmeter, capacitive density flowmeter, neutron activation flowmeter and composition analysis system, gamma ray correlation flowmeter, optical flowmeter, and capacitive liquid interface level meter.

  4. Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol. 11, No. 1--Vol. 17, No. 6

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W.B.; Klein, A.

    1977-02-23

    This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970), through Vol. 17, No. 6 (Nov.-Dec. 1976). The index includes a chronological list of articles (including abstract) followed by KWIC and Author Indexes. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 350 technical articles in the last six years of publication.

  5. Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol. 11, No. 1--Vol. 17, No. 6

    International Nuclear Information System (INIS)

    Cottrell, W.B.; Klein, A.

    1977-01-01

    This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970), through Vol. 17, No. 6 (Nov.-Dec. 1976). The index includes a chronological list of articles (including abstract) followed by KWIC and Author Indexes. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 350 technical articles in the last six years of publication

  6. Power systems development facility. Quarterly technical progress report, July 1, 1994--September 30, 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    The objective of this project is to evaluate hot gas particle control technologies using coal-derived gas streams. This will entail the design, construction, installation, and use of a flexible test facility which can operate under realistic gasification and combustion conditions. The major particulate control device issues to be addressed include the integration of the particulate control devices into coal utilization systems, on-line cleaning techniques, chemical and thermal degradation of components, fatigue or structural failures, blinding, collection efficiency as a function of particle size, and scale-up of particulate control systems to commercial size. The conceptual design of the facility was extended to include a within scope, phased expansion of the existing Hot Gas Cleanup Test Facility Cooperative Agreement to also address systems integration issues of hot particulate removal in advanced coal-based power generation systems. This expansion included the consideration of the following modules at the test facility in addition to the original Transport Reactor gas source and Hot Gas Cleanup Units: (1) Carbonizer/Pressurized Circulating Fluidized Bed Gas Source. (2) Hot Gas Cleanup Units to mate to all gas streams. (3) Combustion Gas Turbine. (4) Fuel Cell and associated gas treatment. This expansion to the Hot Gas Cleanup Test Facility is herein referred to as the Power Systems Development Facility (PSDF).

  7. Research in elementary-particle physics. Technical progress report, April 1, 1982 to June 1, 1983

    International Nuclear Information System (INIS)

    Kirsch, L.E.; Schnitzer, H.J.; Bensinger, J.R.; Abbott, L.F.

    1983-01-01

    Equipment testing and experiments at the Multiparticle Spectrometer facility at Brookhaven are described, and involvement with the Collide Detector program at Fermilab is briefly described. Theoretical research on composite models, supersymmetry and supergravity, gauge theories, and studies on the phenomology of gauge theories are described

  8. Quarterly technical progress report for the period ending June 30, 1984

    Energy Technology Data Exchange (ETDEWEB)

    1984-10-01

    The Magnetohydrodynamics Program (Component Development and Integration Facility) in Butte, Montana, continued its site preparation for the TRW first-stage combustor installation. In the area of flue gas cleanup, our in-house research program is continuing its investigation into the causes of sorbent attrition in PETC's fluidized-bed copper oxide process for simultaneous SO/sub 2//NO/sub x/ removal. Interwoven with these tests is a series of spray dryer/electrostatic precipitator tests that are being conducted with the cooperation of Wheelabrator-Frye, Inc. This test series was completed this quarter, and the data show that when using a Kentucky coal, Wheelabrator-Frye's electrostatic precipitator provides excellent particulate control efficiency while using a spray dryer for sulfur dioxide removal. A unique project at Carnegie-Mellon University is looking at the concept of integrated environmental control for coal-fired power plants making use of precombustion, combustion, and postcombustion control, including systems for the simultaneous removal of more than one pollutant. The objective of this research is to develop a computer model and assessment for integrated environmental control systems that utilize conventional or advanced systems. The Liquid Phase Methanol Project Development Unit in LaPorte, Texas, was restarted after a successful shakedown run was completed. PETC has recently begun an in-house research project aimed at exploring the basic chemistry of liquefying coal in the presence of water under supercritical conditions. In the Alternative Fuels Technology Program, the Gulf Research and Development Company has completed the preliminary testing phase of its erosion test loop. Their results indicate that when pumping a coal-water slurry fuel through a flow loop, the erosion rate increases as velocity increases, suggesting a well-defined relationship between these two parameters.

  9. Advanced thermally stable jet fuels: Technical progress report, October 1994--December 1994

    Energy Technology Data Exchange (ETDEWEB)

    Schobert, H.H.; Eser, S.; Song, C.; Hatcher, P.G.; Boehman, A.; Coleman, M.M.

    1995-02-01

    There are five tasks within this project on thermally stable coal-based jet fuels. Progress on each of the tasks is described. Task 1, Investigation of the quantitative degradation chemistry of fuels, has 5 subtasks which are described: Literature review on thermal stability of jet fuels; Pyrolytic and catalytic reactions of potential endothermic fuels: cis- and trans-decalin; Use of site specific {sup 13}C-labeling to examine the thermal stressing of 1-phenylhexane: A case study for the determination of reaction kinetics in complex fuel mixtures versus model compound studies; Estimation of critical temperatures of jet fuels; and Surface effects on deposit formation in a flow reactor system. Under Task 2, Investigation of incipient deposition, the subtask reported is Uncertainty analysis on growth and deposition of particles during heating of coal-derived aviation gas turbine fuels; under Task 3, Characterization of solid gums, sediments, and carbonaceous deposits, is subtask, Studies of surface chemistry of PX-21 activated carbon during thermal degradation of jet A-1 fuel and n-dodecane; under Task 4, Coal-based fuel stabilization studies, is subtask, Exploratory screening and development potential of jet fuel thermal stabilizers over 400 C; and under Task 5, Exploratory studies on the direct conversion of coal to high quality jet fuels, are 4 subtasks: Novel approaches to low-severity coal liquefaction and coal/resid co-processing using water and dispersed catalysts; Shape-selective naphthalene hydrogenation for production of thermally stable jet fuels; Design of a batch mode and a continuous mode three-phase reactor system for the liquefaction of coal and upgrading of coal liquids; and Exploratory studies on coal liquids upgrading using mesopores molecular sieve catalysts. 136 refs., 69 figs., 24 tabs.

  10. Directional backlight liquid crystal autostereoscopic display: technical challenges, research progress, and prospect (Conference Presentation)

    Science.gov (United States)

    Fan, Hang; Li, Kunyang; Zhou, Yangui; Liang, Haowen; Wang, Jiahui; Zhou, Jianying

    2016-09-01

    Recent upsurge on virtual and augmented realities (VR and AR) has re-ignited the interest to the immerse display technology. The VR/AR technology based on stereoscopic display is believed in its early stage as glasses-free, or autostereoscopic display, will be ultimately adopted for the viewing convenience, visual comfort and for the multi-viewer purposes. On the other hand, autostereoscopic display has not yet received positive market response for the past years neither with stereoscopic displays using shutter or polarized glasses. We shall present the analysis on the real-world applications, rigid user demand, the drawbacks to the existing barrier- and lenticular lens-based LCD autostereoscopy. We shall emphasize the emerging autostereoscopic display, and notably on directional backlight LCD technology using a hybrid spatial- and temporal-control scenario. We report the numerical simulation of a display system using Monte-Carlo ray-tracing method with the human retina as the real image receiver. The system performance is optimized using newly developed figure of merit for system design. The reduced crosstalk in an autostereoscopic system, the enhanced display quality, including the high resolution received by the retina, the display homogeneity without Moiré- and defect-pattern, will be highlighted. Recent research progress including a novel scheme for diffraction-free backlight illumination, the expanded viewing zone for autostereoscopic display, and the novel Fresnel lens array to achieve a near perfect display in 2D/3D mode will be introduced. The experimental demonstration will be presented to the autostereoscopic display with the highest resolution, low crosstalk, Moiré- and defect- pattern free.

  11. Theory of high-energy-collision processes. Technical progress report, January 1-December 31, 1981

    International Nuclear Information System (INIS)

    1982-01-01

    Progress is described in the following areas: (1) several years ago, surprisingly simple expressions were obtained for the differential cross sections of e + e - → μ + μ - γ and e + e - → e + e - γ at high energies. Such simple expressions were generalized to twelve other similar radiative processes in QED and QCD. Afterwards, it was found that these results can be derived easily with the help of helicity amplitudes. This method is being investigated for many other radiative processes; (2) in the two-dimensional Ising model, the horizontal and vertical interaction energies are usually taken to be different. When this idea of different interactions in different directions is applied to the Z 2 lattice gauge theory in four dimensions, a limiting case is found which is exactly solvable. Contrary to numerical calculations at the symmetry point, the phase transition is found to be of second order; (3) on the subject of supersymmetry, general helicity and spin sum rules were obtained for massless and massive supermultiplets, and a functional integral approach was found as a natural setting for Witten's criterion for the occurrence of dynamic symmetry breaking of supersymmetry. A systematic and exhaustive analysis of explicit soft breaking of global supersymmetry has also been carried out using the methods of superfields; (4) the renormalization of the massless Thirring model in the neighborhood of g = -π/2 was studied. The results are consistent with those found previously by placing the model on a lattice; and (5) in studying the effect of laboratory temperature on scattering processes, it was found that transport phenomena play an important role. As a preparation for this study, an exactly solvable case of the nonlinear Boltzmann equation has been found and studied

  12. Nuclear Physics Laboratory, University of Colorado technical progress report, 1976 and proposal for continuation of contract

    International Nuclear Information System (INIS)

    1976-01-01

    This report summarizes the work carried out at the Nuclear Physics Laboratory of the University of Colorado during the period November 1, 1975 to November 1, 1976. The low energy nuclear physics section is dominated by light-ion reaction studies which span a wide range. These include both two-neutron and two-proton transfer reactions, charge exchange and inelastic scattering, as well as single nucleon transfer reactions. The nuclei studied vary widely in their mass and characteristics. These reaction studies have been aided by the multi-use scattering chamber which now allows the energy-loss-spectrometer beam preparation system (beam swinger) to shift from charged particle studies to neutron time-of-flight studies with a minimum loss of time. The intermediate energy section reflects the increase in activity accompanying the arrival of LAMPF data and the initiation of (p,d) studies at the Indiana separated-sector cyclotron. The nucleon removal results provided by the π beam at EPICS previous to completion of the spectrometer have shown that nuclear effects dominate this process, so that the widely used free interaction picture is inadequate. The section entitled ''Other Activities'' reveals continuing activities in new applications of nuclear techniques to problems in medicine and biology. Reactions important to astrophysics continue to be investigated and our trace-element program remains at a high level of activity. The theoretical section reports new progress in understanding magnitudes of two-step reactions by inclusion of finite-range effects. A new finite-range program which is fast and economical has been completed. Intermediate energy results include calculations of π-γ angular correlations, low energy π-nucleus interactions, as well as (p,d) and nucleon scattering calculations for intermediate energies

  13. Improved methods for water shutoff. Final technical progress report, October 1, 1997--September 30, 1998

    Energy Technology Data Exchange (ETDEWEB)

    Seright, R.S.; Liang, J.T.; Schrader, R.; Hagstrom, J. II; Liu, J.; Wavrik, K.

    1998-10-01

    In the United States, more than 20 billion barrels of salt water are produced each year during oilfield operations. A tremendous economic incentive exists to reduce water production if that can be accomplished without significantly sacrificing hydrocarbon production. This three-year research project had three objectives. The first objective was to identify chemical blocking agents that will (a) during placement, flow readily through fractures without penetrating significantly into porous rock and with screening out or developing excessive pressure gradients and (b) at a predictable and controllable time, become immobile and resistant breakdown upon exposure to moderate to high pressure gradients. The second objective was to identify schemes that optimize placement of the above blocking agents. The third objective was to explain why gels and other chemical blocking agents reduce permeability to one phase (e.g., water) more than that to another phase (e.g., oil or gas). The authors also wanted to identify conditions that maximize this phenomenon. This project consisted of three tasks, each of which addressed one of the above objectives. This report describes work performed during the third and final period of the project. During this three-year project, they: (1) Developed a procedure and software for sizing gelant treatments in hydraulically fractured production wells; (2) Developed a method (based on interwell tracer results) to determine the potential for applying gel treatments in naturally fractured reservoirs; (3) Characterized gel properties during extrusion through fractures; (4) Developed a method to predict gel placement in naturally fractured reservoirs; (5) Made progress in elucidating the mechanism for why some gels can reduce permeability to water more than that to oil; (6) Demonstrated the limitations of using water/oil ratio diagnostic plots to distinguish between channeling and coning; and (7) Proposed a philosophy for diagnosing and attacking water

  14. A Blood Test for Alzheimer's Disease: Progress, Challenges, and Recommendations.

    Science.gov (United States)

    Kiddle, Steven J; Voyle, Nicola; Dobson, Richard J B

    2018-03-29

    Ever since the discovery of APOEɛ4 around 25 years ago, researchers have been excited about the potential of a blood test for Alzheimer's disease (AD). Since then researchers have looked for genetic, protein, metabolite, and/or gene expression markers of AD and related phenotypes. However, no blood test for AD is yet being used in the clinical setting. We first review the trends and challenges in AD blood biomarker research, before giving our personal recommendations to help researchers overcome these challenges. While some degree of consistency and replication has been seen across independent studies, several high-profile studies have seemingly failed to replicate. Partly due to academic incentives, there is a reluctance in the field to report predictive ability, to publish negative findings, and to independently replicate the work of others. If this can be addressed, then we will know sooner whether a blood test for AD or related phenotypes with clinical utility can be developed.

  15. Progress report on pre-test calculations for the large block test

    International Nuclear Information System (INIS)

    Lee, K.H.

    1995-01-01

    The U.S. Department of Energy's (DOE) Yucca Mountain Site Characterization Project (YMP) is investigating the suitability of the Topopah Spring tuff in the thick vadose zone at Yucca Mountain, Nevada, as a host rock for permanent disposal of high-level radioactive waste. As part of the YMP, a group of field tests, referred to as the Large Block Test (LBT), will be conducted on a large electrically heated block of Topopah Spring tuff, isolated at Fran Ridge, Nevada Test Site. The block, which will be 3 x 3 m in horizontal dimensions and 4.5 m in height, will be heated by electrical heaters. The goals of the LBT axe to gain information on the coupled thermal-mechanical-hydrological-chemical processes active in the near-field environment of a repository; to provide field data for testing and calibrating models; and to help the development of measurement systems and techniques. This progress report presents results of on-going numerical modeling calculations carried out in support of the LBT design. An equivalent continuum model with an upper boundary temperature of 60 degrees C was used to simulate the hydrothermal response of the block to heating over a one-year period. The total heating power was started at 1500 W and later reduced to maintain an approximately uniform temperature of 138-140 degrees C. For a homogeneous bulk permeability case, the results show the formation of a distinct dry-out zone in and around the heater plane, and well-developed condensation zones above and below the heater plane. For a heterogeneous permeability distribution, the condensation zone above the heater plane was not well developed. This difference in results suggests that water saturation changes might be sensitive to changes in bulk permeability distribution. Rock temperatures were almost unaffected by permeability distribution. Heat flow was dominated by conduction. No liquid flow through the top of the block was predicted

  16. Research in elementary particle physics. Technical progress report, June 1, 1984-May 31, 1985

    International Nuclear Information System (INIS)

    Kirsch, L.E.; Schnitzer, H.J.; Bensinger, J.R.; Abbott, L.F.

    1985-01-01

    Research performed on both the experimental and theoretical properties of elementary particles is briefly described, including: construction of forward electromagnetic shower counters; BO test facility; gas monitor development and production; off-line simulation work for trigger studies; hyperon weak radiative decay; search for dibaryons of strangeness = -1; study of the Skyrme model; collider physics; quarkonium spectroscopy; some theoretical studies of the standard model; and studies of cosmology, the cosmological constant, and scalar fields in curved space-time. 37 refs

  17. Electron acceleration by laser fields in a gas: Technical progress report

    International Nuclear Information System (INIS)

    Fontana, J.R.

    1987-01-01

    Alternative media are considered for inverse Cherenkov interactions, with refractive indices given for several neutral gases. Breakdown considerations are taken into account as well as elastic collisions. Properties of ionized gases are also discussed as they relate to the usefulness of plasmas as accelerator media. The planning for inverse Cherenkov interaction experiments at a CO 2 laser, 50 MeV electron linac test facility is being carried out

  18. MHD Integrated Topping Cycle Project. Thirteenth quarterly technical progress report, August 1, 1990--October 31, 1990

    Energy Technology Data Exchange (ETDEWEB)

    1992-01-01

    The overall objective of the project is to design and construct prototypical hardware for an integrated MHD topping cycle, and conduct long duration proof-of-concept tests of integrated system at the US DOE Component Development and Integration Facility in Butte, Montana. The results of the long duration tests will augment the existing engineering design data base on MHD power train reliability, availability, maintainability, and performance, and will serve as a basis for scaling up the topping cycle design to the next level of development, an early commercial scale power plant retrofit. The components of the MHD power train to be designed, fabricated, and tested include: A slagging coal combustor with a rated capacity of 50 MW thermal input, capable of operation with an Eastern (Illinois {number_sign}6) or Western (Montana Rosebud) coal, a segmented supersonic nozzle, a supersonic MHD channel capable of generating at least 1.5 MW of electrical power, a segmented supersonic diffuser section to interface the channel with existing facility quench and exhaust systems, a complete set of current control circuits for local diagonal current control along the channel, and a set of current consolidation circuits to interface the channel with the existing facility inverter.

  19. Recent technical progress on BA Program: DEMO activities and IFMIF/EVEDA

    Energy Technology Data Exchange (ETDEWEB)

    Yamanishi, T.; Asakura, N.; Tobita, K.; Ohira, S. [Japan Atomic Energy Agency, Rokkasho, Aomori (Japan); Federici, G. [EFDA Close Support Unit, Garching (Germany); Heidinger, R. [Fusion for Energy, Garching (Germany); Knaster, J. [BA IFMIF/EVEDA Project Team, Rokkasho, Aomori (Japan); Clement, S. [Fusion for Energy, Barcelona (Spain); Nakajima, N. [BA IFERC Project Team, Rokkasho, Aomori (Japan)

    2016-11-01

    The Broader Approach (BA) activities consists of three major projects: the International Fusion Energy Research Center (IFERC) project, the International Fusion Materials Irradiation Facility/Engineering Validation and Engineering Design Activities (IFMIF/EVEDA) project, and the Satellite Tokamak Programme (STP, JT-60SA). These projects have been carried out to obtain basic data for the design of DEMO fusion reactor from 2007. For 8-year activities, the above projects could produce a set of fruitful results for the DEMO reactor. DEMO design activity has been conducted to build a set of DEMO design bases in accordance with a series of discussion between EU and JA. In the DEMO R&D activities, five basic R&D subjects for a DEMO blanket system have been selected, and been studies under close collaborations between EU and JA: structure materials (RAFM steels and SiC/SiC composites), functional materials (tritium breeders and neutron multipliers), and tritium technology. Some additional R&D subjects recommended by peer review comments have also been studied successfully in recent years. Regarding the IFMIF/EVEDA project, some main components of the accelerator facility been designed and tested. The validation test using EVEDA Lithium Test Loop (ELTL) was also completed successfully in October 2014.

  20. Spent Fuel Test - Climax: technical measurements. Interim report, fiscal year 1982

    International Nuclear Information System (INIS)

    Patrick, W.C.; Ballou, L.B.; Butkovich, T.R.

    1983-02-01

    The Spent Fuel Test - Climax (SFT-C) is located 420 m below surface in the Climax stock granite on the Nevada Test Site. The test is being conducted for the US Department of Energy (DOE) under the technical direction of the Lawrence Livermore National Laboratory (LLNL). Eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized April to May 1980, thus initiating a test with a planned 3- to 5-year fuel storage phase. The SFT-C operational objective of demonstrating the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner has been met. Three exchanges of spent fuel between the SFT-C and a surface storage facility furthered this demonstration. Technical objectives of the test led to development of a technical measurements program, which is the subject of this and two previous interim reports. Geotechnical, seismological, and test status data have been recorded on a continuing basis for the first 2-1/2 years of the test on more than 900 channels. Data continue to be acquired from the test. Some data are now available for analysis and are presented here. Highlights of activities this year include analysis of fracture data obtained during site characterization, laboratory studies of radiation effects and drilling damage in Climax granite, improved calculations of near-field heat transfer and thermomechanical response, a ventilation effects study, and further development of the data acquisition and management systems

  1. Language Testing in the Military: Problems, Politics and Progress

    Science.gov (United States)

    Green, Rita; Wall, Dianne

    2005-01-01

    There appears to be little literature available -- either descriptive or research-related -- on language testing in the military. This form of specific purposes assessment affects both military personnel and civilians working within the military structure in terms of posting, promotion and remuneration, and it could be argued that it has serious…

  2. Final Technical Progress Report Long term risk from actinides in the environment: Modes of mobility; FINAL

    International Nuclear Information System (INIS)

    Thomas B. Kirchner

    2002-01-01

    The key source of uncertainty in assessing actinide mobility is the relative importance of transport by: (1) wind erosion, (2) water erosion, and (3) vertical migration. Each of these three processes depends on several environmental factors and they compete with one another. A scientific assessment of the long-term risks associated with actinides in surface soils depends on better quantifying each of these three modes of mobility. The objective from our EMSP study was to quantify the mobility of soil actinides by wind erosion, water erosion, and vertical migration at three semiarid sites where actinide mobility is a key technical, social and legal issue. This EMSP project was the first to evaluate all three factors at a site. The approach has been to investigate both short- and long-term issues based on field and lab studies and model comparisons. Our results demonstrate the importance of incorporating threshold responses into a modeling framework that accounts for environmental factors and natural disturbances that trigger large changes in actinide mobility. The study measured erosional losses of sediment and fallout cesium (an actinide analogue) from field plots located near WIPP in 1998. The results highlight the large effect of burning as a disturbance on contaminant transport and mobility via runoff and erosion. The results show that runoff, erosion, and actinide transport are (1) strongly site specific-differences in radionuclide transport between WIPP and Rocky Flats differed by a factor of twelve because of soil and vegetation differences, and (2) are strongly impacted by disturbances such as fire, which can increase runoff, erosion, and actinide transport by more than an order of magnitude. In addition, a laboratory experiment using soil columns was conducted to investigate the vertical transport of contaminants in sandy soils. Nine columns of soil collected from the vicinity of the WIPP site were prepared. The column consisted of a piece of PVC pipe 20 cm

  3. Final Technical Progress Report Long term risk from actinides in the environment: Modes of mobility

    International Nuclear Information System (INIS)

    Kirchner, Thomas B.

    2002-01-01

    The key source of uncertainty in assessing actinide mobility is the relative importance of transport by: (1) wind erosion, (2) water erosion, and (3) vertical migration. Each of these three processes depends on several environmental factors and they compete with one another. A scientific assessment of the long-term risks associated with actinides in surface soils depends on better quantifying each of these three modes of mobility. The objective from our EMSP study was to quantify the mobility of soil actinides by wind erosion, water erosion, and vertical migration at three semiarid sites where actinide mobility is a key technical, social and legal issue. This EMSP project was the first to evaluate all three factors at a site. The approach has been to investigate both short- and long-term issues based on field and lab studies and model comparisons. Our results demonstrate the importance of incorporating threshold responses into a modeling framework that accounts for environmental factors and natural disturbances that trigger large changes in actinide mobility. The study measured erosional losses of sediment and fallout cesium (an actinide analogue) from field plots located near WIPP in 1998. The results highlight the large effect of burning as a disturbance on contaminant transport and mobility via runoff and erosion. The results show that runoff, erosion, and actinide transport are (1) strongly site specific-differences in radionuclide transport between WIPP and Rocky Flats differed by a factor of twelve because of soil and vegetation differences, and (2) are strongly impacted by disturbances such as fire, which can increase runoff, erosion, and actinide transport by more than an order of magnitude. In addition, a laboratory experiment using soil columns was conducted to investigate the vertical transport of contaminants in sandy soils. Nine columns of soil collected from the vicinity of the WIPP site were prepared. The column consisted of a piece of PVC pipe 20 cm

  4. Savannah River Ecology Laboratory Annual Technical Progress Report of Ecological Research, June 30, 2001

    Energy Technology Data Exchange (ETDEWEB)

    Bertsch, Paul M.; Janecek, Laura; Rosier, Brenda

    2001-06-30

    The Savannah River Ecology Laboratory (SREL) is a research unit of the University of Georgia (UGA) and has been conducting ecological research on the Savannah River Site (SRS) in South Carolina for 50 years. The overall mission of the Laboratory is to acquire and communicate knowledge of ecological processes and principles. SREL conducts fundamental and applied ecological research, as well as education and outreach programs, under a Cooperative Agreement with the U.S. Department of Energy (DOE) SRS near Aiken, South Carolina. The Laboratory's research mission during the 2001 fiscal year was fulfilled with the publication of one book and 83 journal articles and book chapters by faculty, technical staff, students, and visiting scientists. An additional 77 journal articles have been submitted or are in press. Other noteworthy events took place as faculty members and graduate students received awards. These are described in the section Special Accomplishments of Faculty, Staff, Students, and Administration on page 54. Notable scientific accomplishments include work conducted on contaminant transport, global reptile decline, phytoremediation, and radioecology. Dr. Domy Adriano authored the second edition of his book ''Trace Elements in Terrestrial Environments: Biogeochemistry, Bioavailability, and Risks of Metals'', which was recently published by Springer-Verlag. The book provides a comprehensive treatment of many important aspects of trace elements in the environment. The first edition of the book, published in 1986, has become a widely acclaimed and cited reference. International attention was focused on the problem of reptile species decline with the publication of an article on this topic in the journal ''Bioscience'' in August, 2000. The article's authors included Dr. Whit Gibbons and a number of other SREL herpetologists who researched the growing worldwide problem of decline of reptile species. Factors related

  5. Final Technical Progress Report Long term risk from actinides in the environment: Modes of mobility

    Energy Technology Data Exchange (ETDEWEB)

    Thomas B. Kirchner

    2002-03-22

    The key source of uncertainty in assessing actinide mobility is the relative importance of transport by: (1) wind erosion, (2) water erosion, and (3) vertical migration. Each of these three processes depends on several environmental factors and they compete with one another. A scientific assessment of the long-term risks associated with actinides in surface soils depends on better quantifying each of these three modes of mobility. The objective from our EMSP study was to quantify the mobility of soil actinides by wind erosion, water erosion, and vertical migration at three semiarid sites where actinide mobility is a key technical, social and legal issue. This EMSP project was the first to evaluate all three factors at a site. The approach has been to investigate both short- and long-term issues based on field and lab studies and model comparisons. Our results demonstrate the importance of incorporating threshold responses into a modeling framework that accounts for environmental factors and natural disturbances that trigger large changes in actinide mobility. The study measured erosional losses of sediment and fallout cesium (an actinide analogue) from field plots located near WIPP in 1998. The results highlight the large effect of burning as a disturbance on contaminant transport and mobility via runoff and erosion. The results show that runoff, erosion, and actinide transport are (1) strongly site specific-differences in radionuclide transport between WIPP and Rocky Flats differed by a factor of twelve because of soil and vegetation differences, and (2) are strongly impacted by disturbances such as fire, which can increase runoff, erosion, and actinide transport by more than an order of magnitude. In addition, a laboratory experiment using soil columns was conducted to investigate the vertical transport of contaminants in sandy soils. Nine columns of soil collected from the vicinity of the WIPP site were prepared. The column consisted of a piece of PVC pipe 20 cm

  6. Research in high energy physics. Annual technical progress report, December 1, 1993--November 30, 1998

    International Nuclear Information System (INIS)

    Olsen, S.L.; Tata, X.

    1996-01-01

    The high energy physics research program at the University of Hawaii is directed toward the study of the properties of the elementary particles and the application of the results of these studies to the understanding of the physical world. Experiments using high energy accelerators are aimed at searching for new particles, testing current theories, and measuring properties of the known particles. Experiments using cosmic rays address particle physics and astrophysical issues. Theoretical physics research evaluates experimental results in the context of existing theories and projects the experimental consequences of proposed new theories

  7. Progress Report on Alloy 617 Notched Specimen Testing

    Energy Technology Data Exchange (ETDEWEB)

    McMurtrey, Michael David [Idaho National Lab. (INL), Idaho Falls, ID (United States); Wright, Richard Neil [Idaho National Lab. (INL), Idaho Falls, ID (United States); Lillo, Thomas Martin [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-08-01

    Creep behavior of Alloy 617 has been extensively characterized to support the development of a draft Code Case to qualify Alloy 617 in Section III division 5 of the ASME Boiler and Pressure Vessel Code. This will allow use of Alloy 617 in construction of nuclear reactor components at elevated temperatures and longer periods of time (up to 950°C and 100,000 hours). Prior to actual use, additional concerns not considered in the ASME code need to be addressed. Code Cases are based largely on uniaxial testing of smooth gage specimens. In service conditions, components will generally be under multi axial loading. There is also the concern of the behavior at discontinuities, such as threaded components. To address the concerns of multi axial creep behavior and at geometric discontinuities, notched specimens have been designed to create conditions representative of the states that service components experience. Two general notch geometries have been used for these series of tests: U notch and V notch specimens. The notches produce a tri axial stress state, though not uniform across the specimen. Characterization of the creep behavior of the U notch specimens and the creep rupture behavior of the V notch specimens provides a good approximation of the behavior expected of actual components. Preliminary testing and analysis have been completed and are reported in this document. This includes results from V notch specimens tested at 900°C and 800°C. Failure occurred in the smooth gage section of the specimen rather than at the root of the notch, though some damage was present at the root of the notch, where initial stress was highest. This indicates notch strengthening behavior in this material at these temperatures.

  8. Biomass power for rural development. Technical progress report, October 1--December 31, 1997

    Energy Technology Data Exchange (ETDEWEB)

    Neuhauser, E.

    1998-05-01

    The focus of the DOE/USDA sponsored biomass power for rural development project is to develop commercial energy crops for power generation by the year 2000. The New York based Salix Consortium project is a multi-partner endeavor, implemented in three stages. Phase-1, Final Design and Project Development, will conclude with the preparation of construction and/or operating permits, feedstock production plans, and contracts ready for signature. Field trials of willow (Salix) have been initiated at several locations in New York (Tully, Lockport, King Ferry, La Fayette, Massena, and Himrod) and co-firing tests are underway at Greenidge Station (NYSEG) and Dunkirk Station (NMPC). Phase-2 of the project will focus on scale-up of willow crop acreage, construction of co-firing facilities at Dunkirk Station (NMPC), and final modifications for Greenidge Station. Cofiring willow is also under consideration for GPU`s Seward Station where testing is underway. There will be an evaluation of the energy crop as part of the gasification trials occurring at BED`s McNeill Power Station. Phase-3 will represent fullscale commercialization of the energy crop and power generation on a sustainable basis. During the fourth quarter of 1997 the Consortium submitted a Phase-2 proposal. A few of the other more important milestones are outlined below. The first quarter of 1998 will be dominated by pre-planting activity in the spring.

  9. Second progress report on pre-test calculations for the large block test

    International Nuclear Information System (INIS)

    Lee, K.H.

    1995-01-01

    The US Department of Energy's (DOE) Yucca Mountain Site Characterization Project (YMP) is investigating the suitability of the Topopah Spring tuff in the thick vadose zone at Yucca Mountain, Nevada, as a host rock for permanent disposal of high-level radioactive waste. As part of the YMP, a group of field tests, called the Large Block Test (LBT), will be conducted on a large electrically heated block of Topopah Spring tuff. The block will be heated by electrical heaters. The goals of the LBT are to gain information on the coupled thermal-mechanical-hydrological-chemical processes that will be active in the near-field environment of a repository; to provide field data for testing and calibrating models; and to help in the development of measurement systems and techniques. In this second progress report, we present results of the final set of numerical modeling calculations performed in support of the LBT design. The results include block temperatures and heat fluxes across the surfaces. The results are applied primarily to the design of guard heaters to enforce adiabatic conditions along the block walls. Conduction-only runs are adequate to estimate the thermal behavior of the system, because earlier calculations showed that heat transfer in the block is expected to be dominated by conduction. In addition, conduction-only runs can be made at substantially shorter execution times than full hydrothermal runs. We also run a two-dimensional, hydrothermal, discrete fracture model, with 200-μm vertical fractures parallel to the heaters and occurring at a uniform spacing of 30 cm. The results show the development of distinct dryout and recondensation zones. The dryout zones are thickest at the fractures and thinnest in the matrix midway between the fractures

  10. Optimal design and routing of power lines; ecological, technical and economic perspectives (OPTIPOL). Progress report 2012

    Energy Technology Data Exchange (ETDEWEB)

    Bevanger, Kjetil; Bartzke, Gundula; Broeseth, Henrik; Dahl, Espen Lie; Gjershaug, Jan Ove; Hanssen, Frank; Jacobsen, Karl-Otto; Kleven, Oddmund; Kvaloey, Paal; May, Roel; Meaas, Roger; Nygaaard, Torgeir; Resnaes, Steinar; Stokke, Sigbjoern; Thomassen, Joern

    2012-07-01

    birds in the database, compared to only 117 a year earlier. WP5 - 'A Least Cost Path (LCP) toolbox for optimal route routing of power lines', has developed an LCP-pilot to demonstrate the LCP method, based on the impact studies were undertaken prior to construction of a 420 kV transmission line in Central Norway 2005. Relevant economic, ecological and technological environment criteria based on suggestions from interested users (NGOs, government, industry, etc.), was used. LCP-pilot and a fuzzy-logic approach of this was demonstrated in the first dialogue-based workshop, 23.-24. april 2012. The seminar, which had an emphasis on criteria definitions were followed up with a working seminar that focused criterion values ??on 20 november 2012. Lecture - 'A Least Cost Path (LCP) Toolbox for Optimal Routing of Power Lines, -was presented and submitted as contributions to the conference report from 'The 10th ROW Conference' in Arizona, 'The 32nd Annual Conference of the International Association for Impact Assessment (IAIA12) ' in Porto, Portugal, and 'The ESRI European User Conference' in Oslo. WP6 - 'Birds and camouflaging of power lines', has almost completed the final report, 'Power line camouflaging. An assessment of the ecological and technical challenges'. 'Because of the budget situation in CEDREN However, completion of the report postponed until the end of April 2013. WP7 - 'Effect of line marking / modifications remedial measures against bird mortality' has almost completed the final report 'Opportunities and limitations in terms of reducing mortality in birds due to collision and electrocution.' Due to overall budget situation in CEDREN the report deferred to the end of april 2013. WP8, 'guidelines for technological solutions that may reduce mortality in birds because of the power line's', has focused topics relating to the labeling, design, insulation, camouflage and wiring. The results, which are presented in the notes and articles, will be implemented in

  11. Research in elementary particle physics: Technical progress report, June 1, 1986-May 31, 1987

    International Nuclear Information System (INIS)

    Kirsch, L.E.; Schnitzer, H.J.; Abbott, L.F.; Bensinger, J.R.; Blocker, C.A.

    1987-01-01

    Work is reported in the areas of: design, construction, and testing of components of the CDF, including shower counters, electronics, and electron identification algorithms; contributions to the design and construction of the Brookhaven MultiParticle Spectrometer; search for charm and K*'s and baryonium; measurement of differential cross section and polarization in the Lambda-antiLambda channel; a study of Xi states which measured the Xi asymmetry parameter; and dibaryon searches using the Brookhaven Hypernuclear Spectrometer. Theoretical efforts are reported in the areas of string theory, the Skyrme model applied to elementary particle phenomenology, quantum field theory, cosmology, galaxy formation, supernova 187A, field theory in curved space-times, and spin-glasses

  12. Cooperative research in coal liquefaction. Technical progress report, May 1, 1993--April 30, 1994

    Energy Technology Data Exchange (ETDEWEB)

    Huffman, G.P. [ed.

    1994-10-01

    Accomplishments for the past year are presented for the following tasks: coliquefaction of coal with waste materials; catalysts for coal liquefaction to clean transportation fuels; fundamental research in coal liquefaction; and in situ analytical techniques for coal liquefaction and coal liquefaction catalysts some of the highlights are: very promising results have been obtained from the liquefaction of plastics, rubber tires, paper and other wastes, and the coliquefaction of wastes with coal; a number of water soluble coal liquefaction catalysts, iron, cobalt, nickel and molybdenum, have been comparatively tested; mossbauer spectroscopy, XAFS spectroscopy, TEM and XPS have been used to characterize a variety of catalysts and other samples from numerous consortium and DOE liquefaction projects and in situ ESR measurements of the free radical density have been conducted at temperatures from 100 to 600{degrees}C and H{sub 2} pressures up to 600 psi.

  13. Collisional dynamics of perturbed particle disks in the solar system. Annual technical progress report

    International Nuclear Information System (INIS)

    Roberts, W.W.; Stewart, G.R.

    1987-03-01

    Investigations of the collisional evolution of particulate disks subject to the gravitational perturbation of a more massive particle orbiting within the disk are underway. Both numerical N-body simulations using a novel collision algorithm and analytical kinetic theory are being employed to extend our understanding of perturbed disks in planetary rings and during the formation of the solar system. Particular problems proposed for investigation are: (1) The development and testing of general criteria for a small moonlet to clear a gap and produce observable morphological features in planetary rings; (2) The development of detailed models of collisional damping of the wavy edges observed on the Encke division of Saturn's A ring; and (3) The determination of the extent of runaway growth of the few largest planetesimals during the early stages of planetary accretion

  14. Technical support for open-cycle MHD program. Progress report, July--December 1978

    Energy Technology Data Exchange (ETDEWEB)

    Doss, E D [ed.

    1979-06-01

    The support program for open-cycle MHD at Argonne National Laboratory is developing the analytical tools needed to investigate the performance of the major components in the combined cycle MHD/steam power system. The analytical effort is centered on the primary components of the system that are unique to MHD and also on the integration of these analytical representations into a model of the entire power producing system. The present project activities include modeling of the combustor, MHD channel, slag separator, and high-temperature air heater. In addition, these models are combined into a complete system model, which is at present capable of carrying out optimizations of the entire system relative to either thermodynamic efficiency or cost of electrical power. Also, in support of other aspects of the open-cycle program, test plans are developed and facility and program reviews are provided upon request in support of the needs and requirements of the DOE/MHD Division.

  15. Investigation of hadronic matter at the Fermilab Tevatron Collider. Technical progress report

    International Nuclear Information System (INIS)

    Anderson, E.W.

    1985-01-01

    Hadronic matter at very high energy densities is investigated. The present experimental effort is focused on a search for a new quark-gluon plasma phase expected to occur when temperatures of 240 MeV are achieved. Instrumentation for several unique signatures is being developed to exploit the first operation of the Fermilab Tevatron Collider in 1986. The capital projects funded under this contract are a 240-element trigger hodoscope array, and in phase II a segmented photon detector. For these projects $172K are requested for the period 1986 February 1 through 1987 January 31 to complete the trigger hodoscope, and $160K for the period 1987 February 1 through 1988 January 31 to construct a portion of the photon detector. These figures are as presented in the original proposal. Due to budget constraints on the Fermilab experimental support program, we will not be able to receive the full complement of necessary electronics from the Fermilab PREP pool in the required period. Consequently, an additional $35K is requested for the period 1986 February 1 through 1987 January 31 for a portion of the electronics for the 240-channel trigger hodoscope. For the same reasons, Fermilab cannot provide the required magnet on schedule; a one year delay is proposed. As this would seriously impact our physics goals, the collaboration is attempting to fund the magnet without delay through the universities. Efforts to date have concentrated on the design and testing of the hodoscope. Extensive measurements on the radiation levels and effects during the various accelerator cycles have been made. These data are essential to the proper selection of scintillator and design of electronics. These tests are now complete, and final construction is beginning. 11 refs

  16. Progress in Developing Finite Element Models Replicating Flexural Graphite Testing

    International Nuclear Information System (INIS)

    Bratton, Robert

    2010-01-01

    This report documents the status of flexural strength evaluations from current ASTM procedures and of developing finite element models predicting the probability of failure. This work is covered under QLD REC-00030. Flexural testing procedures of the American Society for Testing and Materials (ASTM) assume a linear elastic material that has the same moduli for tension and compression. Contrary to this assumption, graphite is known to have different moduli for tension and compression. A finite element model was developed and demonstrated that accounts for the difference in moduli tension and compression. Brittle materials such as graphite exhibit significant scatter in tensile strength, so probabilistic design approaches must be used when designing components fabricated from brittle materials. ASTM procedures predicting probability of failure in ceramics were compared to methods from the current version of the ASME graphite core components rules predicting probability of failure. Using the ASTM procedures yields failure curves at lower applied forces than the ASME rules. A journal paper was published in the Journal of Nuclear Engineering and Design exploring the statistical models of fracture in graphite.

  17. Development of Integral Effect Test Facility P and ID and Technical Specification for SMART Fluid System

    International Nuclear Information System (INIS)

    Lee, Sang Il; Jung, Y. H.; Yang, H. J.; Song, S. Y.; Han, O. J.; Lee, B. J.; Kim, Y. A.; Lim, J. H.; Park, K. W.; Kim, N. G.

    2010-01-01

    SMART integral test loop is the thermal hydraulic test facility with a high pressure and temperature for simulating the major systems of the prototype reactor, SMART-330. The objective of this project is to conduct the basic design for constructing SMART ITL. The major results of this project include a series of design documents, technical specifications and P and ID. The results can be used as the fundamental materials for making the detailed design which is essential for manufacturing and installing SMART ITL

  18. Validity of GRE General Test scores and TOEFL scores for graduate admission to a technical university in Western Europe

    Science.gov (United States)

    Zimmermann, Judith; von Davier, Alina A.; Buhmann, Joachim M.; Heinimann, Hans R.

    2018-01-01

    Graduate admission has become a critical process in tertiary education, whereby selecting valid admissions instruments is key. This study assessed the validity of Graduate Record Examination (GRE) General Test scores for admission to Master's programmes at a technical university in Europe. We investigated the indicative value of GRE scores for the Master's programme grade point average (GGPA) with and without the addition of the undergraduate GPA (UGPA) and the TOEFL score, and of GRE scores for study completion and Master's thesis performance. GRE scores explained 20% of the variation in the GGPA, while additional 7% were explained by the TOEFL score and 3% by the UGPA. Contrary to common belief, the GRE quantitative reasoning score showed only little explanatory power. GRE scores were also weakly related to study progress but not to thesis performance. Nevertheless, GRE and TOEFL scores were found to be sensible admissions instruments. Rigorous methodology was used to obtain highly reliable results.

  19. Biomass power for rural development: Phase 2. Technical progress report, April 1--June 30, 1998

    Energy Technology Data Exchange (ETDEWEB)

    Neuhauser, E.

    1998-11-01

    The project undertaken by the Salix Consortium is a multi-phased, multi-partner endeavor. Phase-1 focused on initial development and testing of the technology and agreements necessary to demonstrate commercial willow production in Phase-2. The Phase-1 objectives have been successfully completed: preparing final design plans for two utility pulverized coal boilers, developing fuel supply plans for the project, obtaining power production commitments from the power companies for Phase-2, obtaining construction and environmental permits, and developing an experimental strategy for crop production and power generation improvements needed to assure commercial success. The R and D effort also addresses environmental issues pertaining to introduction of the willow energy system. Beyond those Phase-1 requirements the Consortium has already successfully demonstrated cofiring at Greenidge Station and developed the required nursery capacity for acreage scale-up. This past summer 105 acres were prepared in advance for the spring planting in 1998. Having completed the above tasks, the Consortium is well positioned to begin Phase-2. In phase-2 every aspect of willow production and power generation from willow will be demonstrated. The ultimate objective of Phase-2 is to transition the work performed under the Rural Energy for the Future project into a thriving, self-supported energy crop enterprise.

  20. [Experimental research in high energy physics: Final technical progress report, 1986--1992

    International Nuclear Information System (INIS)

    1992-01-01

    This is the closeout report for DOE supported research in high energy physics for the period 1986--1992, under contract award AT03-86ER40249 at the Santa Cruz Institute for Particle Physics (SCIPP) at U.C. Santa Cruz. The research during this period consisted primarily of the following: Data taking with the MARK II detector at the SLC at SLAC and construction of a silicon vertex detector for the MARK II. This effort included substantial work on commissioning of the SLC accelerator. Preparation of the SLD experiment for the SLC, and initial data taking with this experiment. Participation in the ALEPH physics program at LEP at CERN in Geneva, with an emphasis on its silicon vertex detector. Analysis of data collected with the MARK III experiment at the SPEAR accelerator at SLAC. Electronics development for the leading proton spectrometer for the ZEUS experiment at DESY in Hamburg. Design, testing and physics studies for a silicon tracker for the SSC. Theoretical physics program emphasizing phenomenology, Higgs physics, supersymmetry, and some issues in cosmology

  1. Indiana University high energy physics, Task A: Technical progress report, December 1, 1987-November 30, 1988

    International Nuclear Information System (INIS)

    Brabson, B.B.; Crittenden, R.R.; Dzierba, A.R.; Martin, H.J.; Ogren, H.O.; Zieminski, A.

    1988-01-01

    This year at Brookhaven data from last year's run on the production of the KKπ system by π's, K's and antiprotons was analyzed. Analysis of the Fermilab fixed-target jet experiment, E557, resulted in 3 publications. In addition two conference contributions were prepared and a third paper will be written. Otherwise E557 is finished. A dimuon detector for E672 was installed and tested. This took place in early 1987. Data were from June, 1987 to February, 1988. Some 800 tapes of triggers (about 10K/tape) are in hand with data from both the E672 and E706 apparatus. We participated in the coordination and writing of software for the D0 collider detector at Fermilab. We will be increasing our efforts in D0. Data-taking with the High-Resolution Spectrometer (HRS) at SLAC is completed. This year 12 publications resulted. More are in preparation. Hardware was built for the muon upgrade for the Mark2 detector at the SLC. Beam position monitors for the SLC are being built and also working on 308/E microprocessors for Mark2 data analysis. At SLAC we are also involved in the SLC Polarization Collaboration

  2. Nondestructive Examination (NDE) Detection and Characterization of Degradation Precursors, Technical Progress Report for FY 2012

    Energy Technology Data Exchange (ETDEWEB)

    Ramuhalli, P.; Meyer, R.M.; Fricke, J.M.; Prowant, M.S.; Coble, J.B.; Griffin, J.W.; Pitman, S.G.; Dahl, M.E.; Kafentzis, T.A.; Roosendaal, T.J.

    2012-09-01

    The overall objective of this project was to investigate the effectiveness of nondestructive examination (NDE) technology in detecting material degradation precursors by initiating and growing cracks in selected materials and using NDE methods to measure crack precursors prior to the onset of cracking. Nuclear reactor components are subject to stresses over time that are not precisely known and that make the life expectancy of components difficult to determine. To prevent future issues with the operation of these plants because of unforeseen failure of components, NDE technology is needed that can be used to identify and quantify precursors to macroscopic degradation of materials. Some of the NDE methods being researched as possible solutions to the precursor detection problem are magnetic Barkhausen noise, nonlinear ultrasonics, acoustic emission, eddy current measurements, and guided wave technology. In FY12, the objective was to complete preliminary assessment of advanced NDE techniques for sensitivity to degradation precursors, using prototypical degradation mechanisms in laboratory-scale measurements. This present document reports on the deliverable that meets the following milestone: M3LW-12OR0402143 – Report detailing an initial demonstration on samples from the crack-initiation tests will be provided (demonstrating acceleration of the work).

  3. Design, Fabrication, and Certification of Advanced Modular PV Power Systems Final Technical Progress Report

    International Nuclear Information System (INIS)

    Minyard, G.

    1998-01-01

    This report describes the overall accomplishments and benefits of Solar Electric Specialties Co. (SES) under this Photovoltaic Manufacturing Technology (PVMaT) subcontract. SES addressed design issues related to their modular autonomous PV power supply (MAPPS) and a mobile photogenset. MAPPS investigations included gel-cell batteries mounted horizontally; redisgn of the SES power supply; modified battery enclosure for increased safety and reduced cost; programmable, interactive battery charge controllers; and UL and FM listings. The photogenset systems incorporate generators, battery storage, and PV panels for a mobile power supply. The unit includes automatic oil-change systems for the propane generators, collapsible array mounts for the PV enclosure, and internal stowage of the arrays. Standardizing the products resulted in product lines of MAPPS and Photogensets that can be produced more economically and with shorter lead times, while increasing product quality and reliability. Product assembly and quality control have also been improved and streamlined with the development of standardized assembly processes and QC testing procedures. SES offers the UL-listed MAPPS at about the same price as its previous non-standardized, unlisted products

  4. Investigation of hadronic matter at the Fermilab Tevatron Collider: Technical progress report, 1986 October-1987 October

    International Nuclear Information System (INIS)

    Anderson, E.W.

    1987-01-01

    An investigation of hadronic matter at very high energy densities is reported. The present experiment, E-735, is a search for a deconfined quark-gluon plasma phase of matter expected to occur when temperatures of 240 MeV are achieved. Preliminary data have been obtained during the first operation of the Fermilab Tevatron Collider during the period January to May 1987. The collaboration is about to publish first results on the charged particle multiplicity and transverse momentum distributions. In addition, we have data on the particle identification of the produced secondaries. Both measurements are regarded on theoretical grounds to be sensitive indicators of the formation of a high temperature plasma. The capital project funded under this contract was a 240-element trigger hodoscope array, with associated electronics and monitor. The hodoscope was completed and performed to design expectations in the high-rate and high-radiation environment of the Collider. Scientific personnel supported under this contract were also responsible for the implementation of the data acquisition system used for E-735. Although the system underwent several unanticipated modifications in response to changing schedules, the required service was provided. Preparations are currently under way for the principal data acquisition during the spring of 1988. At that time we will have in place the central tracking chamber, and the remainder of the spectrometer chambers. Tests will also be made on backgrounds and detector materials appropriate to our proposal, P-787, to measure leptons and photons in the third Collider running period

  5. Biomass power for rural development. Technical progress report, Phase 2, July 1--September 30, 1998

    Energy Technology Data Exchange (ETDEWEB)

    Neuhauser, E.

    1999-01-01

    The project undertaken by the Salix Consortium is a multi-phased, multi-partner endeavor. Phase 1 focused on initial development and testing of the technology and forging the necessary agreements to demonstrate commercial willow production. The Phase 1 objectives have been successfully completed: preparing final design plans for two utility pulverized coal boiler for 20 MW of biopower capacity; developing fuel supply plans for the project with a goal of establishing 365 ha (900 ac) of willow; obtaining power production commitments from the power companies for Phase 2; obtaining construction and environmental permits; and developing an experimental strategy for crop production and power generation improvements needed to assure commercial success. The R and D effort also addresses environmental issues pertaining to introduction of the willow energy system. Beyond those Phase 1 requirements, the Consortium has already successfully demonstrated cofiring at Greenidge Station and has initiated development of the required nursery capacity for acreage scale-up. In Phase 2 every aspect of willow production and power generation from willow biomass will be demonstrated. The ultimate objective of Phase 2 is to transition the work performed under the Biomass Power for Rural Development project into a thriving, self-supported energy crop enterprise.

  6. Continuous Fiber Wound Ceramic Composite (CFCC) for Commercial Water Reactor Fuel. Technical progress report for period ending April 1, 2000

    International Nuclear Information System (INIS)

    2000-01-01

    Our program began on August 1, 1999. As of April 1, 2000, the progress has been in materials selection and test planning. Three subcontracts are in place (McDermott Technologies Inc. for continuous fiber reinforced ceramic tubing fabrication, Swales Aerospace for LOCA testing of tubes, and Massachusetts Institute of Technology for In Reactor testing of tubes). With regard to materials selection we visited McDermott Technologies Inc. a number of times, including on February 23, 2000 to discuss the Draft Material Selection and Fabrication Report. The changes discussed at this meeting were implemented and the final version of this report is attached (attachment 1). McDermott Technologies Inc. will produce one type of tubing: Alumina oxide (Nextel 610) fiber, a carbon coating (left in place), and alumina-yttria matrix. A potentially desirable CFCC material of silicon carbide fiber with spinel matrix was discussed. That material selection was not adopted primarily due to material availability and cost. Gamma Engineering is exploring the available tube coatings at Northwestern University as a mechanism for reducing the permeability of the tubes, and thus, will use coating as a differentiating factor in the testing of tubing in the LOCA test as well as the In-Reactor Test. The conclusion of the Material Selection and Fabrication Report lists the possible coatings under evaluation. With regard to Test Planning, the MIT and Swales Aerospace have submitted draft Test Plans. MIT is attempting to accommodate an increased number of test specimens by evaluating alternative test configurations. Swales Aerospace held a design review at their facilities on February 24, 2000 and various engineering alternatives and safety issues were addressed. The final Test Plans are not expected until just before testing begins to allow for incorporation of changes during ''dry runs.''

  7. The status of the technical development for the Yamanashi Maglev test line

    Energy Technology Data Exchange (ETDEWEB)

    Nakashima, Hiroshi [Maglev Systems Development Dept., Railway Technical Research Inst., Tokyo (Japan); Seki, Akio [Linear Express Research Development Div., Central Japan Railway Co. Ltd., Tokyo (Japan)

    1996-12-31

    The superconducting maglev system has been under development for the past 25 years in Japan. In last 17 years, running test on the 7 km Miyazaki test track has yielded important data for the maglev system development. In 1990, the maglev system gained the status of one of the national - funded projects in Japan. The government authorized the 42.8 km test line in Yamanashi Prefecture and R and D entered into a new phase. This new test line is planned to go through near Tokyo on the supposed Chuo line, which is expected to be a new important line connecting Tokyo and Osaka, the central part of Japan. This fact clearly explains the role of Yamanashi test line in the future. The construction of the Yamanashi test line is energetically promoted, to start running tests in spring of 1997. The situation of the technical development of the Yamanashi test line is reviewed here. (orig.)

  8. Technical critique on radiation test facilities for the CTR surface and materials program

    International Nuclear Information System (INIS)

    Persiani, P.J.

    1975-02-01

    Major radiation test facilities will be necessary in the near-term (5 years) and long-term (greater than 10 years) future for the timely development and understanding of fusion confinement systems and of prototype fusion power reactors. The study includes the technical justifications and requirements for CTR Neutron and Plasma Radiation Test Facilities. The initial technical critique covers the feasibility and design problems: in upgrading the performance of the accelerator-rotating (solid TiT) target systems, and in transforming the accelerator-supersonic jet target concept into a radiation testing facility. A scoping assessment on the potential of a pulsed high-beta plasma device (dense plasma focus) is introduced to explore plasma concepts as near-term neutron and plasma radiation sources for the CTR Surface and Materials Program. (U.S.)

  9. Around Semipalatinsk nuclear test site: Progress of dose estimations relevant to the consequences of nuclear tests

    International Nuclear Information System (INIS)

    Stepanenko, Valeriy F.; Hoshi, Masaharu; Bailiff, Ian K.

    2006-01-01

    The paper is an analytical overview of the main results presented at the 3rd Dosimetry Workshop in Hiroshima (9-11 of March 2005), where different aspects of the dose reconstruction around the Semipalatinsk nuclear test site (SNTS) were discussed and summarized. The results of the international intercomparison of the retrospective luminescence dosimetry (RLD) method for Dolon' village (Kazakhstan) were presented at the Workshop and good concurrence between dose estimations by different laboratories from 6 countries (Japan, Russia, USA, Germany, Finland and UK) was pointed out. The accumulated dose values in brick for a common depth of 10 mm depth of 10 mm depth obtained independently by all participating laboratories were in good agreement for all four brick samples from Dolon' village, Kazakhstan, with the average value of the local gamma dose due to fallout (near the sampling locations) being about 220 mGy (background dose has been subtracted). Furthermore, using a conversion factor of about 2 to obtain the free-in-air dose, a value of local dose ∼440 mGy is obtained, which supports the results of external dose calculations for Dolon': recently published soil contamination data, archive information and new models were used for refining dose calculations and the external dose in air for Dolon village was estimated to be about 500 mGy. The results of electron spin resonance (ESR) dosimetry with tooth enamel have demonstrated the notable progress in application of ESR dosimetry to the problems of dose reconstruction around the Semipalatinsk nuclear test site. At the present moment, dose estimates by the ESR method have become more consistent with calculated values and with retrospective luminescence dosimetry data, but differences between ESR dose estimates and RLD/calculation data were noted. For example mean ESR dose for eligible tooth samples from Dolon' village was estimated to be about 140 mGy (above background dose), which is less than dose values obtained

  10. Feed-in tariffs versus quotas: how to promote renewable s and stimulate technical progress for cost decrease?

    International Nuclear Information System (INIS)

    Menanteau, Ph.; Finon, D.; Lamy, M.L.

    2002-01-01

    Incentive schemes for the development of renewable energy sources may focus on quantities (defining national targets and setting up bidding systems, or quota systems providing for green certificate trading), or they may focus on prices (feed-in tariffs). Whatever the system chosen, the role of the public authorities is quite specific: to stimulate technical progress and speed up the technological learning processes so that ultimately renewable energy technologies will be able to compete with conventional technologies, once the environmental costs have been internalized. A comparison of instruments must thus take into account the characteristics of the innovation process and adoption conditions (uncertainties regarding cost curves, learning effects) which means also looking at dynamic efficiency criteria. The paper concludes that a system of feed-in tariffs is more efficient than a bidding system, but highlights the theoretical interest of green certificate trading which must be confirmed through practice, given the influence of market structures and rules on the performance of this type of approach. (author)

  11. Comparing technical proficiency of elite table tennis players with intellectual disability: simulation testing versus game play.

    Science.gov (United States)

    Van Biesen, Debbie; Mactavish, Jennifer J; Vanlandewijck, Yves C

    2014-04-01

    Technical skill proficiency among elite table tennis players with intellectual disabilities (ID) was investigated in this study using two approaches: an off-court simulation testing protocol and an on-court, standardized observational framework during game play. Participants included 24 players with ID (M age = 25 yr., SD = 6; M IQ = 61, SD = 9), the top 16 performers, 13 men and 11 women, at the International Federation for sport for para-athletes with an intellectual disability (Inas) World Championships. Self-reported table tennis training experience of the players was 13 +/- 5 yr. In the Simulation Testing condition, players were instructed to play five sets of basic and five sets of advanced skills, which were subsequently assessed by experts using a standardized and validated observational protocol. The same protocol was used to assess the same skills during Game Play. Ratings of overall technical proficiency were not significantly different between Simulation Testing and Game Play conditions. There was a strong positive correlation between technical proficiency measured during Game Play vs Simulation Testing for the variables flick, topspin forehand, and topspin backhand. No correlations were found for the variables contra, block, and push. Insight into this relationship is important for future development of classification systems for ID athletes in the Paralympic Games, because comparing competition observation with the athlete's potential shown during the classification session is essential information for classifiers to confirm the athlete's competition class.

  12. Technical progress report

    International Nuclear Information System (INIS)

    1982-01-01

    This report summarizes the work carried out by personnel at the Nuclear Physics Laboratory of the University of Colorado from about August 1, 1981 to October 1, 1982, under contract with the Department of Energy. The intermediate energy studies summarized in this report were carried out at the meson physics facilities at Los Alamos (LAMPF), the cyclotron at Indiana University (IUCF), and the meson physics facilities at Vancouver (TRIUMF). This year, for the first time, intermediate energy experimental studies are being reported in separate documents from the low energy and theoretical nuclear physics efforts. Experimental studies are reported on pion-nucleus interactions, charge exchange reactions, nucleon transfer reactions, and apparatus development

  13. 1996 technical progress report

    International Nuclear Information System (INIS)

    1997-01-01

    Summaries of the researches are grouped into programs as follows: research and development in food and agriculture; research and development in health, environment and industry which includes all the PNRI research projects in 1996; scientific and technological services; and the nuclear regulations, licensing and safeguards of the institute

  14. 1997 technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    This report presents the on-going research and development projects of the Philippine Nuclear Research Institute (PNRI) in the fields of agriculture, environment and industry, scientific and technological services and nuclear regulations, licensing and safeguards.

  15. Annual technical progress report

    International Nuclear Information System (INIS)

    1980-01-01

    During the present contract period Phaedrus has begun operation as a true tandem mirror. This was accomplished by achieving the rf sustained mode in which the plug densities were built up by a combination of central cell gas puffing and plug ICRH following stream gun turn off. It was demonstrated that the tandem mirror plasma could be sustained by plug ICRH for up to 1 msec following decay of the external plasma. In this mode plasma characteristics were no longer dominated by problems associated with a high conductivity stream gun plasma in the external region (as was the case in many previous experiments in Phaedrus). Among these problems were (1) line tying which significantly reduced instabilities in a way that would not apply to reactors and (2) low electron temperatures which had been held to approx. 20 eV

  16. 1999 technical progress report

    International Nuclear Information System (INIS)

    2000-01-01

    This report presents the on-going research and development projects of the Philippine Nuclear Research Institute (PNRI) in the fields of agriculture, environment and industry, scientific and technological services and nuclear regulations, licensing and safeguards

  17. 1999 technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    This report presents the on-going research and development projects of the Philippine Nuclear Research Institute (PNRI) in the fields of agriculture, environment and industry, scientific and technological services and nuclear regulations, licensing and safeguards.

  18. 1996 technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

    Summaries of the researches are grouped into programs as follows: research and development in food and agriculture; research and development in health, environment and industry which includes all the PNRI research projects in 1996; scientific and technological services; and the nuclear regulations, licensing and safeguards of the institute.

  19. 1997 technical progress report

    International Nuclear Information System (INIS)

    1998-01-01

    This report presents the on-going research and development projects of the Philippine Nuclear Research Institute (PNRI) in the fields of agriculture, environment and industry, scientific and technological services and nuclear regulations, licensing and safeguards

  20. 1995 technical progress report

    International Nuclear Information System (INIS)

    1997-01-01

    Summaries of the researches are grouped into programs as follows: research and development which covers all the PNRI research projects in 1994; scientific and technological services; and the nuclear regulations, licensing and safeguards of the institute

  1. Technical Progress Report

    International Nuclear Information System (INIS)

    Engelhardt, G.R.; MacDonald, D.D.

    1999-01-01

    During the past quartile (two month period) most attention has been concentrated on the problem of definition critical temperature at which ''wet'' corrosion first became operable. It has been shown that, in principle, ''wet'' corrosion processes can not be ignored for Yucca Mountain, even for initial times, when the temperature of the surface of containers is well above the boiling temperature of water for the prevailing conditions. This is because the surfaces are covered by highly hydrophilic oxides (e.g. Fe 2 O 3 , NiO, Cr 2 O 3 ) that will hydrate to the form of corresponding hydroxides, which are proton conductors, at least when in the ''wet'' condition. Because proton conduction and the presence of ''bound'' water are all that are required for the external environment to support metallic corrosion in either its general or localized form. Thus, the temperature of dehydration of the hydroxide, e.g. M(OH) 2 → MO + H 2 O(g), is a better criterion for the upper temperature limit for ''wet'' corrosion than is the boiling temperature of ''bulk'' water. During this first task, we have reviewed the existing thermodynamic data base for the dehydration of metal hydroxides and analytical expressions have been developed that allow the upper temperature limit to be estimated

  2. Data Link Test and Analysis System/ATCRBS Transponder Test System Technical Reference

    Science.gov (United States)

    1990-05-01

    This document references material for personnel using or making software changes : to the Data Link Test and Analysis System (DATAS) for Air Traffic Control Radar : Beacon System (ATCRBS) transponder testing and data collection. This is one of : a se...

  3. Domestic activity for technical development of the APR1400's RCP performance test

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Seok; Kim, Seok; Bae, Byung-Uhn; Cho, Yun-Jae; Kim, Yeon-Sik; Jeon, Woo-Jin; Yun, Young-Jung [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The thermal hydraulic and electric capability of the RCP test facility (RCPTF) covers up to 18.5 MPa, 343 .deg. C, 11.7 m{sup 3}/s, and 14.0 MW in the design pressure, temperature, flow rate, and the maximum electric power, respectively. In 2013, commissioning test had been performed to verify its designed capability, followed by several modifications in the RCPTF including signal processing and control logic to enhance verification and evaluation capability of the RCP performance. After finishing the commissioning and modification of the RCPTF, type test for the new-type RCP had been performed successfully. In this paper, several technical issues developed in the 2013 and the type test's method and results will be described. In the present paper, the technical activities for the development of the verification test of APR1400's RCP are described. KAERI has completed the full set of technology development, prerequisite for the RCP verification test, and now on the way to perform a test for the sealing capacity of the seal assembly during the Station Block Out (SBO) condition of APR1400.

  4. Spent fuel test - Climax: technical measurements. Interim report, fiscal year 1981

    International Nuclear Information System (INIS)

    Patrick, W.C.; Ballou, L.B.; Butkovich, T.R.

    1982-01-01

    The Spent Fuel Test-Climax (SFT-C) is located 420 m below surface in the Climax granite stock on the Nevada Test Site. Eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized from April to May 1980, initiating the 3- to 5-year-duration test. The SFT-C operational objective of demonstrating the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner has been met. Technical objectives of the test led to development of a technical measurements program, which is the subject of this report. Geotechnical, seismological, and test status data have been recorded on a continuing basis for the first 1-1/2 years of the test on more than 900 channels. Much of the acquired data are now available for analysis and are presented here. Highlights of activities this year include completion of site characterization field work, major modifications to the data acquisition and the management systems, and the addition of instrument evaluation as an explicit objective of the test

  5. Spent fuel test - Climax: technical measurements. Interim report, fiscal year 1981

    Energy Technology Data Exchange (ETDEWEB)

    Patrick, W.C.; Ballou, L.B.; Butkovich, T.R.

    1982-04-30

    The Spent Fuel Test-Climax (SFT-C) is located 420 m below surface in the Climax granite stock on the Nevada Test Site. Eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized from April to May 1980, initiating the 3- to 5-year-duration test. The SFT-C operational objective of demonstrating the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner has been met. Technical objectives of the test led to development of a technical measurements program, which is the subject of this report. Geotechnical, seismological, and test status data have been recorded on a continuing basis for the first 1-1/2 years of the test on more than 900 channels. Much of the acquired data are now available for analysis and are presented here. Highlights of activities this year include completion of site characterization field work, major modifications to the data acquisition and the management systems, and the addition of instrument evaluation as an explicit objective of the test.

  6. ATTILA 2 S. A technical and interactive test language for architecture allowing simultaneity

    International Nuclear Information System (INIS)

    Batllo, M.

    1980-01-01

    The name ATTILA 2 S is inspired from ATLAS, test language adopted by the Department of Defence of America (D.O.D.) but cannot be implemented on our installation. ATTILA 2 S is principally characterized by: its technical vocabulary (P.O.L.), its interactivity, its simultaneity with main job (Multiprogramming and Multiprocessing allowed by multiprocessors architecture. This language has been developed for the Paris C.R.T. system (Photographies analysis system) on Control Data Cyber 72 computer [fr

  7. Progression of carpal tunnel syndrome according to electrodiagnostic testing in nonoperatively treated patients

    NARCIS (Netherlands)

    van Suchtelen, Mark; Becker, Stéphanie J. E.; Gruber, Jillian S.; Ring, David

    2014-01-01

    This study tested the null hypothesis that nonoperatively treated patients would not show disease progression of carpal tunnel syndrome (CTS) over time according to median nerve distal motor latency (DML) on two electrodiagnostic tests. This retrospective study analyzed sixty-two adult

  8. Technical task plan for testing filter box sorbent-paint filter test

    International Nuclear Information System (INIS)

    Kilpatrick, L.L.

    1993-01-01

    At the Savannah River Plant, High Level Waste Engineering (HLWE) asked Interim Waste Technology (IWT) to choose and test a sorbent to add to the ITP filter box that meets the EPA requirement for land disposal of containerized liquid hazardous wastes per Paint Filter Liquids (PFL) test method 9095. This report outlines the process to be used in accomplishing this task

  9. Comparison of Individual Performance in Intelligence Tests WAIS III and RPM (Raven's Progressive Matrices)

    OpenAIRE

    Petrů, Vít

    2017-01-01

    This thesis deals with replacement of performative scale of Wechsler Adult Intelligence Scale (3rd revision) through Raven's Standard Progressive Matrices and Advanced Progressive Matrices. In the theoretical part introduces the concepts of intelligence, approaches to its exploration and intelligence tests. The theoretical part is also devoted to the description of the used methods and presents an overview of the research on a similar theme as this work. In the empirical part of the thesis is...

  10. Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol 11, No. 1 through Vol. 16, No. 6

    International Nuclear Information System (INIS)

    Cottrell, W.B.; Klein, A.

    1976-04-01

    This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970) through Vol. 16, No. 6 (Nov.-Dec. 1975). Included in the index is a chronological list of articles (including abstract) followed by both a KWIC index and an Author Index. Nuclear Safety is a bimonthly technical progress review prepared by the Nuclear Safety Information Center and covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 300 technical articles in the last six years of publication

  11. Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author. Vol. 11(1)--Vol. 18(6)

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W.B.; Klein, A.

    1978-04-11

    This index to Nuclear Safety covers articles published in Nuclear Safety, Vol. 11, No. 1 (January-February 1970), through Vol. 18, No. 6 (November-December 1977). It is divided into three sections: a chronological list of articles (including abstracts) followed by a permuted-title (KWIC) index and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center (NSIC), covers all safety aspects of nuclear power reactors and associated facilities. Over 450 technical articles published in Nuclear Safety in the last eight years are listed in this index.

  12. Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)

    International Nuclear Information System (INIS)

    Cottrell, W.B.; Passiakos, M.

    1982-06-01

    This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index

  13. Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol 11, No. 1 through Vol. 16, No. 6

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W.B.; Klein, A.

    1976-04-01

    This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970) through Vol. 16, No. 6 (Nov.-Dec. 1975). Included in the index is a chronological list of articles (including abstract) followed by both a KWIC index and an Author Index. Nuclear Safety is a bimonthly technical progress review prepared by the Nuclear Safety Information Center and covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 300 technical articles in the last six years of publication.

  14. Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)

    Energy Technology Data Exchange (ETDEWEB)

    Cottrell, W.B.; Passiakos, M.

    1982-06-01

    This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index.

  15. Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author. Vol. 11(1)--Vol. 18(6)

    International Nuclear Information System (INIS)

    Cottrell, W.B.; Klein, A.

    1978-01-01

    This index to Nuclear Safety covers articles published in Nuclear Safety, Vol. 11, No. 1 (January-February 1970), through Vol. 18, No. 6 (November-December 1977). It is divided into three sections: a chronological list of articles (including abstracts) followed by a permuted-title (KWIC) index and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center (NSIC), covers all safety aspects of nuclear power reactors and associated facilities. Over 450 technical articles published in Nuclear Safety in the last eight years are listed in this index

  16. Spent fuel test - Climax: technical measurements. Interim report, Fiscal Year 1983

    International Nuclear Information System (INIS)

    Patrick, W.C.; Butkovich, T.R.; Carlson, R.C.

    1984-02-01

    The Spent Fuel Test - Climax (SFT-C) is located 420 m below surface in the Climax stock granite on the Nevada Test Site. The test is being conducted as part of the Nevada Nuclear Waste Storage Investigations. Eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized April-May 1980. The spent-fuel canisters were retrieved and the thermal sources were de-energized in March-April 1983 when test data indicated that test objectives were met during the 3-year storage phase. The SFT-C operational objective of demonstrating the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner has been met. In addition to emplacement and retrieval operations, three exchanges of spent-fuel between the SFT-C and a surface storage facility, conducted during the storage phase, furthered this demonstration. Technical objectives of the test led to development of a technical measurements program, which is the subject of this and three previous interim reports. Geotechnical, seismological, and test status data have been recorded on a continuing basis for the 3-1/2 year duration of the test on more than 900 channels. Data acquisition from the test is now limited to instrumentation calibration and evaluation activities. Data now available for analysis are presented here. Highlights of activities this year include a campaign of in situ stress measurements, mineralogical and petrological studies of pretest core samples, microfracture analyses of laboratory irradiated cores, improved calculations of near-field heat transfer and thermomechanical response during the final months of heating as well as during a six-month cool-down period, metallurgical analyses of selected test components, and further development of the data acquisition and data management systems. 27 references, 68 figures, 10 tables

  17. Spent fuel test - Climax: technical measurements. Interim report, Fiscal Year 1983

    Energy Technology Data Exchange (ETDEWEB)

    Patrick, W.C.; Butkovich, T.R.; Carlson, R.C.; Durham, W.B.; Ganow, H.C.; Hage, G.L.; Majer, E.L.; Montan, D.N.; Nyholm, R.A.; Rector, N.L.

    1984-02-01

    The Spent Fuel Test - Climax (SFT-C) is located 420 m below surface in the Climax stock granite on the Nevada Test Site. The test is being conducted as part of the Nevada Nuclear Waste Storage Investigations. Eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized April-May 1980. The spent-fuel canisters were retrieved and the thermal sources were de-energized in March-April 1983 when test data indicated that test objectives were met during the 3-year storage phase. The SFT-C operational objective of demonstrating the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner has been met. In addition to emplacement and retrieval operations, three exchanges of spent-fuel between the SFT-C and a surface storage facility, conducted during the storage phase, furthered this demonstration. Technical objectives of the test led to development of a technical measurements program, which is the subject of this and three previous interim reports. Geotechnical, seismological, and test status data have been recorded on a continuing basis for the 3-1/2 year duration of the test on more than 900 channels. Data acquisition from the test is now limited to instrumentation calibration and evaluation activities. Data now available for analysis are presented here. Highlights of activities this year include a campaign of in situ stress measurements, mineralogical and petrological studies of pretest core samples, microfracture analyses of laboratory irradiated cores, improved calculations of near-field heat transfer and thermomechanical response during the final months of heating as well as during a six-month cool-down period, metallurgical analyses of selected test components, and further development of the data acquisition and data management systems. 27 references, 68 figures, 10 tables.

  18. FY 1997 Progress report on tube propagation testing of tank waste using the PRSST

    International Nuclear Information System (INIS)

    Bechtold, D.B.

    1997-01-01

    The subject of this FY 1997 progress report is tube propagation tests of actual, dried tank waste to verify the contact temperature ignition (CTI) criterion for point-source ignition in the Hanford Site waste tanks. Testing is in support of the Organic Tanks Safety Project and will help resolve safety issues with waste containing organic constituents. In FY 1997, improvements were made to the laboratory apparatus and procedures for conducting the testing, and the final testing strategy was formulated. The strategy lays out details of the tests to be performed, samples to be tested, and modes of reporting results

  19. Progression of Carpal Tunnel Syndrome According to Electrodiagnostic Testing in Nonoperatively Treated Patients

    Directory of Open Access Journals (Sweden)

    Mark van Suchtelen

    2014-09-01

    Full Text Available Background:  This study tested the null hypothesis that nonoperatively treated patients would not show disease progression of carpal tunnel syndrome (CTS over time according to median nerve distal motor latency (DML on two electrodiagnostic tests.   Methods:  This retrospective study analyzed sixty-two adult nonoperatively treated patients who were diagnosed with CTS confirmed by a minimum of two electrodiagnostic tests at our institution between December 2006 and  tober 2012. A Wilcoxon signed-rank test was conducted to test the difference between electrodiagnostic measurements between the first and last test. Results: The mean time between the first and last electrodiagnostic test was 26±12 months (range, 12 to 55 months. The only electrodiagnostic measurement that increased significantly was the difference between median and ulnar DML on the same side (r=0.19, P =0.038. The time between the electrodiagnostic tests was significantly longer for patients with at least 10% worsening of the DML at the second test compared to cases of which the DML did not worsen or improve a minimum of 10% (P =0.015.  Conclusions: There is evidence that—on average—idiopathic median neuropathy at the carpal tunnel slowly progresses over time, and this can be measured with electrodiagnostics, but studies with a much longer interval between lectrodiagnostic tests may be needed to determine if it always progresses.

  20. Technical operations procedure for assembly and emplacement of the soil temperature test--test assembly

    International Nuclear Information System (INIS)

    Weber, A.P.

    1978-01-01

    A description is given of the plan for assembly, instrumentation, emplacement, and operational checkout of the soil temperature test assembly and dry well liner. The activities described cover all operations necessary to accomplish the receiving inspection, instrumentation and pre-construction handling of the dry well liner, plus all operations performed with the test article. Actual details of construction work are not covered by this procedure. Each part and/or section of this procedure is a separate function to be accomplished as required by the nature of the operation. The organization of the procedure is not intended to imply a special operational sequence or schedular requirement. Specific procedure operational sections include: receiving inspection; liner assembly operations; construction operations (by others); prepare shield plug; test article assembly and installation; and operational checkout

  1. Identification of sulfur heterocycles in coal liquids and shale oils. Technical progress report, August 1, 1980-May 1, 1981

    Energy Technology Data Exchange (ETDEWEB)

    Lee, M. L.; Castle, R. N.

    1981-01-01

    The sulfur heterocycle separation scheme which was described in the last progress report was evaluated for quantitative recovery of individual components. The results indicate that recoveries can range from 10% to approx. 30% depending on the structure of the compound. During this period, 23 unsubstituted sulfur-containing heterocyclic ring systems were synthesized in oder to confirm GC/MS identifications and for biological testing. The four possible 3-ring heterocycles and the thirteen possible 4-ring heterocycles were tested for mutagenic activity in the histidine reversion (Ames assay) system. One of the 3-ring isomers, naphtho(1,2-b)-thiophene, and six of the 4-ring isomers induced mutations in Salmonella test strains. One of these compounds, phenanthro(3,4-b)thiophene, displayed approximately the same mutagenic activity as benzo(a)pyrene. A two-step adsorption chromatographic procedure was developed in order to fractionate synthetic fuels into various chemical-type classes for studying the relative concentrations and mutagenic activities of the various types. An SRC-II Heavy Distillate was fractionated into aliphatic hydrocarbons, polycyclic aromatic hydrocarbons, sulfur heterocycles, indoles and carbazoles, azaarenes, and amino polycyclic aromatic hydrocarbons. It was found that the amino-PAH fraction contained most of the mutagenic activity. A survey was made for compounds containing both nitrogen and sulfur heteroatoms in their structures. A number of these compounds were detected by GC using nitrogen- and sulfur-selective detection.

  2. Technical concept for a test of geologic storage of spent reactor fuel in the climax granite, Nevada Test Site

    International Nuclear Information System (INIS)

    Ramspott, L.D.; Ballou, L.B.; Carlson, R.C.; Montan, D.N.; Butkovich, T.R.; Duncan, J.E.; Patrick, W.C.; Wilder, D.G.; Brough, W.G.; Mayr, M.C.

    1979-01-01

    We plan to emplace spent fuel assemblies from an operating commercial nuclear reactor in the Climax granite at the US Department of Energy's Nevada Test Site. In this generic test, 11 canisters of spent fuel will be emplaced with 6 electrical simulator canisters in a storage drift 420 m below in surface and their effects compared. Two adjacent drifts will contain electrical heaters, operated to simulate the temperature-stress-displacement fields of a large repository. We describe the test objectives, the technical issues, the site, the preoperational measurement program, thermal and mechanical response calculations, the characteristics of the spent fuel, the field instrumentation and data-acquisition systems, and the system for handling the spent fuel

  3. Technical specification: Mixed-oxide pellets for the light-water reactor irradiation demonstration test

    International Nuclear Information System (INIS)

    Cowell, B.S.

    1997-06-01

    This technical specification is a Level 2 Document as defined in the Fissile Materials Disposition Program Light-Water Reactor Mixed-oxide Fuel Irradiation Test Project Plan. It is patterned after the pellet specification that was prepared by Atomic Energy of Canada, Limited, for use by Los Alamos National Laboratory in fabrication of the test fuel for the Parallex Project, adjusted as necessary to reflect the differences between the Canadian uranium-deuterium reactor and light-water reactor fuels. This specification and the associated engineering drawing are to be utilized only for preparation of test fuel as outlined in the accompanying Request for Quotation and for additional testing as directed by Oak Ridge National Laboratory or the Department of Energy

  4. US Department of Energy Environment, Safety and Health Progress Assessment of the Nevada Test Site

    Energy Technology Data Exchange (ETDEWEB)

    1992-08-01

    This report documents the result of the US Department of Energy (DOE) Environment, Safety, and Health (ES&H) Progress Assessment of the Nevada Test Site (NTS), Nye County, Nevada. The assessment, which was conducted from July 20 through August 4, 1992, included a selective review of the ES&H management systems and progress of the responsible DOE Headquarters Program Offices; the DOE Nevada Field Office (NV); and the site contractors. The ES&H Progress Assessments are part of the Secretary of Energy`s continuing effort to institutionalize line management accountability and the self-assessment process throughout DOE and its contractor organizations. This report presents a summary of issues and progress in the areas of environment, safety and health, and management.

  5. US Department of Energy Environment, Safety and Health Progress Assessment of the Nevada Test Site

    International Nuclear Information System (INIS)

    1992-08-01

    This report documents the result of the US Department of Energy (DOE) Environment, Safety, and Health (ES ampersand H) Progress Assessment of the Nevada Test Site (NTS), Nye County, Nevada. The assessment, which was conducted from July 20 through August 4, 1992, included a selective review of the ES ampersand H management systems and progress of the responsible DOE Headquarters Program Offices; the DOE Nevada Field Office (NV); and the site contractors. The ES ampersand H Progress Assessments are part of the Secretary of Energy's continuing effort to institutionalize line management accountability and the self-assessment process throughout DOE and its contractor organizations. This report presents a summary of issues and progress in the areas of environment, safety and health, and management

  6. Engaging Local Stakeholders on Technical Issues: Test Case at the La Hague Reprocessing Plant - 59211

    International Nuclear Information System (INIS)

    Gilli, Ludivine

    2012-01-01

    In 2009 and 2010, the Institute for Nuclear Safety and Radiation Protection (IRSN) lead a pilot action dealing with the decommissioning of a workshop located on the site of Areva's La Hague fuel-reprocessing plant site in Northwestern France. The purpose of the pilot program was to test ways for IRSN and a few local stakeholders (Non-Governmental Organizations (NGOs) members, local elected officials, etc.) to engage in technical discussions. The discussions were intended to enable the local stakeholders to review the operator's decommissioning application and provide input. The pilot program confirmed there is a definite challenge in successfully opening a meaningful dialogue to discuss technical issues. Three factors influence the extent of the challenge: the knowledge gap between experts and local stakeholders, the conflict between transparency and confidentiality which is inherent with technical topics, and the difficulty for an official expertise institute to hold a dialogue with 'outsiders' during an ongoing reviewing process in which it is participating. The pilot program, given its mixed results, also provided valuable lessons for further improvement of stakeholders' involvement. (authors)

  7. Technical Bases to Consider for Performance and Demonstration Testing of Space Fission Reactors

    International Nuclear Information System (INIS)

    Hixson, Laurie L.; Houts, Michael G.; Clement, Steven D.

    2004-01-01

    Performance and demonstration testing are critical to the success of a space fission reactor program. However, the type and extent to which testing of space reactors should be performed has been a point of discussion within the industry for many years. With regard to full power ground nuclear tests, questions such as 'Do the benefits outweigh the risks? Are there equivalent alternatives? Can a test facility be constructed (or modified) in a reasonable amount of time? Will the test article accurately represent the flight system? Are the costs too restrictive?' have been debated for decades. There are obvious benefits of full power ground nuclear testing such as obtaining systems integrated reliability data on a full-scale, complete end-to-end system. But these benefits come at some programmatic risk. In addition, this type of testing does not address safety related issues. This paper will discuss and assess these and other technical considerations essential in deciding which type of performance and demonstration testing to conduct on space fission reactor systems. (authors)

  8. Mount Elbert Gas Hydrate Stratigraphic Test Well, Alaska North Slope: Overview of scientific and technical program

    Science.gov (United States)

    Hunter, R.B.; Collett, T.S.; Boswell, R.; Anderson, B.J.; Digert, S.A.; Pospisil, G.; Baker, R.; Weeks, M.

    2011-01-01

    The Mount Elbert Gas Hydrate Stratigraphic Test Well was drilled within the Alaska North Slope (ANS) Milne Point Unit (MPU) from February 3 to 19, 2007. The well was conducted as part of a Cooperative Research Agreement (CRA) project co-sponsored since 2001 by BP Exploration (Alaska), Inc. (BPXA) and the U.S. Department of Energy (DOE) in collaboration with the U.S. Geological Survey (USGS) to help determine whether ANS gas hydrate can become a technically and commercially viable gas resource. Early in the effort, regional reservoir characterization and reservoir simulation modeling studies indicated that up to 0.34 trillion cubic meters (tcm; 12 trillion cubic feet, tcf) gas may be technically recoverable from 0.92 tcm (33 tcf) gas-in-place within the Eileen gas hydrate accumulation near industry infrastructure within ANS MPU, Prudhoe Bay Unit (PBU), and Kuparuk River Unit (KRU) areas. To further constrain these estimates and to enable the selection of a test site for further data acquisition, the USGS reprocessed and interpreted MPU 3D seismic data provided by BPXA to delineate 14 prospects containing significant highly-saturated gas hydrate-bearing sand reservoirs. The "Mount Elbert" site was selected to drill a stratigraphic test well to acquire a full suite of wireline log, core, and formation pressure test data. Drilling results and data interpretation confirmed pre-drill predictions and thus increased confidence in both the prospect interpretation methods and in the wider ANS gas hydrate resource estimates. The interpreted data from the Mount Elbert well provide insight into and reduce uncertainty of key gas hydrate-bearing reservoir properties, enable further refinement and validation of the numerical simulation of the production potential of both MPU and broader ANS gas hydrate resources, and help determine viability of potential field sites for future extended term production testing. Drilling and data acquisition operations demonstrated that gas hydrate

  9. Development of Abbreviated Nine-Item Forms of the Raven's Standard Progressive Matrices Test

    Science.gov (United States)

    Bilker, Warren B.; Hansen, John A.; Brensinger, Colleen M.; Richard, Jan; Gur, Raquel E.; Gur, Ruben C.

    2012-01-01

    The Raven's Standard Progressive Matrices (RSPM) is a 60-item test for measuring abstract reasoning, considered a nonverbal estimate of fluid intelligence, and often included in clinical assessment batteries and research on patients with cognitive deficits. The goal was to develop and apply a predictive model approach to reduce the number of items…

  10. Progress report on fish counting on the Rivers Itchen and Test

    OpenAIRE

    Welton, J.S.

    1982-01-01

    This progress report summarises work on NSHEB Mark 10 fish counters which are installed at Woodmill on the River Itchen and Nurseling Mill and Connegar Bridge on the River Test. Counters are evaluated and salmon behaviour regarding the counters examined. The report includes a a list of equipment needed for the efficient running of the project in the future.

  11. Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Part 1. Geological environment of Japan

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-11-01

    Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, the part 1 of the progress report, describes first in detail the role of geological environment in high-level radioactive wastes disposal, the features of Japanese geological environment, and programs to proceed the investigation in geological environment. The following chapter summarizes scientific basis for possible existence of stable geological environment, stable for a long period needed for the HLW disposal in Japan including such natural phenomena as volcano and faults. The results of the investigation of the characteristics of bed-rocks and groundwater are presented. These are important for multiple barrier system construction of deep geological disposal. The report furthermore describes the present status of technical and methodological progress in investigating geological environment and finally on the results of natural analog study in Tono uranium deposits area. (Ohno, S.)

  12. Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. An extra issue: background of the geological disposal

    International Nuclear Information System (INIS)

    1999-11-01

    Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, an extra issue of the progress report, was prepared for the expected readers of the report to have background information on the geological disposal. Thus it gives information about (1) generation of high-level radioactive wastes, (2) history of plans proposed for HLW disposal in Japan, and (3) procedure until the geological disposal plan is finally adopted and basic future schedules. It further discusses on such problems in HLW treatment and disposal, as for example a problem of reliable safety for a very long period. (Ohno, S.)

  13. Exotic atoms: Hadronic and muonic atoms 1969--1997. Technical progress report, February 1, 1996--August 31, 1997

    International Nuclear Information System (INIS)

    Kunselman, R.

    1997-01-01

    Since this is a terminal progress-report it is a synopsis over the total time of the grant. The author has utilized exotic hadronic and muonic atoms as tools to access information concerning questions to do with particle, nuclear, and atomic physics. The information has answered fundamental questions about lepton conservations, quark models, tests of the CPT theorem, QED energies, and nuclear structure. The present experiments involve reactions with a variety of hydrogen isotopic mixtures to form solid targets to produce muonic hydrogen isotope atoms. The method relies on muon capture by a proton and transfer of the muon from the proton to a deuteron or a triton. The resulting muonic deuterium or muonic tritium will not immediately thermalize because of the very low elastic cross sections of the Ramsauer-Townsend effect, and are emitted from the surface of the layer and escape into a vacuum region. A second solid hydrogen isotopic target is produced downstream on which the muonic hydrogen atom can react and the time of flight measured

  14. Intermediate-energy nuclear physics. Task C. Technical progress report, October 1, 1982-October 1, 1983. Part I

    International Nuclear Information System (INIS)

    1983-01-01

    Progress is reported on the following experimental studies: (1) excitation of giant resonances in 118 Sn in inelastic pion scattering at 130 MeV; (2) giant dipole excitations of 40 Ca by inelastic pion scattering; (3) charge symmetry test using the π + and π - elastic scattering from deuterium at 143 and 256 MeV; (4) binding energy effects on the isospin amplitudes in p-shell nuclei; (5) the energy dependence of the 14 C (π + ,π 0 ) 14 N reaction to the IAS; (6) the ( 3 He,t) reaction at 2 GeV; (7) analyzing power in the (polarized p,n) IAS transitions; (8) the excitation of the 1/2 + (2.36) MeV state in the 24Mg (polarized p,d) reaction from 27 to 150 MeV; (9) the energy dependence of the (polarized p,d) reaction for 54 Fe and 140 Ce; and (10) the energy dependence of the 7 Li(p,d) 6 Li reaction. Publications are listed

  15. Justification of Technical System Control in Developing and Testing Objects of Missile and Space Technology

    Directory of Open Access Journals (Sweden)

    A. A. Fedorovskiy

    2015-01-01

    Full Text Available Tests in general lifecycle of missile and space technology, play a special role. The high cost of such products and a little time for creation and refinement, allow only a limited number of tests. Justification of the appropriate number of tests and finding the ways to reduce it are important from the practical point of view.When the appropriate number of field tests is impossible to implement, as well as if full or partial realization of the sample operation conditions is impossible the authors propose to use software with the involvement of previously obtained aprioristic information to have the modeling results of the functioning sample or its parts, according to the reliability and quality standards.Involvement of statistical methods for systems and objects of the missile and space equipment is limited to the single number of the carried-out tests. Currently used models and methods for systems of missile and barreled weapon do not allow us to conduct analysis and provide guidance on emerging issues of concern to ensure the quality and reliability of objects of the missile and space equipment by results of tests.The method of probabilistic and statistical analysis of the stochastic system operability is supposed to be used to solve a problem of the planning tests, assessment and control of reliability of technical systems at tests using aprioristic calculated and experimental information. This method makes it possible to relate the number of tests, required to prove the desirable level of reliability, to different types of constructional, functional, structural reserves of the system, as well as the level of information-and-measuring base and the completeness of available information.Thus, the structure of controlled elements, their importance, and acceptance conditions including elaboration of actions and recommendations to eliminate discrepancies in controlled parameters and improve quality of the considered system are justified and formed

  16. In-Pile Testing and Instrumentation for Development of Generation-IV Fuels and Materials. Proceedings of a Technical Meeting

    International Nuclear Information System (INIS)

    2013-12-01

    For many years, the increase in efficiency in the production of nuclear electricity has been an economic challenge in many countries which have developed this kind of energy. The increase in fuel burnup and fuel residence time leads to a reduction in the volume of fresh fuel loaded and spent fuel discharged, respectively. More demanding nuclear fuel cycle parameters are combined with a need to operate nuclear power plants with maximal availability and load factors, in load-follow mode and with longer fuel cycles. In meeting these requirements, fuel has to operate in a demanding environment of high radiation fields, high temperatures, high mechanical stresses and high coolant flow. Requirements of increased fuel reliability and minimal fuel failures also remain in force. Under such circumstances, continuous development of more radiation resistant fuel materials, especially advanced cladding, careful and incremental examinations, and improved understanding and modelling of high burnup fuel behaviour are required. Following a recommendation of the IAEA Technical Working Group on Fuel Performance and Technology, the Technical Meeting on In-pile Testing and Instrumentation for Development of Generation-IV Fuels and Materials was held in Halden, Norway, on 21-24 August 2012. The purpose of the meeting was to review the current status and the progress in methods and technologies used for the in-pile testing of nuclear fuel achieved since the previous IAEA meeting on In-core Instrumentation and Reactor Core Assessment, also held in Halden in 2007. Emphasis was placed on advanced techniques applied for the understanding of high burnup fuel behaviour of water cooled power reactors that represent the vast majority of the current nuclear reactor fleet. However, the meeting also included papers and discussion on testing techniques applied or developed specifically for new fuel and structural materials considered for Generation-IV systems. The meeting was attended by 43

  17. Structured approach to design of diagnostic test evaluation studies for chronic progressive infections in animals

    DEFF Research Database (Denmark)

    Nielsen, Søren Saxmose; Toft, Nils; Gardner, Ian Andrew

    2011-01-01

    Diagnostic test evaluations (DTEs) for chronic infections are challenging because a protracted incubation period has to be considered in the design of the DTE, and the adverse effects of infection may be widespread and progressive over an animal's entire life. Frequently, the specific purpose......) than originally intended. The objective of this paper is to outline a structured approach to the design and conduct of a DTE for diagnostic tests used for chronic infections in animals, and intended for different purposes. We describe the process from reflections about test purpose and the underlying...... of the test is not formally considered when a test is evaluated. Therefore, the result is often a DTE where test sensitivity and specificity estimates are biased, either because of problems with establishing the true infection status or because the test detects another aspect of the infection (and analyte...

  18. Conversion of research and test reactors to low enriched uranium fuel: technical overview and program status

    International Nuclear Information System (INIS)

    Roglans-Ribas, J.

    2008-01-01

    Many of the nuclear research and test reactors worldwide operate with high enriched uranium fuel. In response to worries over the potential use of HEU from research reactors in nuclear weapons, the U.S Department of Energy (DOE) initiated a program - the Reduced Enrichment for Research and Test Reactors (RERTR) - in 1978 to develop the technology necessary to reduce the use of HEU fuel by converting research reactors to low enriched uranium (LEU) fuel. The Reactor Conversion program is currently under the DOE's National Nuclear Security Administration's Global Threat Reduction Initiative (GTRI). 55 of the 129 reactors included in the scope have been already converted to LEU fuel or have shutdown prior to conversion. The major technical activities of the Conversion Program include: (1) the development of advanced LEU fuels; (2) conversion analysis and conversion support; and (3) technology development for the production of Molybdenum-99 (Mo 99 ) with LEU targets. The paper provides an overview of the status of the program, the technical challenges and accomplishments, and the role of international collaborations in the accomplishment of the Conversion Program objectives. Nuclear research and test reactors worldwide have been in operation for over 60 years. Many of these facilities operate with high enriched uranium fuel. In response to increased worries over the potential use of HEU from research reactors in the manufacturing of nuclear weapons, the U.S Department of Energy (DOE) initiated a program - the Reduced Enrichment for Research and Test Reactors (RERTR) - in 1978 to develop the technology necessary to reduce the use of HEU fuel in research reactors by converting them to low enriched uranium (LEU) fuel. The reactor conversion program was initially focused on U.S.-supplied reactors, but in the early 1990s it expanded and began to collaborate with Russian institutes with the objective of converting Russian supplied reactors to the use of LEU fuel.

  19. The Dutch Technical-Tactical Tennis Test (D4T) for Talent Identification and Development : Psychometric Characteristics

    NARCIS (Netherlands)

    Kolman, Nikki; Huijgen, Barbara; Kramer, Tamara; Elferink-Gemser, Marije; Visscher, Chris

    2017-01-01

    This study examined the test-retest reliability, validity and feasibility of the newly developed Dutch Technical Tactical Tennis Test (D4T). This new test is relevant for talent identification and development in tennis. Thirty-two youth male tennis players (age 13.4 +/- 0.5) were classified as elite

  20. Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Introductory part and summaries

    International Nuclear Information System (INIS)

    1999-11-01

    Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan and comprises seven chapters. Chapter I briefly describes the importance of HLW management in promoting nuclear energy utilization. According to the long-term program, the HLW separated from spent fuels at reprocessing plants is to be vitrified and stored for a period of 30 to 50 years to allow cooling, then be disposed of in a deep geological formation. Chapter II mainly explains the concepts of geological disposal in Japan. Chapters III to V are devoted to discussions on three important technical elements (the geological environment of Japan, engineering technology and safety assessment of the geological disposal system) which are necessary for reliable realization of the geological disposal concept. Chapter VI demonstrates the technical ground for site selection and for setup of safety standards of the disposal. Chapter VII summarizes together with plans for future research and development. (Ohno, S.)

  1. NRC review of passive reactor design certification testing programs: Overview, progress, and regulatory perspective

    Energy Technology Data Exchange (ETDEWEB)

    Levin, A.E.

    1995-09-01

    New reactor designs, employing passive safety systems, are currently under development by reactor vendors for certification under the U.S. Nuclear Regulatory Commission`s (NRC`s) design certification rule. The vendors have established testing programs to support the certification of the passive designs, to meet regulatory requirements for demonstration of passive safety system performance. The NRC has, therefore, developed a process for the review of the vendors` testing programs and for incorporation of the results of those reviews into the safety evaluations for the passive plants. This paper discusses progress in the test program reviews, and also addresses unique regulatory aspects of those reviews.

  2. A case of natalizumab-associated progressive multifocal leukoencephalopathy with repeated negative CSF JCV testing.

    Science.gov (United States)

    Mazda, Monica E; Brosch, Jared R; Wiens, Andrea L; Bonnin, José M; Kamer, Aaron P; Mattson, David H; Snook, Riley J

    2013-05-01

    The development of progressive multifocal leukoencephalopathy (PML) in patients treated with natalizumab is a well-known potential risk. Diagnosis of PML can be confounded in patients with multiple sclerosis (MS) if new demyelinating lesions develop, and the sensitivity of existing diagnostic tests is less than ideal. In the case presented here, four samples of cerebrospinal fluid tested negative for John Cunningham virus (JCV) DNA by polymerase chain reaction, yet brain biopsy eventually proved positive by immunohistochemistry. A review of the limitations of existing clinical diagnostic tests is addressed, and we review the most recent literature on the proper management of natalizumab-treated MS patients.

  3. [Progress in isokinetic technology in testing and training for assessment of muscle function].

    Science.gov (United States)

    Huang, Ting-Ting; Fan, Li-Hua; Gao, Dong; Xia, Qing; Zhang, Min

    2013-02-01

    Isokinetic technology in testing and training is the most advanced practical technique in the evaluation of muscle function. This method is a continuous dynamic test in the full range of the joint motion which has strong pertinence at the aspect of assessing muscle strength, and is an objective and quantitative method for reflecting each point's muscle strength in the range of the joint motion. This article reviews the key concepts, brief history of development and influencing factors of isokinetic technology in testing and training, introduces the progress in the field of rehabilitation medicine and sport science, etc., and discusses the future exploration in forensic science.

  4. Creating a test blueprint for a progress testing program: A paired-comparisons approach.

    Science.gov (United States)

    von Bergmann, HsingChi; Childs, Ruth A

    2018-03-01

    Creating a new testing program requires the development of a test blueprint that will determine how the items on each test form are distributed across possible content areas and practice domains. To achieve validity, categories of a blueprint are typically based on the judgments of content experts. How experts judgments are elicited and combined is important to the quality of resulting test blueprints. Content experts in dentistry participated in a day-long faculty-wide workshop to discuss, refine, and confirm the categories and their relative weights. After reaching agreement on categories and their definitions, experts judged the relative importance between category pairs, registering their judgments anonymously using iClicker, an audience response system. Judgments were combined in two ways: a simple calculation that could be performed during the workshop and a multidimensional scaling of the judgments performed later. Content experts were able to produce a set of relative weights using this approach. The multidimensional scaling yielded a three-dimensional model with the potential to provide deeper insights into the basis of the experts' judgments. The approach developed and demonstrated in this study can be applied across academic disciplines to elicit and combine content experts judgments for the development of test blueprints.

  5. Plutonium immobilization project development and testing technical project office quality assurance program description

    International Nuclear Information System (INIS)

    Gould, T.H.; MacLean, L.M.; Ziemba, J.M.

    1999-01-01

    The Plutonium Immobilization Project (PIP) is one of several fissile materials disposition projects managed by the Department of Energy (DOE) Office of Fissile Materials Disposition (OFMD). The PIP is expected to evolve from the current Development and Testing (D and T) effort, to design, to construction, and finally to operations. Overall management and technical management of the D and T effort resides at the Lead Laboratory, Lawrence Livermore National Laboratory (LLNL), through the LLNL Manager, Fissile Materials Disposition Program (FMDP). Day to day project activities are managed by the D and T Technical Project Office (TPO), which reports to the LLNL Manager, FMDP. The D and T TPO consists of the Technical Manager, the TPO Quality Assurance (QA) Program Manager, and TPO Planning and Support Staff. This Quality Assurance Program Description (QAPD) defines the QA policies and controls that will be implemented by these TPO personnel in their management of D and T activities. This QAPD is consistent with and responsive to the Department of Energy Fissile Materials Disposition Program Quality Assurance Requirements Document (FMDP QARD). As the Project and upper level requirement's documents evolve, this QAPD will be updated as necessary to accurately define and describe the QA Program and Management of the PIP. The TPO has a policy that all development and testing activities be planned, performed and assessed in accordance with its customer's requirements, needs and expectations, and with a commitment to excellence and continuous improvement. The TPO QAPD describes implementation requirements which, when completed, will ensure that the project development and testing activities conform to the appropriate QA requirements. For the program to be effective, the TPO QA Program Manager will ensure that each site participating in D and T activities has developed a QAPD, which meets the customer's requirements, and has a designated quality leader in place. These customer

  6. Controlled environmental radioiodine tests at the national reactor testing station. 1965 progress report

    Energy Technology Data Exchange (ETDEWEB)

    Adams, D.R.; Bunch, D.F.; Gammill, W.P.; Hawley, C.A. Jr.; Markee, E.H.; Tiernan, M.W.

    1966-02-01

    The CERT project consists of a series of planned releases of radioiodine over different vegetation and during various meteorological conditions, with the prime objective being to measure the relationships involved in the passage of radioiodine through the air-vegetation-cow-milk-human chain. The results of the first five tests in the series, which started in the spring of 1963 and is continuing, are reported. Each test was conducted under measured meteorological conditions and over prepared sampling and grazing courses. Two tests were made over open-range type vegetation, two over irrigated pastures, and one over snow-covered ground. Two tests were conducted under lapse conditions, two under inversion conditions, and one under neutral conditions. In each case, known quantities of elemental /sup 131/I/sub 2/ were released. Relationships determined included air-grass ratios (deposition velocities) which ranged from 0.1 to 1.0 cm/sec; effective half life of /sup 131/I on grass of 3.5 days and 5.5 days; the time of peak activity in milk at two days following a release; milk-grass ratio (C/1:C/g); total /sup 131/I secreted in milk by cows to that ingested by cows; adult human thyroid uptake fraction (inhalation); and based on a breathing rate of 20 m/sup 3//24 hours, the ratio between infinity mills ingestion dose and infinity inhalation dose for a single release was calculated. Data, descriptions of methods, and calculations are reported. Discussions of resuspension factors and particle sizes and behavior are also included.

  7. The concurrent validity of the technical test battery as an indicator of work performance in a telecommunications company

    Directory of Open Access Journals (Sweden)

    Marelize Barnard

    2005-10-01

    Full Text Available The purpose of this study was to assess the concurrent validity of the Technical Test Battery (TTB in a South African telecommunications institution. The Technical Test Battery (TTB was administered to a sample of 107 technical officers. Their test scores were compared to the scores obtained from a job performance rating scale specifically designed for this position on the basis of a thorough job analysis. The TTB demonstrated high concurrent validity as an indicator of work performance for technical posts in the telecommunications environment. These results suggest that the TTB may have a high predictive validity for performance in technical positions. The findings and implications of the study are discussed. Opsomming Die doel van hierdie studie was om die samevallende geldigheid van die “Technical Test Battery (TTB�? in ’n Suid-Afrikaanse telekommunikasie instansie te bepaal. Die TTB is op ’n steekproef van 107 tegniese personeel toegepas. Die toetstellings is in verband gebring met die tellings van ’n werksprestasiemaatstaf wat spesifiek vir die pos ontwikkel is op grond van ’n deeglike posanalise. Daar is bevind dat die TTB ’n hoë samevallende geldigheid as aanduider van werksprestasie vir tegniese poste in the telekommunikasiebedryf toon. Dié resultate dui op ’n sterk moontlikheid dat die TTB ’n goeie voorspeller van werksprestasie vir tegniese beroepe kan wees. Die bevindinge en implikasies van die studie word bespreek.

  8. Technical requirements for the actinide source-term waste test program

    Energy Technology Data Exchange (ETDEWEB)

    Phillips, M.L.F.; Molecke, M.A.

    1993-10-01

    This document defines the technical requirements for a test program designed to measure time-dependent concentrations of actinide elements from contact-handled transuranic (CH TRU) waste immersed in brines similar to those found in the underground workings of the Waste Isolation Pilot Plant (WIPP). This test program wig determine the influences of TRU waste constituents on the concentrations of dissolved and suspended actinides relevant to the performance of the WIPP. These influences (which include pH, Eh, complexing agents, sorbent phases, and colloidal particles) can affect solubilities and colloidal mobilization of actinides. The test concept involves fully inundating several TRU waste types with simulated WIPP brines in sealed containers and monitoring the concentrations of actinide species in the leachate as a function of time. The results from this program will be used to test numeric models of actinide concentrations derived from laboratory studies. The model is required for WIPP performance assessment with respect to the Environmental Protection Agency`s 40 CFR Part 191B.

  9. Technical requirements for the actinide source-term waste test program

    International Nuclear Information System (INIS)

    Phillips, M.L.F.; Molecke, M.A.

    1993-10-01

    This document defines the technical requirements for a test program designed to measure time-dependent concentrations of actinide elements from contact-handled transuranic (CH TRU) waste immersed in brines similar to those found in the underground workings of the Waste Isolation Pilot Plant (WIPP). This test program wig determine the influences of TRU waste constituents on the concentrations of dissolved and suspended actinides relevant to the performance of the WIPP. These influences (which include pH, Eh, complexing agents, sorbent phases, and colloidal particles) can affect solubilities and colloidal mobilization of actinides. The test concept involves fully inundating several TRU waste types with simulated WIPP brines in sealed containers and monitoring the concentrations of actinide species in the leachate as a function of time. The results from this program will be used to test numeric models of actinide concentrations derived from laboratory studies. The model is required for WIPP performance assessment with respect to the Environmental Protection Agency's 40 CFR Part 191B

  10. Investigations of nuclear structure and nuclear reactions induced by complex projectiles. Technical progress report, November 1, 1978-October 31, 1979

    International Nuclear Information System (INIS)

    Sarantites, D.G.

    1979-01-01

    Experimental research on nuclear structure and reactions both published and in progress is summarized. Included are fusion reactions, strongly damped heavy ion collisions, and nuclear structure at high angular momentum. A list of publications is included

  11. Effect of point defects on mechanical properties of metals. Technical progress report, January 1, 1978--November 30, 1978

    International Nuclear Information System (INIS)

    Meshii, M.

    1978-11-01

    Progress is reported on deformation behavior of niobium single crystals below 77 0 K, the effect of electron irradiation on the deformation behavior of niobium single crystals, and surface film softening phenomenon in Ni plated iron single crystals

  12. 42 CFR 493.1838 - Training and technical assistance for unsuccessful participation in proficiency testing.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 5 2010-10-01 2010-10-01 false Training and technical assistance for unsuccessful... REQUIREMENTS Enforcement Procedures § 493.1838 Training and technical assistance for unsuccessful participation... may require the laboratory to undertake training of its personnel, or to obtain necessary technical...

  13. New York City School Survey 2008-2010: Assessing the Reliability and Validity of a Progress Report Measure. Technical Appendices

    Science.gov (United States)

    Nathanson, Lori; Cole, Rachel; Kemple, James J.; Lent, Jessica; McCormick, Meghan; Segeritz, Micha

    2013-01-01

    The Research Alliance for New York City Schools examined Department of Education (DOE) School Survey data from 2008-2010 to better understand the richness and complexities of the information elicited by the Survey from parents, students, and teachers. This document provides the appendices to the technical report "New York City School Survey…

  14. Technical basis for the ITER-FEAT outline design. Progress in resolving open design issues from the outline design report

    International Nuclear Information System (INIS)

    2000-01-01

    In this publication the technical basis for the ITER-FEAT outline design is presented. It comprises the Plant Design Specifications, the Safety Principles and Environmental Criteria, the Site Requirements and Site Design Assumptions. The outline of the key features of the ITER-FEAT design includes main physical parameters and assessment, design overview and preliminary safety assessment, cost and schedule

  15. Technical issues of reduced activation ferritic/martensitic steels for fabrication of ITER test blanket modules

    International Nuclear Information System (INIS)

    Tanigawa, H.; Hirose, T.; Shiba, K.; Kasada, R.; Wakai, E.; Serizawa, H.; Kawahito, Y.; Jitsukawa, S.; Kimura, A.; Kohno, Y.; Kohyama, A.; Katayama, S.; Mori, H.; Nishimoto, K.; Klueh, R.L.; Sokolov, M.A.; Stoller, R.E.; Zinkle, S.J.

    2008-01-01

    Reduced activation ferritic/martensitic steels (RAFMs) are recognized as the primary candidate structural materials for fusion blanket systems. The RAFM F82H was developed in Japan with emphasis on high-temperature properties and weldability. Extensive irradiation studies have conducted on F82H, and it has the most extensive available database of irradiated and unirradiated properties of all RAFMs. The objective of this paper is to review the R and D status of F82H and to identify the key technical issues for the fabrication of an ITER test blanket module (TBM) suggested from the recent research achievements in Japan. This work clarified that the primary issues with F82H involve welding techniques and the mechanical properties of weld joints. This is the result of the distinctive nature of the joint caused by the phase transformation that occurs in the weld joint during cooling, and its impact on the design of a TBM will be discussed

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

    International Nuclear Information System (INIS)

    Hart, A.T.; Rivers, T.J.; Alsberg, C.M.; Filius, K.D.

    1992-01-01

    The Component Development and Integration Facility (CDIF) is a Department of Energy test facility operated by MSE, Inc. In the fall of 1984, a 50-MW t , pressurized, slag rejecting coal-fired combustor (CFC) replaced the oil-fired combustor in the test train. In the spring of 1989, a coal-fired precombustor was added to the test hardware, and current controls were installed in the spring of 1990. In the fall of 1990, the slag rejector was installed. MSE test hardware activities included installing the final workhorse channel and modifying the coalfired combustor by installing improved design and proof-of-concept (POC) test pieces. This paper discusses the involvement of this hardware in test progress during the past year. Testing during the last year emphasized the final workhorse hardware testing. This testing will be discussed. Facility modifications and system upgrades for improved operation and duration testing will be discussed. In addition, this paper will address long-term testing plans

  17. Hydrologic Resources Management Program and Underground Test Area Project FY2005 Progress Report

    International Nuclear Information System (INIS)

    Eaton, G F; Genetti, V; Hu, Q; Hudson, G B; Kersting, A B; Lindvall, R E; Moran, J E; Nimz, G J; Ramon, E C; Rose, T P; Shuller, L; Williams, R W; Zavarin, M; Zhao, P

    2007-01-01

    This report describes FY 2005 technical studies conducted by the Chemical Biology and Nuclear Science Division (CBND) at Lawrence Livermore National Laboratory (LLNL) in support of the Hydrologic Resources Management Program (HRMP) and the Underground Test Area Project (UGTA). These programs are administered by the U.S. Department of Energy, National Nuclear Security Administration, Nevada Site Office (NNSA/NSO) through the Defense Programs and Environmental Restoration Divisions, respectively. HRMP-sponsored work is directed toward the responsible management of the natural resources at the Nevada Test Site (NTS), enabling its continued use as a staging area for strategic operations in support of national security. UGTA-funded work emphasizes the development of an integrated set of groundwater flow and contaminant transport models to predict the extent of radionuclide migration from underground nuclear testing areas at the NTS. The report is organized on a topical basis and contains five chapters that highlight technical work products produced by CBND. However, it is important to recognize that most of this work involves collaborative partnerships with the other HRMP and UGTA contract organizations. These groups include the Energy and Environment Directorate at LLNL (LLNL-E and E), Los Alamos National Laboratory (LANL), the Desert Research Institute (DRI), the U.S. Geological Survey (USGS), Stoller-Navarro Joint Venture (SNJV), and Bechtel Nevada (BN)

  18. Serologic test systems development. Progress report, July 1, 1976--September 30, 1977

    Energy Technology Data Exchange (ETDEWEB)

    Saunders, G.C.; Clinard, E.H.; Bartlett, M.L.; Petersen, P.M.; Sanders, W.M.; Payne, R.J.; Martinez, E.

    1978-01-01

    Work has continued on the development and application of the Enzyme-Labeled Antibody (ELA) test to the USDA needs. Results on trichinosis, brucellosis, and staphylococcal enterotoxin A detection are very encouraging. A field test for trichinosis detection is being worked out in cooperation with Food Safety and Quality Service personnel. Work is in progress with the Technicon Instrument Corporation to develop a modification of their equipment to automatically process samples by the ELA procedure. An automated ELA readout instrument for 96-well trays has been completed and is being checked out.

  19. Technical committee on transport package test standards (for radioactive materials transport). Vienna, 6-10 August 1979

    International Nuclear Information System (INIS)

    White, M.C.

    1979-11-01

    The report of a meeting of the technical committee on transport package test standards is presented. The committee assigned high priority to work on Low Level Solid material and Low Specific Activity material, on the justification for and requirements of a Crush Test and on leakage from packages

  20. Spent Fuel Test-Climax: technical measurements data management system description and data presentation

    International Nuclear Information System (INIS)

    Carlson, R.C.

    1985-08-01

    The Spent Fuel Test-Climax (SFT-C) was located 420 m below surface in the Climax Stock granite on the Nevada Test Site. The test was conducted under the technical direction of the Lawrence Livermore National Laboratory (LLNL) as part of the Nevada Nuclear Waste Storage Investigations (NNWSI) for the US Department of Energy. Eleven canisters of spent nuclear reactor fuel were emplaced, along with six electrical simulators, in April-May 1980. The spent fuel canisters were retrieved and the electrical simulators de-energized in March-April 1983. During the test, just over 1000 MW-hr of thermal energy was deposited in the site, causing temperature changes 100 0 C near the canisters, and about 5 0 in the tunnels. More than 900 channels of geotechnical, seismological, and test status data were recorded on nearly continuous basis for about 3-1/2 years, ending in September 1983. Most geotechnical instrumentation was known to be temperature sensitive, and thus would require temperature compensation before interpretation. Accordingly, a 10-in. reel of digital tape was off-loaded and shipped to Livermore every 4 to 8 weeks, where the data were verified, organized into 45 one-million-word files, and temperature corrected. The purpose of this report is to document the receipt and processing of the data by LLNL Livermore personnel, present facts about the history of the instruments which may be important to the interpretation of the data, present the data themselves in graphical form for each instrument over its operating lifetime, document the forms and locations in which the data will be archived, and offer the data to the geotechnical community for future use in understanding and predicting the effects of the storage of heat-generating waste in hard rocks such as granite

  1. Association Euratom - Risø National Laboratory for Sustainable Energy, Technical University of Denmark - Annual Progress Report 2009

    DEFF Research Database (Denmark)

    Korsholm, Søren Bang; Michelsen, Poul; Juul Rasmussen, Jens

    The programme of the Research Unit of the Fusion Association Euratom - Risø National Laboratory for Sustainable Energy, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its...... superconductors. Minor activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2009....

  2. Association Euratom - Risø National Laboratory for Sustainable Energy, Technical University of Denmark - Annual Progress Report 2008

    DEFF Research Database (Denmark)

    Korsholm, Søren Bang; Michelsen, Poul; Juul Rasmussen, Jens

    The programme of the Research Unit of the Fusion Association Euratom - Risø National Laboratory for Sustainable Energy, Technical University of Denmark, covers work in fusion plasma physics and in fusion technology. The fusion plasma physics research focuses on turbulence and transport, and its...... been initiated in 2008. Minor activities are system analysis, initiative to involve Danish industry in ITER contracts and public information. A summary is presented of the results obtained in the Research Unit during 2008....

  3. Technical progress, the concept of individualized cancer treatment and the innovation of computer-assisted radiotherapy planning

    International Nuclear Information System (INIS)

    Merkle, K.; Tanneberger, S.; Matschke, S.

    1985-01-01

    After a first step of cancerogenesis, the further development of the tumor is an individual process. At the end of this process the tumor is formed as an individual in the individual. The individuality of cancer exists on the level of organs, tissues and cells and includes an individual tumor-host relationship. Today, optimized cancer treatment requires a most precise biological characterization possible of the tumor and of the tumor-host relationship, which will provide objective information about the individual character of every tumor. Routine analysis and strict therapeutic consideration of the clinical and biological individuality of human cancer can offer real chances for the improvement of cancer treatment. A routine acquisition of individual tumor characteristics will be possible only if methods and equipment are available for the registration of suitable parameters. In this context technical innovations have an essential influence on the realization of the concept of individualized cancer treatment. With the method of flow cytophotometry and other techniques examples are given in how far the ideas of individual cancer management can be realized by introduction of new technical solutions into medical research and clinical practice. Unfortunately there is still a lack of methodology in individualizing cancer treatment. The individualization of radiotherapy is connected to an extremely high degree of technical innovations. Particularly this refers to the topometrical description of the target volume in relation to the adjacent anatomical structures and the body contour as well as the fitting of isodoses to the shape and size of the target volume. As an example of innovation of a technical solution for individual radiotherapy planning the computer-assisted radiotherapy planning system DOPSY is described. (author)

  4. The 3 vs 1 game build-up effectiveness examination in physical and technical tests of 11-year-old football players

    Directory of Open Access Journals (Sweden)

    Tóth jr. Janos

    2014-01-01

    Full Text Available Study aim: The aim of this study is to prove that young players who have been coached with the main focus on technical ability and player interaction, perform better when tested on physical and technical attributes.

  5. Record of Technical Change No.2 for ''Corrective Action Investigation Plan for Corrective Action Unit 143: Area 25 Contaminated Waste Dumps, Nevada Test Site, Nevada''

    International Nuclear Information System (INIS)

    1999-01-01

    This Record of Technical Change provides updates to the technical information included in ''Corrective Action Investigation Plan for Corrective Action Unit 143: Area 25 Contaminated Waste Dumps, Nevada Test Site, Nevada.''

  6. Characterization and testing of materials for nuclear reactors. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2007-03-01

    Nuclear techniques in general and neutrons based methods in particular have played and will continue to play an important role in research in materials science and technology. Today the world is looking at nuclear fission and nuclear fusion as the main sources of energy supply for the future. Research reactors have played a key role in the development of nuclear technology. A materials development programme will thus play a major role in the design and development of new nuclear power plants, for the extension of the life of operating reactors as well as for fusion reactors. Against this background, the IAEA had organized a Technical Meeting on Development, Characterization and Testing of Materials - With Special Reference to the Energy Sector under the activity on specific applications of research reactors. The meeting was held in Vienna, May 29- June 2, 2006. There was also participation by experts in techniques, complementary to neutrons. The participants for the technical meeting were experts in the utilization of nuclear techniques namely the high flux and medium flux research reactors, fusion research and positron annihilation. They presented the design, development and utilization of the facilities at their respective centres for materials characterization with main focus on materials for nuclear energy, both fission and fusion. In core irradiation of materials, development of instrument for residual stress measurement in large and / or irradiated specimen, neutron radiography for inspection of irradiated fuel, work on oxide dispersion strengthened (ODS) steels and SiC composites, relevant to future power systems were cited as application of nuclear techniques in fission reactors. The use of neutron scattering for helium bubbles in steel, application of positron annihilation to study helium bubbles in Cu, Ti-stabilized stainless steel and voidswelling studies etc. show that these techniques have an important role in the development of materials for energy

  7. TESTING TECHNICAL AND SCALE EFFICIENCY OF KAZAKHBANKS:EVIDENCE BASED ON DATA ENVELOPMENT ANALYSIS

    Directory of Open Access Journals (Sweden)

    Razzaque H Bhatti

    2013-01-01

    Full Text Available This paper tests technical and scale efficiency of 20 Kazakh banks using annualdata on three inputs (interest expenses, non-interestexpenses and deposits andthree outputs (interest income, non-interest income and loans over the period2007-2011. Two input-oriented data envelopment analysis models of Charnes etal (1978 and Banker et al(1984, which are based on constant return to scale andvariable return to scale respectively, areused to evaluate technical efficiency,whereas scale efficiency is computed bydividing the former efficiency ratio bythe latter one. The resultsobtained show that the average efficiency ratios ofindividual banks under constant and variable returns toscale range from 0.88 and1.00 to 0.93 and 1.00 respectively, whereas those of all banks between 0.95 and0.98 respectively. Only are the fivebanks (ATFB, Citibank, HSBC bank,KazInvest bank and Exim bank the mostefficient banks in Kazakhstan, sincetheir efficiency ratios have been consistently equal to unity, implying that thesebanks operate at their optimal levels. The efficiency scores of the remaining 15banks range from 0.88 to 0.99, and as suchthe majority of these banks do notseem to operate far more below their optimal level. The results indicate that theperformance of the Kazakh banks deteriorated substantially during the globalfinancial crisis of 2008 because theCRS ratio dropped from 0.65 in 2007 to 0.50in 2008 and to 0.40 in 2009. The results alsoconfirm that most of the foreignbanks perform relatively better than domestic banks.

  8. Spent Fuel Test-Climax: An evaluation of the technical feasibility of geologic storage of spent nuclear fuel in granite: Final report

    International Nuclear Information System (INIS)

    Patrick, W.C.

    1986-01-01

    In the Climax stock granite on the Nevada Test Site, eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized. When test data indicated that the test objectives were met during the 3-year storage phase, the spent-fuel canisters were retrieved and the thermal sources were de-energized. The project demonstrated the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner. In addition to emplacement and retrieval operations, three exchanges of spent-fuel assemblies between the SFT-C and a surface storage facility, conducted during the storage phase, furthered this demonstration. The test led to development of a technical measurements program. To meet these objectives, nearly 1000 instruments and a computer-based data acquisition system were deployed. Geotechnical, seismological, and test status data were recorded on a continuing basis for the three-year storage phase and six-month monitored cool-down of the test. This report summarizes the engineering and scientific endeavors which led to successful design and execution of the test. The design, fabrication, and construction of all facilities and handling systems are discussed, in the context of test objectives and a safety assessment. The discussion progresses from site characterization and experiment design through data acquisition and analysis of test data in the context of design calculations. 117 refs., 52 figs., 81 tabs

  9. Spent Fuel Test-Climax: An evaluation of the technical feasibility of geologic storage of spent nuclear fuel in granite: Final report

    Energy Technology Data Exchange (ETDEWEB)

    Patrick, W.C. (comp.)

    1986-03-30

    In the Climax stock granite on the Nevada Test Site, eleven canisters of spent nuclear reactor fuel were emplaced, and six electrical simulators were energized. When test data indicated that the test objectives were met during the 3-year storage phase, the spent-fuel canisters were retrieved and the thermal sources were de-energized. The project demonstrated the feasibility of packaging, transporting, storing, and retrieving highly radioactive fuel assemblies in a safe and reliable manner. In addition to emplacement and retrieval operations, three exchanges of spent-fuel assemblies between the SFT-C and a surface storage facility, conducted during the storage phase, furthered this demonstration. The test led to development of a technical measurements program. To meet these objectives, nearly 1000 instruments and a computer-based data acquisition system were deployed. Geotechnical, seismological, and test status data were recorded on a continuing basis for the three-year storage phase and six-month monitored cool-down of the test. This report summarizes the engineering and scientific endeavors which led to successful design and execution of the test. The design, fabrication, and construction of all facilities and handling systems are discussed, in the context of test objectives and a safety assessment. The discussion progresses from site characterization and experiment design through data acquisition and analysis of test data in the context of design calculations. 117 refs., 52 figs., 81 tabs.

  10. Studies in chemical dynamics and radiation chemistry. Technical progress report, 1 July 1974--30 June 1975

    International Nuclear Information System (INIS)

    Kuppermann, A.

    1975-01-01

    Research progress in the following areas is reported: low energy electron scattering; photoelectron spectrometry; elementary reactions by photolysis at variable wavelengths; collisions in crossed molecular beams; and, diffusion kinetics in the radiation chemistry of water. Publications related to the work are included. (JGB)

  11. Sodium boiling detection in LMFBRs (Phase I). 5th quarterly technical progress report, July 1, 1975--October 31, 1975

    International Nuclear Information System (INIS)

    Albrecht, R.W.; McCormick, N.J.

    1975-01-01

    Progress summarized includes the design of a gamma heated subassembly for sodium boiling experiments and an experiment showing that neutronic noise and acoustic noise caused by sodium boiling are highly correlated in a wide frequency band about the bubble repetition frequency

  12. Effects of Water Radiolysis in Water Cooled Reactors - Nuclear Energy Research Initiative (NERI) Program. Technical Progress Report

    International Nuclear Information System (INIS)

    Pimblott, S.M.

    2000-01-01

    OAK B188 Quarterly Progress Report on NERI Proposal No.99-0010 for the Development of an Experiment and Calculation Based Model to Describe the Effects of Radiation on Non-standard Aqueous Systems Like Those Encountered in the Advanced Light Water Reactor

  13. Effects of humic substances on the migration of radionuclides: complexation and transport of actinides. First technical progress report (work period 01.97 - 12.97)

    International Nuclear Information System (INIS)

    Buckau, G.

    1998-08-01

    The present report describes progress within the first year of the EC-project 'Effects of Humic Substances on the Migration of Radionuclides: Complexation and Transport of Actinides'. The project is conducted within the EC-Cluster 'Radionuclide Transport/Retardation Processes'. Contrary to formal requirements of the Commission, this report with a great deal of detail is established already after one year of project work. It is scheduled to be followed by a second technical progress report covering the second year of the project. In agreement with the contractual obligations a final report of similar technical detail will also be generated. The report contains an executive summary written by the coordinator (FZK/INE) with strong support from the other three task leaders (BGS, CEA-SGC and RMC-E). More detailed results are given by individual contributions of the project partners in 13 annexes. In the executive summary report the origin of results presented is given, also serving as guidance for finding more detailed results in the annexes. Not all results are discussed or referred to in the executive summary report and thus readers with a deeper interest also need to consult the annexes. (orig.)

  14. Progress in control and data acquisition for the ITER neutral beam test facility

    Energy Technology Data Exchange (ETDEWEB)

    Luchetta, Adriano, E-mail: adriano.luchetta@igi.cnr.it [Consorzio RFX, Euratom-ENEA Association, Padova (Italy); Manduchi, Gabriele; Taliercio, Cesare; Soppelsa, Anton [Consorzio RFX, Euratom-ENEA Association, Padova (Italy); Paolucci, Francesco; Sartori, Filippo [Fusion for Energy, Barcelona (Spain); Barbato, Paolo; Capobianco, Roberto; Breda, Mauro; Molon, Federico; Moressa, Modesto; Polato, Sandro; Simionato, Paola; Zampiva, Enrico [Consorzio RFX, Euratom-ENEA Association, Padova (Italy)

    2013-10-15

    Highlights: ► An ion source experiment, referred to as SPIDER, is under construction in the ITER neutral beam test facility. ► The progress in designing and testing the SPIDER control and data acquisition system is reported. ► An original approach is proposed in using ITER CODAC and non-ITER CODAC technology. -- Abstract: SPIDER, the ion source test bed in the ITER neutral beam test facility, is under construction and its operation is expected to start in 2014. Control and data acquisition for SPIDER are undergoing final design. SPIDER CODAS, as the control and data acquisition system is referred to, is requested to manage 25 plant units, to acquire 1000 analogue signals with sampling rates ranging from a few S/s to 10 MS/s, to acquire images with up to 100 frames per second, to operate with long pulses lasting up to 1 h, and to sustain 200 MB/s data throughput into the data archive with an annual data storage amount of up to 50 TB. SPIDER CODAS software architecture integrates three open-source software frameworks each addressing specific system requirements. Slow control exploits the synergy among EPICS and Siemens S7 programmable controllers. Data handling is by MDSplus a data-centric framework that is geared towards the collection and organization of scientific data. Diagnostics based on imaging drive the design of data throughput and archive size. Fast control is implemented by using MARTe, a data-driven, object-oriented, real-time environment. The paper will describe in detail the progress of the system hardware and software architecture and will show how the software frameworks interact to provide the functions requested by SPIDER CODAS. The paper will focus on how the performance requirements can be met with the described SPIDER CODAS architecture, describing the progress achieved by carrying out prototyping activities.

  15. Progress in control and data acquisition for the ITER neutral beam test facility

    International Nuclear Information System (INIS)

    Luchetta, Adriano; Manduchi, Gabriele; Taliercio, Cesare; Soppelsa, Anton; Paolucci, Francesco; Sartori, Filippo; Barbato, Paolo; Capobianco, Roberto; Breda, Mauro; Molon, Federico; Moressa, Modesto; Polato, Sandro; Simionato, Paola; Zampiva, Enrico

    2013-01-01

    Highlights: ► An ion source experiment, referred to as SPIDER, is under construction in the ITER neutral beam test facility. ► The progress in designing and testing the SPIDER control and data acquisition system is reported. ► An original approach is proposed in using ITER CODAC and non-ITER CODAC technology. -- Abstract: SPIDER, the ion source test bed in the ITER neutral beam test facility, is under construction and its operation is expected to start in 2014. Control and data acquisition for SPIDER are undergoing final design. SPIDER CODAS, as the control and data acquisition system is referred to, is requested to manage 25 plant units, to acquire 1000 analogue signals with sampling rates ranging from a few S/s to 10 MS/s, to acquire images with up to 100 frames per second, to operate with long pulses lasting up to 1 h, and to sustain 200 MB/s data throughput into the data archive with an annual data storage amount of up to 50 TB. SPIDER CODAS software architecture integrates three open-source software frameworks each addressing specific system requirements. Slow control exploits the synergy among EPICS and Siemens S7 programmable controllers. Data handling is by MDSplus a data-centric framework that is geared towards the collection and organization of scientific data. Diagnostics based on imaging drive the design of data throughput and archive size. Fast control is implemented by using MARTe, a data-driven, object-oriented, real-time environment. The paper will describe in detail the progress of the system hardware and software architecture and will show how the software frameworks interact to provide the functions requested by SPIDER CODAS. The paper will focus on how the performance requirements can be met with the described SPIDER CODAS architecture, describing the progress achieved by carrying out prototyping activities

  16. Lead Coolant Test Facility Technical and Functional Requirements, Conceptual Design, Cost and Construction Schedule

    International Nuclear Information System (INIS)

    Soli T. Khericha

    2006-01-01

    This report presents preliminary technical and functional requirements (T and FR), thermal hydraulic design and cost estimate for a lead coolant test facility. The purpose of this small scale facility is to simulate lead coolant fast reactor (LFR) coolant flow in an open lattice geometry core using seven electrical rods and liquid lead or lead-bismuth eutectic. Based on review of current world lead or lead-bismuth test facilities and research need listed in the Generation IV Roadmap, five broad areas of requirements of basis are identified: Develop and Demonstrate Prototype Lead/Lead-Bismuth Liquid Metal Flow Loop Develop and Demonstrate Feasibility of Submerged Heat Exchanger Develop and Demonstrate Open-lattice Flow in Electrically Heated Core Develop and Demonstrate Chemistry Control Demonstrate Safe Operation and Provision for Future Testing. These five broad areas are divided into twenty-one (21) specific requirements ranging from coolant temperature to design lifetime. An overview of project engineering requirements, design requirements, QA and environmental requirements are also presented. The purpose of this T and FRs is to focus the lead fast reactor community domestically on the requirements for the next unique state of the art test facility. The facility thermal hydraulic design is based on the maximum simulated core power using seven electrical heater rods of 420 kW; average linear heat generation rate of 300 W/cm. The core inlet temperature for liquid lead or Pb/Bi eutectic is 420 C. The design includes approximately seventy-five data measurements such as pressure, temperature, and flow rates. The preliminary estimated cost of construction of the facility is $3.7M. It is also estimated that the facility will require two years to be constructed and ready for operation

  17. Preschool Multiple-Breath Washout Testing. An Official American Thoracic Society Technical Statement.

    Science.gov (United States)

    Robinson, Paul D; Latzin, Philipp; Ramsey, Kathryn A; Stanojevic, Sanja; Aurora, Paul; Davis, Stephanie D; Gappa, Monika; Hall, Graham L; Horsley, Alex; Jensen, Renee; Lum, Sooky; Milla, Carlos; Nielsen, Kim G; Pittman, Jessica E; Rosenfeld, Margaret; Singer, Florian; Subbarao, Padmaja; Gustafsson, Per M; Ratjen, Felix

    2018-03-01

    Obstructive airway disease is nonuniformly distributed throughout the bronchial tree, although the extent to which this occurs can vary among conditions. The multiple-breath washout (MBW) test offers important insights into pediatric lung disease, not available through spirometry or resistance measurements. The European Respiratory Society/American Thoracic Society inert gas washout consensus statement led to the emergence of validated commercial equipment for the age group 6 years and above; specific recommendations for preschool children were beyond the scope of the document. Subsequently, the focus has shifted to MBW applications within preschool subjects (aged 2-6 yr), where a "window of opportunity" exists for early diagnosis of obstructive lung disease and intervention. This preschool-specific technical standards document was developed by an international group of experts, with expertise in both custom-built and commercial MBW equipment. A comprehensive review of published evidence was performed. Recommendations were devised across areas that place specific age-related demands on MBW systems. Citing evidence where available in the literature, recommendations are made regarding procedures that should be used to achieve robust MBW results in the preschool age range. The present work also highlights the important unanswered questions that need to be addressed in future work. Consensus recommendations are outlined to direct interested groups of manufacturers, researchers, and clinicians in preschool device design, test performance, and data analysis for the MBW technique.

  18. Progress Testing for Medical Students at the University of Auckland: Results from the First Year of Assessments

    Directory of Open Access Journals (Sweden)

    Steven Lillis

    2014-01-01

    Full Text Available Background Progress testing is a method of assessing longitudinal progress of students using a single best answer format pitched at the standard of a newly graduated doctor. Aim To evaluate the results of the first year of summative progress testing at the University of Auckland for Years 2 and 4 in 2013. SUBJECTS: Two cohorts of medical students from Years 2 and 4 of the Medical Program. Methods A survey was administered to all involved students. Open text feedback was also sought. Psychometric data were collected on test performance, and indices of reliability and validity were calculated. Results The three tests showed increased mean scores over time. Reliability of the assessments was uniformly high. There was good concurrent validity. Students believe that progress testing assists in integrating science with clinical knowledge and improve learning. Year 4 students reported improved knowledge retention and deeper understanding. Conclusion Progress testing has been successfully introduced into the Faculty for two separate year cohorts and results have met expectations. Other year cohorts will be added incrementally. Recommendation Key success factors for introducing progress testing are partnership with an experienced university, multiple and iterative briefings with staff and students as well as demonstrating the usefulness of progress testing by providing students with detailed feedback on performance.

  19. 1993 Annual progress report for subsidiary agreement No. 2 (1991--1996) between AECL and US/DOE for a radioactive waste management technical co-operative program

    International Nuclear Information System (INIS)

    1993-01-01

    A coordinated research program on radioactive waste disposal is being carried out by the Atomic Energy of Canada Limited and the US Department of Energy. This annual report describes progress in the following eight studies: Fundamental materials investigations; In-situ stress determination; Development of a spent fuel dissolution model; Large block tracer test--Experimental testing of retardation models; Laboratory and field tests of in-situ hydrochemical tools; Cigar Lake--Analogue study, actinide and fission product geochemistry; Performance assessment technology exchange; and Development of multiple-well hydraulic test and field tracer test methods

  20. 1993 Annual progress report for subsidiary agreement No. 2 (1991--1996) between AECL and US/DOE for a radioactive waste management technical co-operative program

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-12-31

    A coordinated research program on radioactive waste disposal is being carried out by the Atomic Energy of Canada Limited and the US Department of Energy. This annual report describes progress in the following eight studies: Fundamental materials investigations; In-situ stress determination; Development of a spent fuel dissolution model; Large block tracer test--Experimental testing of retardation models; Laboratory and field tests of in-situ hydrochemical tools; Cigar Lake--Analogue study, actinide and fission product geochemistry; Performance assessment technology exchange; and Development of multiple-well hydraulic test and field tracer test methods.

  1. Psychometric Investigation of the Raven's Colored Progressive Matrices Test in a Sample of Preschool Children.

    Science.gov (United States)

    Lúcio, Patrícia Silva; Cogo-Moreira, Hugo; Puglisi, Marina; Polanczyk, Guilherme Vanoni; Little, Todd D

    2017-11-01

    The present study investigated the psychometric properties of the Raven's Colored Progressive Matrices (CPM) test in a sample of preschoolers from Brazil ( n = 582; age: mean = 57 months, SD = 7 months; 46% female). We investigated the plausibility of unidimensionality of the items (confirmatory factor analysis) and differential item functioning (DIF) for sex and age (multiple indicators multiple causes method). We tested four unidimensional models and the one with the best-fit index was a reduced form of the Raven's CPM. The DIF analysis was carried out with the reduced form of the test. A few items presented DIF (two for sex and one for age), confirming that the Raven's CPM items are mostly measurement invariant. There was no effect of sex on the general factor, but increasing age was associated with higher values of the g factor. Future research should indicate if the reduced form is suitable for evaluating the general ability of preschoolers.

  2. JOYO-1 Irradiation Test Campaign Technical Close-out, For Information

    International Nuclear Information System (INIS)

    G. Borges

    2006-01-01

    The JOYO-1 irradiation testing was designed to screen the irradiation performance of candidate cladding, structural and reflector materials in support of space reactor development. The JOYO-1 designation refers to the first of four planned irradiation tests in the JOYO reactor. Limited irradiated material performance data for the candidate materials exists for the expected Prometheus-1 duration, fluences and temperatures. Materials of interest include fuel element cladding and core materials (refractory metal alloys and silicon carbide (Sic)), vessel and plant structural materials (refractory metal alloys and nickel-base superalloys), and control and reflector materials (BeO). Key issues to be evaluated were long term microstructure and material property stability. The JOYO-1 test campaign was initiated to irradiate a matrix of specimens at prototypical temperatures and fluences anticipated for the Prometheus-1 reactor [Reference (1)]. Enclosures 1 through 9 describe the specimen and temperature monitors/dosimetry fabrication efforts, capsule design, disposition of structural material irradiation rigs, and plans for post-irradiation examination. These enclosures provide a detailed overview of Naval Reactors Prime Contractor Team (NRPCT) progress in specific areas; however, efforts were in various states of completion at the termination of NRPCT involvement with and restructuring of Project Prometheus

  3. JOYO-1 Irradiation Test Campaign Technical Close-out, For Information

    Energy Technology Data Exchange (ETDEWEB)

    G. Borges

    2006-01-31

    The JOYO-1 irradiation testing was designed to screen the irradiation performance of candidate cladding, structural and reflector materials in support of space reactor development. The JOYO-1 designation refers to the first of four planned irradiation tests in the JOYO reactor. Limited irradiated material performance data for the candidate materials exists for the expected Prometheus-1 duration, fluences and temperatures. Materials of interest include fuel element cladding and core materials (refractory metal alloys and silicon carbide (Sic)), vessel and plant structural materials (refractory metal alloys and nickel-base superalloys), and control and reflector materials (BeO). Key issues to be evaluated were long term microstructure and material property stability. The JOYO-1 test campaign was initiated to irradiate a matrix of specimens at prototypical temperatures and fluences anticipated for the Prometheus-1 reactor [Reference (1)]. Enclosures 1 through 9 describe the specimen and temperature monitors/dosimetry fabrication efforts, capsule design, disposition of structural material irradiation rigs, and plans for post-irradiation examination. These enclosures provide a detailed overview of Naval Reactors Prime Contractor Team (NRPCT) progress in specific areas; however, efforts were in various states of completion at the termination of NRPCT involvement with and restructuring of Project Prometheus.

  4. Progress in sensor performance testing, modeling and range prediction using the TOD method: an overview

    Science.gov (United States)

    Bijl, Piet; Hogervorst, Maarten A.; Toet, Alexander

    2017-05-01

    The Triangle Orientation Discrimination (TOD) methodology includes i) a widely applicable, accurate end-to-end EO/IR sensor test, ii) an image-based sensor system model and iii) a Target Acquisition (TA) range model. The method has been extensively validated against TA field performance for a wide variety of well- and under-sampled imagers, systems with advanced image processing techniques such as dynamic super resolution and local adaptive contrast enhancement, and sensors showing smear or noise drift, for both static and dynamic test stimuli and as a function of target contrast. Recently, significant progress has been made in various directions. Dedicated visual and NIR test charts for lab and field testing are available and thermal test benches are on the market. Automated sensor testing using an objective synthetic human observer is within reach. Both an analytical and an image-based TOD model have recently been developed and are being implemented in the European Target Acquisition model ECOMOS and in the EOSTAR TDA. Further, the methodology is being applied for design optimization of high-end security camera systems. Finally, results from a recent perception study suggest that DRI ranges for real targets can be predicted by replacing the relevant distinctive target features by TOD test patterns of the same characteristic size and contrast, enabling a new TA modeling approach. This paper provides an overview.

  5. Research and development on optically pumped polarized ion sources. Technical progress report, February 1, 1985-January 31, 1986

    International Nuclear Information System (INIS)

    Anderson, L.W.

    1985-07-01

    During the past year we have studied the relaxation times in an optically pumped 23 Na vapor target, studied the effects of radiation trapping on the polarization in a Na vapor target, and have studied the effects of spin exchange collisions on a beam of fast H 0 atoms as they pass through a polarized alkali target. This research is directed toward improvements in the optically pumped Na or other alkali vapor targets used for the production of polarized H - ions. In this progress report we review the properties of the optically pumped polarized H - ion source as well as discussing the progress of our research on optically pumped Na or other alkali vapor targets. 81 refs., 9 figs

  6. Technical progress report of biological research on the Volcanic Island Surtsey and its environs for the period 1965--1978

    Energy Technology Data Exchange (ETDEWEB)

    Fridriksson, S.

    1978-01-01

    Progress is reported on the following research projects: changes in shoreline and surface of the island due to volcanic activity; colonization of microorganisms, algae, lichens, and vascular plants; introduction of insects and other arthropods by wind, water, and man; transport of invertebrates to the island by flotsam of the sea; species and nesting habits of birds on the island; behavior of seals on beaches of the island; and future trends of Surtsey ecosystems. (HLW)

  7. Research proposal and annual report No. 16. Part B. Technical progress, September 1, 1975--August 31, 1976

    Energy Technology Data Exchange (ETDEWEB)

    1976-06-01

    Progress is reported on the following research projects: RNA synthesis in yeast; regulation of nitrogen metabolism; biological toxicity of intracellular radioisotope decay; the mechanism of energy conversion in chloroplasts; promoting vibrations in spin-orbital coupling in vibrationally deficient molecules; electronic excitation and hydrogen bonding; macromolecular biophysics; the synthesis and maturation of RNA; electronic response properties of biomolecular systems; chromosome structure and function and chromosome damage; DNA replication and chromosome structure; and influence of phospholipids on the dynamic properties of rhodopsin. (HLW)

  8. Research proposal and annual report No. 16. Part B. Technical progress, September 1, 1975--August 31, 1976

    International Nuclear Information System (INIS)

    1976-01-01

    Progress is reported on the following research projects: RNA synthesis in yeast; regulation of nitrogen metabolism; biological toxicity of intracellular radioisotope decay; the mechanism of energy conversion in chloroplasts; promoting vibrations in spin-orbital coupling in vibrationally deficient molecules; electronic excitation and hydrogen bonding; macromolecular biophysics; the synthesis and maturation of RNA; electronic response properties of biomolecular systems; chromosome structure and function and chromosome damage; DNA replication and chromosome structure; and influence of phospholipids on the dynamic properties of rhodopsin

  9. Progress of the RERTR [Reduced Enrichment Research and Test Reactor] Program in 1989

    International Nuclear Information System (INIS)

    Travelli, A.

    1989-01-01

    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 1988, the major events, findings, and activities of 1989 are reviewed. The scope of the RERTR Program activities was curtailed, in 1989, by an unexpected legislative restriction which limited the ability of the Arms Control and Disarmament Agency to adequately fund the program. Nevertheless, the thrust of the major planned program activities was maintained, and meaningful results were obtained in several areas of great significance for future work. 15 refs., 12 figs

  10. Progress towards extreme attitude testing with Magnetic Suspension and Balance Systems

    Science.gov (United States)

    Britcher, Colin P.; Parker, David H.

    1988-01-01

    Progress is reported in a research effort aimed towards demonstration of the feasibility of suspension and aerodynamic testing of models at high angles of attack in wind tunnel Magnetic Suspension and Balance Systems. Extensive modifications, described in this paper, have been made to the Southampton University suspension system in order to facilitate this work. They include revision of electromagnet configuration, installation of all-new position sensors and expansion of control system programs. An angle of attack range of 0 to 90 deg is expected for axisymmetric models. To date, suspension up to 80 deg angle of attack has been achieved.

  11. Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Part 3. Safety assessment for geological disposal systems

    International Nuclear Information System (INIS)

    1999-11-01

    Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, the part 3 of the progress report, concerns safety assessment for geological disposal systems definitely introduced in part 1 and 2 of this series and consists of 9 chapters. Chapter I concerns the methodology for safety assessment while Chapter II deals with diversity and uncertainty about the scenario, the adequate model and the required data of the systems above. Chapter III summarizes the components of the geological disposal system. Chapter IV refers to the relationship between radioactive wastes and human life through groundwater, i.e. nuclide migration. In Chapter V is made a reference case which characterizes the geological environmental data using artificial barrier specifications. (Ohno. S.)

  12. Technical reliability of geological disposal for high-level radioactive wastes in Japan. The second progress report. Part 2. Engineering technology for geological disposal

    International Nuclear Information System (INIS)

    1999-11-01

    Based on the Advisory Committee Report on Nuclear Fuel Cycle Backend Policy submitted to the Japanese Government in 1997, JNC documents the progress of research and development program in the form of the second progress report (the first one published in 1992). It summarizes an evaluation of the technical reliability and safety of the deep geological disposal concept for high-level radioactive wastes (HLW) in Japan. The present document, part 2 of the progress report, concerns engineering aspect with reference to Japanese geological disposal plan, according to which the vitrified HLW will be disposed of into a deep, stable rock mass with thick containers and surrounding buffer materials at the depth of several hundred meters. It discusses on multi-barrier systems consisting of a series of engineered and natural barriers that will isolate radioactive nuclides effectively and retard their migrations to the biosphere environment. Performance of repository components, including specifications of containers for vitrified HLW and their overpacks under design as well as buffer material such as Japanese bentonite to be placed in between are described referring also to such possible problems as corrosion arising from the supposed system. It also presents plans and designs for underground disposal facilities, and the presumed management of the underground facilities. (Ohno, S.)

  13. Transfer of Air Force technical procurement bid set data to small businesses, using CALS and EDI: Test report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-08-15

    This report documents a test transfer of three Air Force technical procurement bid sets to one large and twelve small businesses, using the Department of Defense (DoD) Continuous Acquisition and Life-cycle Support (CALS) and ANSI ASC X12 Electronic Data Interchange (EDI) standards. The main goal of the test was to evaluate the effectiveness of using CALS technical data within the context of the DoD`s EDI-based standard approach to electronic commerce in procurement, with particular emphasis on receipt and use of the data by small contractors. Air Force procurement data was provided by the Sacramento Air Logistics Center at McClellan Air Force Base; the manufacturing participants were selected from among McClellan`s ``Blue Ribbon`` contractors, located throughout the US. The test was sponsored by the Air Force CALS Test Network, headquartered at Wright-Patterson Air Force Base. The test successfully demonstrated the technical feasibility of including CALS MIL-R-28002 (Raster) engineering data in an EDI Specification/Technical Information transaction set (ANSI ASC X12 841) when issuing electronic requests for quotation to small businesses. In many cases, the data was complete enough for the contractor participant to feel comfortable generating a quote. Lessons learned from the test are being fed back to the CALS and EDI standards organizations, and to future implementors of CALS-EDI based acquisition or contracting systems, which require the transfer of technical information, such as engineering data, manufacturing process data, quality test data, and other product or process data, in the form of a CALS or other digital datafile.

  14. Test-retest reliability of the Progressive Isoinertial Lifting Evaluation (PILE).

    Science.gov (United States)

    Lygren, Hildegunn; Dragesund, Tove; Joensen, Jón; Ask, Tove; Moe-Nilssen, Rolf

    2005-05-01

    A repeated measures single group design. To investigate test-retest reliability of Progressive Isoinertial Lifting Evaluation on patients with long lasting musculoskeletal problems related to the lumbar spine. Test-retest reliability has been satisfactory in healthy men. Test-retest reliability for clinical populations has not been reported. A total of 31 patients (17 women and 14 men) with long lasting low back pain participated in the study. The patients were tested twice at an interval of 2 days and at the same time of the day. The heaviest load that the patient could lift 4 times was used as outcome measure. The error of measurement indicates that the true result in 95% of cases will be within +/-4.5 kg from the measured value, while the difference between 2 measurements in 95% of cases will be less than 6.4 kg. Intra-class correlation (1,1) was 0.91. Relative test-retest reliability was high assessed by intra-class correlation, but absolute measurement variability reported as the smallest detectable difference has relevance for the interpretation of clinical test results and should also be considered.

  15. GPHS-RTGs in support of the Cassini Mission. Semi-annual technical progress report, April 3, 1995--October 1, 1995

    International Nuclear Information System (INIS)

    1995-01-01

    This document is the April-October 1995 Progress Report on the Cassini RTG Program. Nine tasks are summarized; (1) Spacecraft integration and liason, (2) Engineering support, (3) Safety, (4) Unicouple fabrication, (5) ETG fabrication, assembly, and test, (6) Ground support equipment, (7) RTG shipping and launch support, (8) Design, reviews, and mission applications, and (9) Project management, QA, contract changes, and material acquisitions

  16. Proceedings of a technical session on rock mechanics ''Advance in laboratory sample testing''

    International Nuclear Information System (INIS)

    Come, B.

    1984-01-01

    This report brings together a series of papers about rock mechanics. The meeting was divided into three sessions, which dealt with the three main types of rock formation currently considered in the CEC Programme: granite, clay and salt. Safe disposal of high-level radioactive waste involves the proper design of deep underground repositories. This necessitates an in-depth knowledge of the mechanical properties of the rock mass. The behaviour of the rock mass must be known both for the construction and the operation (heating effects) of the repository. Usually, the dominant factor for designing an underground structure is the fracturing of the rock mass. In the present case, the rock is chosen with a very low fracturing. Therefore, the mechanical properties of the formation are mainly those of the rock matrix. These properties are obtained, at least in a first exploratory step, by laboratory testing of rock samples obtained by core-drilling from surface. This aspect of rock characterization was thought to deserve a special technical meeting, in order to bring together most of the results obtained in this field by contracting partners of the CEC for the years 1980-82

  17. TECHNICAL COORDINATION

    CERN Multimedia

    Austin Ball

    Summary of progress since last CMS week. Ten years of construction work have been completed. CMS is closed, in very close to the ideal low luminosity configuration, and performed well in the first tests with LHC beam. Behind this encouraging news is the story of a summer of intense commitment by many teams (from the collaboration and 3 CERN departments) working together, against the clock and despite many minor setbacks, to ensure that the experiment was ready to play a leading role in the excitement of September 10. Following beampipe bakeout and refill with pure neon, a magnificent effort by the ECAL group and the pt 5 technical crew made it possible to install and commission all 4 ECAL endcap Dees before the end of August. In the shadow of this activity, the barrel and forward pixel trackers and part of the beam monitoring were installed within the vac tank. The pt 5 technical teams then succeeded in safely removing the 20t installation tables and their support blocks from beneath the already installed ...

  18. The RERTR [Reduced Enrichment Research and Test Reactor] Program: Progress and plans

    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 occurred 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 US 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

  19. Gas-Cooled Thermal Reactor Program. Annual technical progress report for the period ending September 30, 1981

    International Nuclear Information System (INIS)

    1982-03-01

    This report provides descriptions and results of the technical effort during FY81 on the Gas-Cooled Thermal Reactor Program. The FY81 work was organized according to the Work Breakdown Structure (WBS) for the National HTGR Program, and fell within five of the WBS tasks. The work on Market Definition and Development (WBS 03) was associated with estimating product costs for HTGR systems and their alternatives, projecting markets and market penetrations for these systems, and providing costs and market input to application analyses and component design. The Plant Technology (WBS 13) effort was mainly in the development of the systems dynamic computer code, STAR, for the transient analysis of HTGR's in reformer applications. The analysis of pebble bed reactors (PBR) was performed under Technology Transfer (WBS 15). The effort on components and systems within the nuclear heat source for reforming plants was performed under High Temperature Nuclear Heat Source (WBS 42)

  20. Realization of radiation-chemical processes in national economy-important stage of scientific and technical progress

    International Nuclear Information System (INIS)

    Breger, A.Kh.

    1975-01-01

    Realization of energy resourses of the atomic power engineering will greatly contribute to the scientific and technological progress. The dominat role play the radiochemical methods of properties modification applied for the well-known materials and for the production of materials with modern operating characteristics necessary for their application in different branches of industry and agriculture. Radiation modeling of products from polyolefine, wood-plastic and concrete-polymer materials are considered as well as the processes in ''thin'' units of agitating systems. The future developments and present state of the art of radiation sources are presented

  1. Recent progress and tests of radiation resistant impregnation materials for Nb3Sn coils

    Science.gov (United States)

    Bossert, R.; Krave, S.; Ambrosio, G.; Andreev, N.; Chlachidze, G.; Nobrega, A.; Novitski, I.; Yu, M.; Zlobin, A. V.

    2014-01-01

    Fermilab is collaborating with Lawrence Berkeley National Laboratory (LBNL) and Brookhaven National Laboratory (BNL) (US-LARP collaboration) to develop a large-aperture Nb3Sn superconducting quadrupole for the Large Hadron Collider (LHC) luminosity upgrade. An important component of this work is the development of materials that are sufficiently radiation resistant for use in critical areas of the upgrade. This paper describes recent progress in characterization of materials, including the baseline CTD101K epoxy, cyanate ester blends, and Matrimid 5292, a bismaleimide-based system. Structural properties of "ten stacks" of cable impregnated with these materials are tested at room and cryogenic temperatures and compared to the baseline CT-101K. Experience with potting 1 and 2 meter long coils with Matrimid 5292 are described. Test results of a single 1-m coil impregnated with Matrimid 5292 are reported and compared to similar coils impregnated with the traditional epoxy.

  2. Recent progress and tests of radiation resistant impregnation materials for Nb3Sn coils

    International Nuclear Information System (INIS)

    Bossert, R.; Krave, S.; Ambrosio, G.; Andreev, N.; Chlachidze, G.; Nobrega, A.; Novitski, I.; Yu, M.; Zlobin, A. V.

    2014-01-01

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

  3. Validity of GRE General Test Scores and TOEFL Scores for Graduate Admission to a Technical University in Western Europe

    Science.gov (United States)

    Zimmermann, Judith; von Davier, Alina A.; Buhmann, Joachim M.; Heinimann, Hans R.

    2018-01-01

    Graduate admission has become a critical process in tertiary education, whereby selecting valid admissions instruments is key. This study assessed the validity of Graduate Record Examination (GRE) General Test scores for admission to Master's programmes at a technical university in Europe. We investigated the indicative value of GRE scores for the…

  4. Committee on Atomic, Molecular, and Optical Sciences (CAMOS). Technical progress report ampersand continuation proposal, February 1, 1993--January 31, 1994

    International Nuclear Information System (INIS)

    Taylor, R.D.

    1997-01-01

    The Committee on Atomic, Molecular and Optical Sciences (CAMOS) of the National Research Council (NRC) is charged with monitoring the health of the field of atomic, molecular, and optical (AMO) science in the United States. Accordingly, the Committee identifies and examines both broad and specific issues affecting the field. Regular meetings, teleconferences, briefings from agencies and the scientific community, the formation of study panels to prepare reports, and special symposia are among the mechanisms used by the CAMOS to meet its charge. This progress report presents a review of CAMOS activities from February 1, 1993 to January 31, 1994. The details of prior activities are discussed in earlier progress reports. This report also includes the status of activities associated with the CAMOS study on the field that is being conducted by the Panel on the Future of Atomic, Molecular, and Optical Sciences (FAMOS). During the above period, CAMOS has continued to track and participate in, when requested, discussions on the health of the field. Much of the perspective of CAMOS has been presented in the recently-published report Research Briefing on Selected Opportunities in Atomic, Molecular, and Optical Sciences. That report has served as the basis for briefings to representatives of the federal government as well as the community-at-large. In keeping with its charge to monitor the health of the field, CAMOS launched a study designed to highlight future directions of the field

  5. Bioremediation of mixed microbial mats: System development of mixed contaminants for application at the Savannah River Site. Annual technical progress report, October 1, 1995--September 30, 1996

    International Nuclear Information System (INIS)

    Bender, J.; Phillips, P.

    1996-01-01

    The fundamental objective of this project is to develop and field test the mixed microbial mat bioremediation system for decontamination of target sites at SRS. Although microbial mats have performed well in several pilot projects in the past, atypical problems and site characteristics at SRS demand special field designs. In the interest of designing a pilot and locating it at an appropriate site, the project investigators have worked closely with the technical staff at the SREL. We have concluded that the diverse characteristics of contaminations at SRS may dictate testing several pilot designs during the course of this project

  6. Overview of the Last Progresses for the European Test Blanket Modules Projects

    International Nuclear Information System (INIS)

    Salavy, J.-F.; Rampal, G.; Boccaccini, L.V.; Meyder, R.; Neuberger, H.; Laesser, R.; Poitevin, Y.; Zmitko, M.; Rigal, E.

    2006-01-01

    The long-term objective of the EU Breeding Blankets programme is the development of DEMO breeding blankets, which shall assure tritium self-sufficiency, an economically attractive use of the heat produced inside the blankets for electricity generation and a sufficiently high shielding of the superconducting magnets for long time operation. In the short-term so-called DEMO relevant Test Blanket Modules (TBMs) of these breeder blanket concepts shall be designed, manufactured, tested, installed, commissioned and operated in ITER for first tests in a fusion environment. The Helium Cooled Lithium-Lead (HCLL) breeder blanket and the Helium Cooled Pebble Bed (HCPB) concepts are the two breeder blanket lines presently developed by the EU. The main objective of the EU test strategy related to TBMs in ITER is to provide the necessary information for the design and fabrication of breeding blankets for a future DEMO reactor. EU TBMs shall therefore use the same structural and functional materials, apply similar fabrication technologies, and test adequate processes and components. This paper gives an overview of the last progresses in terms of system design, calculations, test program, safety and R-and-D done these last two years in order to cope with the ambitious objective to introduce two EU TBM systems for day-1 of ITER operation. The engineering design of the two systems is mostly concluded and the priority is now on the development and qualification of the fabrication technologies. From calculations point of view, the last modelling efforts related to the thermal-hydraulic of the first wall, the tritium behaviour, and the box thermal and mechanical resistance in accidental conditions are presented. Last features of the TBM and cooling system designs and integration in ITER reactor are highlighted. In particular, this paper also describes the safety and licensing analyses performed for each concept to be able to include the TBM systems in the ITER preliminary safety report

  7. Theoretical research in intermediate-energy nuclear physics. [Technical progress report, April 1, 1993--March 31, 1994

    International Nuclear Information System (INIS)

    Seki, R.

    1994-01-01

    This paper discusses progress that has been made on the following seven problems: (1) (e, e'p) at high momentum transfer; (2) post,acceleration effects in two-nucleon interferometry of heavy-ion collisions; (3) pion-nucleus interactions above 0.5 GeV; (4) chiral symmetry breaking in nuclei and picnic atom anomaly; (5) atomic screening on nuclear astronomical reactions; (6) QCD related work (coherent pion production from skyrmion-antiskyrmion annihilation, QCD in 1 + 1 dimensions, and correlation functions in the QCD vacuum), and (7) kaonic hydrogen atom experiment. The problems deal with various topics mostly in intermediate-energy nuclear physics. We place priority on (1) and (2), and describe them somewhat in detail below. Other problems are our on-going projects, but we are placing lower priority on them in the second and third year

  8. Measurements of scattering processes in negative ion: Atom collisions. Technical progress report, 1 September 1991--31 December 1994

    International Nuclear Information System (INIS)

    Kvale, T.J.

    1994-01-01

    This report describes the progress made on the research objectives during the past three years of the grant. This research project is designed to study various scattering processes which occur in H - collisions with atomic (specifically, noble gas and atomic hydrogen) targets in the intermediate energy region. These processes include: elastic scattering, single- and double-electron detachment, and target excitation/ionization. For the elastic and target inelastic processes where H - is scattered intact, the experimental technique of Ion Energy-Loss Spectroscopy (IELS) will be employed to identify the final target state(s). In most of the above processes, cross sections are unknown both experimentally and theoretically. The measurements will provide total cross sections (TCS) initially, and once the angular positioning apparatus is installed, will provide angular differential cross sections (ADCS)

  9. AFCT/TFCT/ISFS Program. Technical progress report for the period October 1, 1977--December 31, 1977

    Energy Technology Data Exchange (ETDEWEB)

    Hill, O.F. (comp.)

    1978-02-01

    This is the eighth in a series of quarterly progress reports on studies performed for the Alternate Fuel Cycle Technologies/Thorium Fuel Cycle Technologies/International Spent Fuel Receipt and Storage (AFCT/TFCT/ISFS) Program, formerly the LWR Fuel Recycle Program. This program is designed to provide information needed by industry to close the back end of the power reactor fuel cycle. During the past quarter, studies were conducted in the following tasks: Survey of Current Technology of Fuel Handling Techniques; Investigation of Air Cleaning Processes for Removing Tributyl Phosphate (TBP) from Off-Gas Streams; Study of Iodine Chemistry in Process Solutions; Electropolishing to Decontaminate Metallic Waste from Alternate and Thorium Converter Fuel Cycles; and U.S. Scale Transport, Dispersion and Removal Mode Comparison Safety Criticality Experiments. (11 figs., 7 tables)

  10. Combined macroscopic and microscopic approach to the fracture of metals. Technical progress report, July 1975--June 1976

    International Nuclear Information System (INIS)

    Gurland, J.; Rice, J.R.; Asaro, R.J.; Needleman, A.

    1976-07-01

    Major studies have been started on (1) The conditions governing the localization of plastic flow at the onset of rupture. Specific calculations of critical conditions for a number of material models have been made possible through a theoretical framework by which localization is formulated as a constitutive instability, in the form of a bifurcation into a localized mode from a state of previously homogeneous deformation, and (2) The strength of interfaces with and without the presence of dissolved segregants. Criteria for brittle vs. ductile response of an interface were developed on the basis of dislocation mechanisms and thermodynamic relations, and applied to hydrogen embrittlement. Further progress has been achieved in the analysis of stress and deformation at a crack tip by the application of the large-strain elastic-plastic finite element program developed over the last two years. Work has continued on particle and sub-boundary strengthening in steels and an experimental study of fracture initiation at particles was begun

  11. AFCT/TFCT/ISFS Program. Technical progress report for the period April 1, 1978--June 30, 1978

    Energy Technology Data Exchange (ETDEWEB)

    Hill, O.F. (comp.)

    1978-08-01

    This is the tenth in a series of quarterly progress reports on studies performed for the Alternate Fuel Cycle Technologies/Thorium Fuel Cycle Technologies/International Spent Fuel Receipt and Storage (AFCT/TFCT/ISFS) Program. This program provides information needed by industry to close the back end of the power reactor fuel cycle. During the past quarter, studies were conducted in the following tasks: thorium resource price analyses; spent fuel receipt and storage; investigation of air cleaning processes for removing TBP from off-gas streams; study of iodine chemistry in process solutions, high-level waste treatment; electropolishing to decontaminate metallic waste from alternate and thorium converter fuel cycles; U.S. scale transport, dispersion and removal model comparison; safety criticality experiments; and criticality research in support of thorium fuel cycle.

  12. Projects at the Western Environmental Technology Office. Quarterly technical progress report, July 1, 1995--September 30, 1995

    International Nuclear Information System (INIS)

    1996-01-01

    The goal of this project is to demonstrate the technical and economic feasibility of commercializing a biotechnology that uses plants to remediate soils, sediments, surface waters, and groundwaters contaminated by heavy metals and radionuclides. This technology, known as phytoremediation, is particularly suited to remediation of soils or water where low levels of contaminants are widespread. Project objectives are to provide an accurate estimate of the capability and rate of phytoremediation for removal of contaminants of concern from soils and groundwaters at Department of Energy (DOE) sites and to develop data suitable for engineering design and economic feasibility evaluations, including methods for destruction or final disposition of plants containing contaminants of concern. The bioremediation systems being evaluated could be less expensive than soil removal and treatment systems, given the areal extent and topography of sites under consideration and the investment of energy and money in soil-moving and -treating processes. In situ technology may receive regulatory acceptance more easily than ex situ treatments requiring excavation, processing, and replacement of surface soils. In addition, phytoremediation may be viable for cleanup of contaminated waters, either as the primary treatment or the final polishing stage, depending on the contaminant concentrations and process economics considerations

  13. Projects at the Western Environmental Technology Office. Quarterly technical progress report, July 1, 1995--September 30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-01

    The goal of this project is to demonstrate the technical and economic feasibility of commercializing a biotechnology that uses plants to remediate soils, sediments, surface waters, and groundwaters contaminated by heavy metals and radionuclides. This technology, known as phytoremediation, is particularly suited to remediation of soils or water where low levels of contaminants are widespread. Project objectives are to provide an accurate estimate of the capability and rate of phytoremediation for removal of contaminants of concern from soils and groundwaters at Department of Energy (DOE) sites and to develop data suitable for engineering design and economic feasibility evaluations, including methods for destruction or final disposition of plants containing contaminants of concern. The bioremediation systems being evaluated could be less expensive than soil removal and treatment systems, given the areal extent and topography of sites under consideration and the investment of energy and money in soil-moving and -treating processes. In situ technology may receive regulatory acceptance more easily than ex situ treatments requiring excavation, processing, and replacement of surface soils. In addition, phytoremediation may be viable for cleanup of contaminated waters, either as the primary treatment or the final polishing stage, depending on the contaminant concentrations and process economics considerations.

  14. Progress of the radioactive waste management at the Dalat Nuclear Research Institute and the role of an IAEA technical co-operation project in this process

    International Nuclear Information System (INIS)

    Nang, N.T.; Ngoc, O.V.; Nhu Thuy, T.T.; Nghi, D.V.; Thu, N.T.

    2002-01-01

    At present, the main radioactive waste generator in Vietnam is the Dalat Nuclear Research Institute (DNRI). For safe management of radioactive waste generated from this nuclear center, in 1982 Soviet specialists newly constructed one combined technology system for low level radioactive waste management. The existing system consists of two main parts, a Liquid Radioactive Waste Treatment Station and a Storage/Disposal Facility. The liquid treatment station can in principle meet the needs for this nuclear center but disposal technology and storage/disposal facilities are not good enough both with respect to safety and economy, especially the storage/disposal facility placed in Dalat, the tourist city. In order to help DNRI and Vietnam to solve the radioactive waste management problem, the IAEA Technical Co-operation (TC) project VIE/9/007 was implemented in Vietnam. The facilities and IAEA experts provided under this project gradually help to develop radioactive waste management at DNRI, Vietnam. This paper outlines progress under way in the management of the radioactive waste at the Nuclear Research Institute (NRI), Dalat, Vietnam, and the role of the IAEA Technical Co-operation (TC) project in this process. (author)

  15. [Engineering development of advanced coal-fired low-emission boiler systems]. Technical progress report, October--December 1995

    Energy Technology Data Exchange (ETDEWEB)

    Wesnor, J.D.; Bakke, E. [ABB Environmental Systems, Birmingham, AL (United States); Bender, D.J.; Kaminski, R.S. [Raytheon Engineers and Constructors, Inc., Philadelphia, PA (United States)

    1995-12-31

    The overall objective of the Project is the expedited commercialization of advanced coal-fired low-emisssion boiler systems. The primary objectives are: NO{sub x} emissions, lb/million Btu; SO{sub 2} emissions, lb/million Btu; particulate emissions, lb/million Btu; and net plant efficiency, not less than 42%. The secondary objectives are: improved ash disposability; reduced waste generation; and reduced air toxics emissions. Accomplishments to date are summarized for the following tasks: task 1, project planning and management; task 7, component development and optimization; task 8, preliminary POC test facility design; task 9, subsystem test design and plan; task 10, subsystem test unit construction; and task 11, subsystem test operation and evaluation.

  16. Technical issues of RAFMs for the fabrication of ITER Test Blanket Module

    International Nuclear Information System (INIS)

    Tanigawa, Hiroyasu; Hirose, Takanori; Shiba, Kiyoyuki

    2007-01-01

    Reduced activation ferritic/martensitic steels (RAFMs) are recognized as the primary candidate structural materials for fusion blanket systems, as it has they have been developed based on massive industrial experience of ferritic/martensitic steel replacing Mo and Nb of high chromium heat resistant martensitic steels (such as modified 9Cr-1Mo) with W and Ta, respectively. F82H and JLF-1 are RAFMs, which have been developed and studied in Japan and the various effects of irradiation were reported. F82H is designed with emphasis on high temperature property and weldability, and was provided and evaluated in various countries as a part of the IEA fusion materials development collaboration. The JAEA/US collaboration program also has been conducted with the emphasis on irradiation effects of F82H. Now, among the existing database for RAFMs the most extensive one is that for F82H. The objective of this paper is to review the R and D status of F82H and to identify the key technical issues for the fabrication of ITER Test Blanket Module (TBM) suggested from the recent achievements in Japan. It is desirable to make the status of RAFMs equivalent to commercial steels to use RAFMs as the ITER-TBM structural material. This would require demonstrating the reproducibility and weldability as well as providing the database. The excellent reproducibility of F82H has been demonstrated with four 5-ton-heats, and two of them were provided as F82H-IEA heats. It has been also proved that F82H could be provided as plates (thickness of 1.5 to 55 mm), pipes and rectangular tubes. It is also important to have the excellent weldability as the TBM has about 300m length of weld line, and it was proved through TIG, EB and YAG weld test performed in air atmosphere. Various mechanical and microstructural data have been accumulated including long-term tests such as creep rupture tests and aging tests. Although F82H is a well-perceived RAFM as the ITER-TBM structural material, some issues are

  17. Nemaha Uplift seismotectonic study: regional tectonics and seismicity of eastern Kansas. Technical progress report, October 1, 1978-September 30, 1979

    International Nuclear Information System (INIS)

    Wilson, F.W.

    1979-11-01

    Progress and results of all work on this project to the end of its second year, or September 30, 1978, were reported in NUREG/CR-0666, published March 1979. Project third-year activites and results include the following: continued operation of a regional microearthquake monitoring network which detected and located 26 regional events between October 1, 1978, and August 2, 1979; designing and building a triggering system to allow digitized recording of microearthquakes by a modified exploration seismography; continued surface and subsurface studies of selected areas along the Nemaha Uplift-Keweenanan Mafic belt trend; continued study of Precambrian rock types from recently drilled wells; beginning compilation of a fault catalog; terrain analysis and lineament studies which indicate that the alignment of stream drainages and divides are strongly controlled by basement and subsurface structure; continued reduction of gravity data for northeastern Kansas (a Bouguer gravity map probably will be available late Fall 1979); modification of the exploration seismograph system to a more efficient 12-channel Mini-Sosie system and completion of several line-miles of reflection profiling; and beginning integration of data from Oklahoma, Nebraska, and Iowa co-investigators. All major goals for FY 1979 were accomplished. 2 figures

  18. Establishment of an Institute for Fusion Studies. Technical progress report, 1 November 1993--31 October 1994

    International Nuclear Information System (INIS)

    Hazeltine, R.D.

    1994-07-01

    The Institute for Fusion Studies is a national center for theoretical fusion plasma physics research. Its purposes are: (1) to conduct research on theoretical questions concerning the achievement of controlled fusion energy by means of magnetic confinement--including both fundamental problems of long-range significance, as well as shorter-term issues; (2) to serve as a national and international center for information exchange by hosting exchange visits, conferences, and workshops; (3) and to train students and postdoctoral research personnel for the fusion energy program and plasma physics research areas. The theoretical research results obtained by the Institute contribute to the progress of nuclear fusion research, whose goal is the development of fusion power as a basic energy source. Close collaborative relationships have been developed with other university and national laboratory fusion groups, both in the US and abroad. In addition to its primary focus on mainstream fusion physics, the Institute is also involved with research in fusion-sidestream fields, such as advanced computing techniques, nonlinear dynamics, space plasmas and astrophysics, statistical mechanics, fluid dynamics, and accelerator physics. Important research discoveries are briefly described

  19. Indiana University High Energy Physics Group: Task A: Technical progress report, December 1, 1986 to November 30, 1987

    International Nuclear Information System (INIS)

    Alyea, E.D.; Brabson, B.B.; Crittenden, R.R.; Dzierba, A.R.; Martin, H.J.; Ogren, H.O.; Zieminski, A.

    1987-05-01

    Data collection on the production of the KKπ state in π - , K - , and p-bar induced reactions is reported, with partial wave analysis in progress. Work on the design of a target calorimeter and data taking for a muon scattering experiment at CERN is completed. Analysis of a fixed-target jet experiment is reported. A dimuon detector has been prepared for an experiment at Fermilab to study hadronic processes yielding high mass dimuons and associated particles. Participation in the coordination and writing of software for the DO collider detector at Fermilab is reported. Some results from the High Resolution Spectrometer (HRS) are reported, including direct observation of several decay modes of the charmed mesons, directly observed meson resonances, baryon resonances, and some discoveries concerning the tau lepton. Activity is reported in the building of hardware for the muon upgrade for the Mark2 detector at the SLC and the building of the beam position monitors for the SLC, and microprocessors for Mark2 data analysis. Involvement in the SLC polarization collaboration is also reported

  20. Molluscs and echinoderms aquaculture: biological aspects, current status, technical progress and future perspectives for the most promising species in Italy

    Directory of Open Access Journals (Sweden)

    Antonio Pais

    2012-10-01

    Full Text Available Shellfish aquaculture is a widespread activity in the Italian peninsula. However, only two bivalve species are mainly cultured along the coastline of that country: the Mediterranean mussel Mytilus galloprovincialis and the Manila clam Venerupis philippinarum (Ruditapes philippinarum. By contrast, just a few other mollusc species of commercial interest are scarcely reared at a small-scale level. After analysing the current status of Italian shellfish production, this paper reports and discusses the potential for culturing several different invertebrate species [i.e., the European flat oyster Ostrea edulis, the grooved carpet shell Venerupis decussata (Ruditapes decussatus, the razor clams Ensis minor and Solen marginatus, the cephalopod Octopus vulgaris, and the purple sea urchin Paracentrotus lividus] in this country. In addition, a detailed overview of the progress made in aquacultural techniques for these species in the Mediterranean basin is presented, highlighting the most relevant bottlenecks and the way forward to shift from the experimental to the aquaculture phase. Finally, an outlook of the main economic and environmental benefits arising from these shellfish culture practices is also given.

  1. 1991 Technical progress report of the University of South Carolina's High Energy Physics Group, February 1990--July 1991

    International Nuclear Information System (INIS)

    1991-01-01

    The high energy physics group at the University of South Carolina includes five teaching faculty members, one research faculty member, and five graduate students. Profs. Childers, Darden, and Wilson devote most of their research effort to Fermilab experiment E789, which is designed to observe charmless two-body decays of b-flavored mesons and baryons. Prof. Wilson works on Fermilab experiment E687 which studies charm physics in the wide-band photon beam. Profs. Rosenfeld and Wang participate in the AMY collaboration, which studies electron-positron interactions using the TRISTAN collider at KEK. Prof. Rosenfeld and one student collaborate with personnel from KEK and INS, Tokyo, on an experiment to detect a 17 keV neutrino in the β-decay spectrum of 63 Ni. Members of the group also participate in Fermilab Proposal P803 which will search for the oscillation of muon neutrino to tau neutrino with sensitivity better than a factor of 40 than previously achieved and in Superconducting Super Collider activities which include the development of an imaging preradiator. A brief discussion is given on progress made for each program

  2. Progress in the development of a SiC{sub f}/SiC creep test

    Energy Technology Data Exchange (ETDEWEB)

    Hamilton, M.L.; Lewinsohn, C.A.; Jones, R.H.; Youngblood, G.E.; Garner, F.A. [Pacific Northwest National Lab., Richland, WA (United States); Hecht, S.L.

    1996-10-01

    An effort is now underway to design an experiment that will allow the irradiation creep behavior of SiC{sub f}/SiC composites to be quantified. Numerous difficulties must be overcome to achieve this goal, including determining an appropriate specimen geometry that will fit their radiation volumes available and developing a fabrication procedure for such a specimen. A specimen design has been selected, and development of fabrication methods is proceeding. Thermal and stress analyses are being performed to evaluate the viability of the specimen and to assist with determining the design parameters. A possible alternate type of creep test is also being considered. Progress in each of these areas is described in this report.

  3. Progress in the development of a SiCf/SiC creep test

    International Nuclear Information System (INIS)

    Hamilton, M.L.; Lewinsohn, C.A.; Jones, R.H.; Youngblood, G.E.; Garner, F.A.; Hecht, S.L.

    1996-01-01

    An effort is now underway to design an experiment that will allow the irradiation creep behavior of SiC f /SiC composites to be quantified. Numerous difficulties must be overcome to achieve this goal, including determining an appropriate specimen geometry that will fit their radiation volumes available and developing a fabrication procedure for such a specimen. A specimen design has been selected, and development of fabrication methods is proceeding. Thermal and stress analyses are being performed to evaluate the viability of the specimen and to assist with determining the design parameters. A possible alternate type of creep test is also being considered. Progress in each of these areas is described in this report

  4. IFMIF High Flux Test Module-Recent progress in design and manufacturing

    Energy Technology Data Exchange (ETDEWEB)

    Leichtle, D. [Association FZK-EURATOM, Forschungszentrum Karlsruhe, Institut fuer Reaktorsicherheit, Hermann-von-Helmholtz-Platz 1, D-76344 Eggenstein-Leopoldshafen (Germany)], E-mail: leichtle@irs.fzk.de; Arbeiter, F.; Dolensky, B.; Fischer, U.; Gordeev, S.; Heinzel, V.; Ihli, T.; Lang, K.-H. [Association FZK-EURATOM, Forschungszentrum Karlsruhe, Institut fuer Reaktorsicherheit, Hermann-von-Helmholtz-Platz 1, D-76344 Eggenstein-Leopoldshafen (Germany); Moeslang, A. [Association FZK-EURATOM, Forschungszentrum Karlsruhe, Institut fuer Materialforschung, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Simakov, S.P.; Slobodchuk, V.; Stratmanns, E. [Association FZK-EURATOM, Forschungszentrum Karlsruhe, Institut fuer Reaktorsicherheit, Hermann-von-Helmholtz-Platz 1, D-76344 Eggenstein-Leopoldshafen (Germany)

    2008-12-15

    The International Fusion Material Irradiation Facility (IFMIF) is an accelerator driven neutron source for irradiation tests of candidate fusion reactor materials. Within the High Flux Test Module (HFTM) a testing volume of 0.5 l filled by qualified small scale specimens will be irradiated at displacement rates of 20-50 dpa/fpy in structural materials. The Forschungszentrum Karlsruhe (FZK) has developed a HFTM design which closely follows the design premise of maximising the space available for irradiation specimens in the IFMIF high flux zone and in addition allows keeping the temperature nearly constant in the rigs containing the specimen. Complementary analyses on nuclear, thermo-hydraulics and mechanical performance of the HFTM were performed to optimize the design. The present paper highlights the main design characteristics as well as recent progress achieved in this area. The contribution also includes (i) recommendations for the use of container, rig and capsule materials, and (ii) a description of the fabrication routes for the entire HFTM including brazing and filling procedures which are currently under development at the Forschungszentrum Karlsruhe.

  5. IFMIF High Flux Test Module-Recent progress in design and manufacturing

    International Nuclear Information System (INIS)

    Leichtle, D.; Arbeiter, F.; Dolensky, B.; Fischer, U.; Gordeev, S.; Heinzel, V.; Ihli, T.; Lang, K.-H.; Moeslang, A.; Simakov, S.P.; Slobodchuk, V.; Stratmanns, E.

    2008-01-01

    The International Fusion Material Irradiation Facility (IFMIF) is an accelerator driven neutron source for irradiation tests of candidate fusion reactor materials. Within the High Flux Test Module (HFTM) a testing volume of 0.5 l filled by qualified small scale specimens will be irradiated at displacement rates of 20-50 dpa/fpy in structural materials. The Forschungszentrum Karlsruhe (FZK) has developed a HFTM design which closely follows the design premise of maximising the space available for irradiation specimens in the IFMIF high flux zone and in addition allows keeping the temperature nearly constant in the rigs containing the specimen. Complementary analyses on nuclear, thermo-hydraulics and mechanical performance of the HFTM were performed to optimize the design. The present paper highlights the main design characteristics as well as recent progress achieved in this area. The contribution also includes (i) recommendations for the use of container, rig and capsule materials, and (ii) a description of the fabrication routes for the entire HFTM including brazing and filling procedures which are currently under development at the Forschungszentrum Karlsruhe

  6. Development of Monitoring and Diagnostic Methods for Robots Used in Remediation of Waste Sites 1999 Technical Progress Report

    International Nuclear Information System (INIS)

    Martin, Michael

    1999-01-01

    The final assembly of the test rig was completed in January 1999 (see Figure 1). The test rig incorporated a wheel motor typical of those used for hydraulic robots, and allowed wheel motor loading at expected operating conditions. The rig included instrumentation, as shown in Figure 2, for acquisition of key parameters for both unfaulted baseline and inserted fault runs. Checkout of the test rig was accomplished in two phases. In the first phase, only the wheel motor was connected to the hydraulic supply and the driven pump disconnected. With the rig in this configuration, operation of the wheel motor control loop and the monitoring and diagnostic (M and D) data acquisition system was verified. In the second phase, the driven pump was connected to the wheel motor and the operation of the rig under load was confirmed and unfaulted baseline data were acquired. A list of 13 faults was developed (see Table 1). All faults were inserted and data were acquired. The data files were electronically transmitted to Rice University for analysis using Analytical Redundancy (AR), a model-based static space technique that derives the maximum number of independent tests of the consistency of sensor data with the linearized system model and past sensor and control inputs

  7. Humic substances in performance assessment of nuclear waste disposal: Actinide and iodine migration in the far-field. First technical progress report

    International Nuclear Information System (INIS)

    Buckau, G.

    2003-04-01

    The present project is one in a series of research activities supported by the European Commission on the role of humic substances for the long-term safety of nuclear waste disposal. These activities started in the mid eighties within the MIRAGE project (MIgration of RAdionuclides in the GEosphere) with the most recent project being ''Effects of humic substances on the migration of radionuclides: Complexation and transport of actinides (HUMICS)'' (FI4W-CT96-0028). The HUMICS project was conducted within the fourths framework of the European Commissions research program. It started January 1997 and had a duration of three years. The results of the HUMICS project can be found in three open technical progress reports and a final report [1-4]. In analogy with the HUMICS project, the present project makes use of annual technical progress reports where individual results are published as papers in the form of annexes. By this approach, results rapidly become available to interested parties in a compact form before their publication in various scientific journals and conference proceedings. Furthermore, some of the more preliminary and/or detailed results are not likely to appear in scientific journals and proceedings. The present project is conducted within the fifths framework of the European Commissions research program. It started November 2001 and has a duration of three years. The present report covers the first project year, i.e. November 2001 to September 2002. The project is divided into eight different work packages. These are (i) ''Critical assessment of experimental methods'', (ii) ''Generation and characterization of humic substances'', (iii) ''Radionuclide humate interaction data by designed system investigations'', (iv) ''Characterization of radionuclide humate complexes'', (v) ''Natural chemical analogue studies'', (vi) ''Radionuclide transport experiments'', (vii) ''Model development'', and (viii) ''Performance assessment''. Division of work into

  8. Technical protocol for laboratory tests of transformation of veterinary medicinal products and biocides in liquid manures. Version 1.0

    Energy Technology Data Exchange (ETDEWEB)

    Kreuzig, Robert [Technische Univ. Braunschweig (Germany). Inst. fuer Oekologische Chemie und Abfallanalytik

    2010-07-15

    The technical protocol under consideration describes a laboratory test method to evaluate the transformation of chemicals in liquid bovine and pig manures under anaerobic conditions and primarily is designed for veterinary medicinal products and biocides. The environmentally relevant entry routes into liquid manures occur via urine and feces of cattle and pigs in stable housings after excretion of veterinary medicinal products as parent compounds or metabolites and after the application of biocides in animal housings. Further entry routes such as solid dung application and direct dung pat deposition by production animals on pasture are not considered by this technical protocol. Thus, this technical protocol focused on the sampling of excrements from cattles and pigs kept in stables and fed under standard nutrition conditions. This approach additionally ensures that excrement samples are operationally free of any contamination by veterinary medicinal products and biocides. After the matrix characterization, reference-manure samples are prepared from the excrement samples by adding tap water to adjust defined dry substance contents typical for bovine or pig manures. This technical protocol comprehends a tiered experimental design in two parts: (a) Sampling of excrements and preparation of reference bovine and pig manures; (b) Testing of anaerobic transformation of chemicals in reference manures.

  9. Search for neutrino oscillations and measurements of neutrino-nucleus cross sections. Technical progress report, 16 January 1985-15 October 1985

    International Nuclear Information System (INIS)

    Koetke, D.D.

    1985-01-01

    Progress is reported in these areas: work done at LANL on experiment E764, including beam line modification, new target installation, system testing, on-line software development, beam tuning, and data acquisition; neutrino Monte Carlo program development; flux calculations for the DC modified torroidal pion focussing device for the low energy decay-in-flight neutrino source; and prototype preparation for a large modular segmented detector

  10. GPHS-RTGs in support of the Cassini Mission. Semi annual technical progress report, 28 March 1994--25 September 1994

    International Nuclear Information System (INIS)

    1994-01-01

    The progress on the radioisotope generators and ancillary activities is described. This report is organized by program task as follows: spacecraft integration and liaison; engineering support; safety; qualified unicouple fabrication; ETG fabrication, assembly, and test; ground support equipment; RTG shipping and launch support; design, reviews, and mission applications; project management, quality assurance and reliability, contract changes, non-capital CAGO acquisition, and CAGO maintenance; contractor acquired government owned property (CAGO) acquisition

  11. Progress in the development of very high density research and test reactor fuels

    Energy Technology Data Exchange (ETDEWEB)

    Wachs, D.M. [Idaho National Laboratory, P.O. Box 2528, Idaho Falls, Idaho 83415 (United States)

    2009-06-15

    New nuclear fuels are being developed to enable many of the most important research and test reactors worldwide to convert from high enriched uranium (HEU) fuels to low enriched uranium (LEU) fuels without significant loss in performance. The last decade of work has focused on the development of uranium-molybdenum alloy (U-Mo) based fuels and is an international effort that includes the active participation of more than ten national programs. The US RERTR program, under the NNSA's Global Threat Reduction Initiative (GTRI), is in the process of developing both dispersion and monolithic U-Mo fuel designs. While the U-Mo fuel alloy has behaved extremely well under irradiation, initial testing (circa 2003) revealed that the U-Mo fuels dispersed in aluminum had an unexpected tendency toward unstable swelling (pillowing) under high-power conditions. Technical investigations were initiated worldwide at this time by the partner programs to understand this behavior as well as to develop and test remedies. The behavior was corrected by modifying the chemistry of the U-Mo/Al interfaces in both fuel designs. In the dispersion fuel design, this was accomplished by the addition of small amounts of silicon to the aluminum matrix material. Two methods are under development for the monolithic fuel design, which include the application of a thin layer of silicon or a thin zirconium based diffusion barrier at the fuel/clad interface. This paper gives an overview of the current status of U-Mo fuel development, including basic research results, manufacturing aspects, results of the latest irradiations and post irradiation examinations, the approach to fuel performance qualification, and the scale-up and commercialization of fabrication technology. (authors)

  12. Final Progress Report: Developing Ethical Practices for Genetics Testing in the Workplace

    Energy Technology Data Exchange (ETDEWEB)

    Laura Roberts, MD; Teddy Warner, PhD

    2008-05-14

    Our multidisciplinary research team for this project involved collaboration between the Department of Psychiatry and Behavioral Medicine at the Medical College of Wisconsin (MCW) and the Department of Family and Community Medicine at the University of New Mexico Health Sciences Center (UNM HSC). Our research team in Wisconsin was led by Laura Roberts, M.D., Principal Investigator, and included Scott Helberg, MLS (Project Coordinator), Kate Green Hammond, Ph.D. (Consultant), Krisy Edenharder (Research Coordinator), and Mark Talatzko (Research Assistant). Our New Mexico-based team was led by Teddy Warner, Ph.D., Co-Principal Investigator and UNM Site Principal Investigator, and included Suzanne Roybal (Project Assistant), Darlyn Mabon (Project Assistant), Kate Green Hammond, PhD (Senior Research Scientist on the UNM team from 2004 until January, 2007), and Paulette Christopher (Research Assistant). In addition, computer technical and web support for the web-based survey conducted on a secure server at the University of New Mexico was provided by Kevin Wiley and Kim Hagen of the Systems and Programming Team of the Health Sciences Center Library and Information Center. We stated 3 aims in the grant proposal: (1) To collect web survey reports of the ethical perspectives, concerns, preferences and decision-making related to genetic testing using surveys from employees at: (a) Los Alamos National Laboratory (LANL); (b) Sandia National Laboratories (SNL); and (c) the University of New Mexico Health Sciences Center (UNMHSC); (2) To perform an extensive literature search and the extant survey data to develop evidence-based policy recommendations for ethically sound genetic testing associated with research and occupational health activities in the workplace; and, (3) To host a conference at the Medical College of Wisconsin to provide employers, workers, health professionals, researchers, the public, and the media an opportunity to consider ethical issues involved in genetic

  13. Automated Array Assembly, Phase 2. Quarterly technical progress report, fourth quarter 1977. Texas Instruments report No. 03-77-56

    Energy Technology Data Exchange (ETDEWEB)

    Carbajal, B.G.

    1978-01-01

    The Automated Array Assembly Task, Phase 2 of the Low Cost Silicon Solar Array (LSSA) Project, is a process development task. This contract includes solar cell module process development activities in the areas of Surface Preparation, Plasma Processing, Diffusion, Cell Processing and Module Fabrication. In addition, a High Efficiency Cell Development Activity is included. During this quarter, effort was concentrated on wafer etching for saw damage removal, establishing a standard phosphorous diffusion process and a baseline solar cell process as a test bed, designing a large area square cell including test sites, analyzing module layouts for optimum packing efficiency and fabricating the first Tandem Junction Cells (TJC) for this contract. A TJC with backside contacts gave 15.1% efficiency at AM1.

  14. Application of railgun principle to high-velocity hydrogen pellet injection for magnetic fusion reactor refueling: Technical progress report

    International Nuclear Information System (INIS)

    Kim, Kyekyoon.

    1987-12-01

    This paper discusses the use of a railgun accelerator to inject hydrogen pellets into a magnetic fusion reactor for refueling purposes. Specific studies in this paper include: 1.5 mm-diameter two-stage fuseless plasma-arc-driven electromagnetic railgun, construction and testing of a 3.2 mm-diameter two-stage railgun and a theoretical analysis of the behavior of a railgun plasma-arc armature inside a railgun

  15. Mutagenic effect of tritium on DNA of Drosophila melanogaster: Technical progress report, December 15, 1986-July 15, 1987

    International Nuclear Information System (INIS)

    Lee, W.R.

    1987-01-01

    Recombinant DNA techniques were used to analyze mutants induced by either tritium or x-ray. Mutations induced at the alcohol dehydrogenase locus (Adh) in Drosophila melanogaster were first characterized by genetic complementation tests to determine if a multi-locus deletion has occurred. Mutants that are intragenic as defined by the complementation test are then placed opposite a deficiency so that the DNA from the mutant allele may be extracted and analyzed. Part I of the project is to analyze mutants induced by ionizing radiation with molecular techniques, and part II is to determine the molecular effects of these mutant phenotypes on their expression in the polypeptide produced by the mutant gene. Part III of this project consists of inducing mutants with tritiated water at the Adh locus in D. melanogaster. We have reported the development of a feeding method for exposing male D. melanogaster to tritiated water that would give a range in dose from 6.66 Gy to 26.64 Gy. This method of exposing Drosophila was used first to study a dose response curve for tritium using as a genetic endpoint the sex-linked recessive lethal test. 3 figs., 1 tab

  16. Technology development for cobalt F-T catalysts. Quarterly technical progress report No. 12, July 1, 1995--September 30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Singleton, A.H.

    1996-03-21

    The investigation of the effect of certain promoters (Fe, Pd, and Ru) on the deactivation characteristics of Co catalysts during F-T synthesis was continued during this reporting period. All catalysts were tested first at 220{degrees}C, then at higher temperatures from 240 to 280{degrees}C, while monitoring their deactivation. The choice of these promoters was based on their intrinsic ability to enhance the hydrogenation reactions while slowing down the Boudouard reaction under the conditions used in F-T synthesis. Olefin hydrogenation and CO dissociation reactions were used individually to investigate further the nature of the deactivation process of these catalyst during F-T synthesis. Hydrogenation of isobutene (IB) was carried out in the presence of CO between 120 and 180{degrees}C and atmospheric pressure. CO dissociation activities of the catalysts were measured using a pulse technique at 2.5 atm and at temperatures between 180 and 280{degrees}C with intermittent H{sub 2} bracketing at 350{degrees}C. Promotion with high loadings of Fe or Pd resulted in catalysts with relatively lower activity and higher methane selectivity. The deactivation process and rate for catalysts containing Pd or Fe were similar to those of the non-promoted or Ru-promoted alumina-supported Co catalysts tested previously. The only exception was Co.068 with 1% Pd which had adequate activity and selectivity as well as lower deactivation rate at the various temperatures tested.

  17. Micelle-derived catalysts for extended Schulz-Flory. Technical progress report, July 1, 1986--September 30, 1986

    Energy Technology Data Exchange (ETDEWEB)

    Abrevaya, H.

    1986-12-31

    The objective of this program is to develop a synthesis gas conversion catalyst with higher selectivity to liquid fuels, while maintaining catalytic activity and stability at least equivalent relative to state-of-the-art precipitated iron catalysts. During this quarter, the emphasis in the program has been the investigation of the hydrocarbon cutoff hypothesis with supported ruthenium catalysts. An alumina-supported catalyst with smaller than 20{Angstrom} ruthenium particles was tested under conditions of maximal water gas shift activity. During this test more than 90% of the water made in the Fischer-Tropsch synthesis reaction was converted to H{sub 2}. However, the extent of ruthenium metal agglomeration was not reduced. Accordingly, it was not possible to conclude whether hydrocarbon cutoff occurs with smaller than 20{Angstrom} ruthenium particles on {gamma}-alumina. A ruthenium catalyst prepared on Y-type zeolite had 20{Angstrom} or smaller ruthenium particles according to STEM examination and a 15{Angstrom} average ruthenium metal particle size according to EXAFS examination. The ruthenium metal particle size was stable during the test with this catalyst. The hydrocarbon product distribution was Anderson-Schulz-Flory with no cutoff up to a carbon number of 160. A well-dispersed titania-supported ruthenium catalyst is going to be evaluated during the next quarter in order to determine whether hydrocarbon cutoff occurs.

  18. ATR Technical Specification Upgrade Program

    International Nuclear Information System (INIS)

    McCracken, R.T.; Durney, J.L.; Freund, G.A.

    1990-01-01

    The Advanced Test Reactor (ATR) is a 250 MW, uranium-aluminum fueled test reactor which began full power operation in 1969. The initial operation was controlled by an Operating Limits document based on the original Safety Analysis Report. Additional safety bases were later developed to support Technical Specifications which were approved and implemented in 1977. The Technical Specifications which were initially developed with content and format specified in ANSI/ANS--15.1, ''The Development of Technical Specifications for Research Reactors.'' The safety basis documentation and the Technical Specifications have been updated as required to maintain them current with the ATR facility configuration. All revisions have been made with a content, format and style consistent with the original. A major, two-phase program to upgrade the content, format and style is in progress. This paper describes the first phase of this program

  19. Task Order 22 – Engineering and Technical Support, Deep Borehole Field Test. AREVA Summary Review Report

    Energy Technology Data Exchange (ETDEWEB)

    Denton, Mark A. [AREVA Federal Services, Charlotte, NC (United States)

    2016-01-19

    Under Task Order 22 of the industry Advisory and Assistance Services (A&AS) Contract to the Department of Energy (DOE) DE-NE0000291, AREVA has been tasked with providing assistance with engineering, analysis, cost estimating, and design support of a system for disposal of radioactive wastes in deep boreholes (without the use of radioactive waste). As part of this task order, AREVA was requested, through a letter of technical direction, to evaluate Sandia National Laboratory’s (SNL’s) waste package borehole emplacement system concept recommendation using input from DOE and SNL. This summary review report (SRR) documents this evaluation, with its focus on the primary input document titled: “Deep Borehole Field Test Specifications/M2FT-15SN0817091” Rev. 1 [1], hereafter referred to as the “M2 report.” The M2 report focuses on the conceptual design development for the Deep Borehole Field Test (DBFT), mainly the test waste packages (WPs) and the system for demonstrating emplacement and retrieval of those packages in the Field Test Borehole (FTB). This SRR follows the same outline as the M2 report, which allows for easy correlation between AREVA’s review comments, discussion, potential proposed alternatives, and path forward with information established in the M2 report. AREVA’s assessment focused on three primary elements of the M2 report: the conceptual design of the WPs proposed for deep borehole disposal (DBD), the mode of emplacement of the WP into DBD, and the conceptual design of the DBFT. AREVA concurs with the M2 report’s selection of the wireline emplacement mode specifically over the drill-string emplacement mode and generically over alternative emplacement modes. Table 5-1 of this SRR compares the pros and cons of each emplacement mode considered viable for DBD. The primary positive characteristics of the wireline emplacement mode include: (1) considered a mature technology; (2) operations are relatively simple; (3) probability of a

  20. Post-Lamination Manufacturing Process Automation for Photovoltaic Modules; Annual Technical Progress Report: 15 June 1999--14 July 2000

    Energy Technology Data Exchange (ETDEWEB)

    Nowlan, M. J.; Murach, J. M.; Sutherland, S. F.; Lewis, E. R.; Hogan, S. J.

    2000-09-29

    Spire is addressing the PVMaT project goals of photovoltaic (PV) module cost reduction and improved module manufacturing process technology. New cost-effective automation processes are being developed for post-lamination PV module assembly, where post-lamination is defined as the processes after the solar cells are encapsulated. These processes apply to both crystalline and thin-film solar cell modules. Four main process areas are being addressed: (1) Module buffer storage and handling between steps; (2) Module edge trimming, edge sealing, and framing; (3) Junction-box installation; and (4) Testing for module performance, electrical isolation, and ground-path continuity.