WorldWideScience

Sample records for materials technical progress

  1. Technical Progress Report for "Optical and Electrical Properties of III-Nitrides and Related Materials"

    Energy Technology Data Exchange (ETDEWEB)

    Jiang, Hongxing

    2008-10-31

    Investigations have been conducted focused on the fundamental material properties of AIN and high AI-content AIGaN alloys and further developed MOCVD growth technologies for obtaining these materials with improved crystalline quality and conductivities.

  2. Helium generation in fusion reactor materials. Technical progress report, April--September 1977

    International Nuclear Information System (INIS)

    1978-01-01

    The near-term objectives of this program are to measure the spectrum-integrated helium generation rates and cross sections of a number of pure elements and alloys in several high-intensity neutron sources, and to develop and demonstrate neutron dosimetry procedures using some of these materials. To this end, four neutron irradiation experiments have now been run: one using accelerator-produced d-Be neutrons, two using the accelerator-produced d-T reaction, and one in the neutron field of a mixed-spectrum fission reactor. All of these irradiations have incorporated a large number of helium-generation materials

  3. Radiation effects on structural materials. Technical progress report, January 1, 1984-June 30, 1984

    International Nuclear Information System (INIS)

    Ghoneim, N.M.

    1984-01-01

    By a generalization of an analysis due to Frank of the growing precipitate, we derive an analytic sink strength for the growing void that takes account of the void surface motion in a self-consistent fashion. The lower mobility of the vacancies compared to the interstitials ensures that a growing void captures more vacancies than the usual quasi-static void. The various consequences of this void bias for vacancies are discussed in relation to the swelling of reactor materials

  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. 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

  6. Materials Technical Team Roadmap

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2013-08-01

    Roadmap identifying the efforts of the Materials Technical Team (MTT) to focus primarily on reducing the mass of structural systems such as the body and chassis in light-duty vehicles (including passenger cars and light trucks) which enables improved vehicle efficiency regardless of the vehicle size or propulsion system employed.

  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. Quarterly Technical Progress Report of Radioisotope Power System Materials Production and Technology Program tasks for January 2000 through March 2000

    International Nuclear Information System (INIS)

    Moore, J.P.

    2000-01-01

    The Office of Space and Defense Power Systems (OSDPS) of the Department of Energy (DOE) provides radioisotope Power Systems (BPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of .I 997 to study the planet Saturn. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. For the Cassini Mission, for example, ORNL was involved in the production of carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVSs) and weld shields (WSs). This quarterly report has been divided into three sections to reflect program guidance from OSDPS for fiscal year (FY) 2000. The first section deals primarily with maintenance of the capability to produce flight quality carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, clad vent sets (CVSs), and weld shields (WSs). In all three cases, production maintenance is assured by the manufacture of limited quantities of flight quality (FQ) components. The second section deals with several technology activities to improve the manufacturing processes, characterize materials, or to develop technologies for two new RPS. The last section is dedicated to studies of the potential for the production of 238Pu at OBNL

  9. 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.)

  10. Technical Division quarterly progress report, October 1--December 31, 1977. [Fuel cycle research and development; special materials production

    Energy Technology Data Exchange (ETDEWEB)

    Slansky, C.M. (ed.)

    1978-02-01

    Results are presented on the fluidized-bed calcination of simulated radioactive waste from the reprocessing of spent commercial nuclear fuel and on the removal of actinide elements from the waste prior to calcination. Other programs include the development of storage technology for /sup 85/Kr waste; and the behavior of volatile radionuclides during the combustion of HTGR graphite-based fuel. The long-term management of defense waste from the ICPP covers post-calcination treatment of ICPP calcined waste; the removal of actinide elements from first-cycle raffinate; the retrieval and handling of calcined waste from ICPP storage vaults; and the preparation of the Programmatic Environmental Impact Statement on ICPP waste. Process improvements are reported on the Fluorinel headend process for Zircaloy-clad fuels and on uranium accountability measurements. Other development results cover the process for recovering spent Rover fuel, buried pipeline transfer systems, support to the Waste Management Program, Waste Calcining Facility support, New Waste Calcining Facility support, and effluent monitoring methods evaluation and development. In this category are studies on nuclear materials security, application of a liquid-solid fluidized-bed heat exchanger to the recovery of geothermal heat, inplant reactor source term measurements, burnup methods for fast breeder reactor fuels, absolute thermal fission yield measurements, analytical support to light water breeder reactor development, research on analytical methods, and the behavior of environmental species of iodine.

  11. 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.)

  12. Annual Technical Progress Report of Radioisotope Power System Materials Production and Technical Program Tasks for October 1, 2005 through September 30, 2006

    Energy Technology Data Exchange (ETDEWEB)

    None

    2007-04-02

    The Office of Space and Defense Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. For the Cassini Mission, ORNL produced carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS) used in the generators. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. This report reflects program guidance from the Office of Space and Defense Power Systems for fiscal year (FY) 2006. Production activities for prime quality (prime) CBCF insulator sets, iridium alloy blanks and foil, and CVS are summarized in this report. Technology activities are also reported that were conducted to improve the manufacturing processes, characterize materials, or to develop information for new radioisotope power systems.

  13. 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...

  14. 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)

  15. 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

  16. 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)

  17. 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.

  18. US/Japan collaborative program on fusion reactor materials: Summary of the tenth DOE/JAERI Annex I technical progress meeting on neutron irradiation effects in first wall and blanket structural materials

    International Nuclear Information System (INIS)

    Rowcliffe, A.F.

    1989-01-01

    This meeting was held at Oak Ridge National Laboratory on March 17, 1989, to review the technical progress on the collaborative DOE/JAERI program on fusion reactor materials. The purpose of the program is to determine the effects of neutron irradiation on the mechanical behavior and dimensional stability of US and Japanese austenitic stainless steels. Phase I of the program focused on the effects of high concentrations of helium on the tensile, fatigue, and swelling properties of both US and Japanese alloys. In Phase II of the program, spectral and isotropic tailoring techniques are fully utilized to reproduce the helium:dpa ratio typical of the fusion environment. The Phase II program hinges on a restart of the High Flux Isotope Reactor by mid-1989. Eight target position capsules and two RB* position capsules have been assembled. The target capsule experiments will address issues relating to the performance of austenitic steels at high damage levels including an assessment of the performance of a variety of weld materials. The RB* capsules will provide a unique and important set of data on the behavior of austenitic steels irradiated under conditions which reproduce the damage rate, dose, temperature, and helium generation rate expected in the first wall and blanket structure of the International Thermonuclear Experimental Reactor

  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. 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).

  3. 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

  4. Development of New Low-Cost, High-Performance, PV Module Encapsulant/Packaging Materials: Final Technical Progress Report, 22 October 2002 - 15 November 2007

    Energy Technology Data Exchange (ETDEWEB)

    Tucker, R.

    2008-04-01

    Report on objectives to work with U.S.-based PV module manufacturers (c-Si, a-Si, CIS, other thin films) to develop/qualify new low-cost, high-performance PV module encapsulant/packaging materials, and processes using the packaging materials.

  5. 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.

  6. Annual Technical Progress Report of Radioisotope Power Systems Materials Production and Technology Program Tasks for October 1, 2006 Through September 30, 2007

    Energy Technology Data Exchange (ETDEWEB)

    King, James F [ORNL

    2008-04-01

    The Office of Radioisotope Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. For the Cassini Mission, ORNL produced carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS) used in the generators. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. This report reflects program guidance from the Office of Radioisotope Power Systems for fiscal year (FY) 2007. Production activities for prime quality (prime) CBCF insulator sets, iridium alloy blanks and foil, and CVS are summarized in this report. Technology activities are also reported that were conducted to improve the manufacturing processes, characterize materials, or to develop information for new radioisotope power systems.

  7. Annual Technical Progress Report of Radioisotope Power System Materials Production and Technology Program Tasks for October 1, 2002 Through September 30, 2003

    Energy Technology Data Exchange (ETDEWEB)

    King, J.F.

    2004-05-18

    The Office of Space and Defense Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. For the Cassini Mission, for example, ORNL was involved in the production of carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS). This report has been divided into three sections to reflect program guidance from the Office of Space and Defense Power Systems for fiscal year (FY) 2003. The first section deals primarily with maintenance of the capability to produce flight quality (FQ) CBCF insulator sets, iridium alloy blanks and foil, and CVS. In all three cases, production maintenance is assured by the manufacture of limited quantities of FQ components. The second section deals with several technology activities to improve the manufacturing processes, characterize materials, or to develop technologies for new radioisotope power systems. The last section is dedicated to studies related to the production of {sup 238}Pu.

  8. Annual Technical Progress Report of Radioisotope Power System Materials Production and Technology Programs Tasks for October 1, 2005, through September 30, 2006

    Energy Technology Data Exchange (ETDEWEB)

    None

    2006-09-30

    The Office of Space and Defense Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. For the Cassini Mission, ORNL produced carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS) used in the generators. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. This report reflects program guidance from the Office of Space and Defense Power Systems for fiscal year (FY) 2006. Production activities for prime quality (prime) CBCF insulator sets, iridium alloy blanks and foil, and CVS are summarized in this report. Technology activities are also reported that were conducted to improve the manufacturing processes, characterize materials, or to develop information for new radioisotope power systems.

  9. Annual Technical Progress Report of Radioisotope Power Systems Materials Production and Technology Program Tasks for October 1, 2007 Through September 30,2008

    Energy Technology Data Exchange (ETDEWEB)

    King, James F [ORNL

    2009-04-01

    The Office of Radioisotope Power Systems (RPS) of the Department of Energy (DOE) provides RPS for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration (NASA) for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. For the Cassini Mission, ORNL produced carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS) used in the generators. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. This report reflects program guidance from the Office of RPS for fiscal year (FY) 2008. Production activities for prime quality (prime) CBCF insulator sets, iridium alloy blanks and foil, and CVS are summarized in this report. Technology activities are also reported that were conducted to improve the manufacturing processes, characterize materials, or to develop information for new RPS.

  10. ANNUAL TECHNICAL PROGRESS REPORT OF RADIOISOTOPE POWER SYSTEM MATERIALS PRODUCTION AND TECHNOLOGY PROGRAM TASKS FOR OCTOBER 1, 2005 THROUGH SEPTEMBER 30, 2006

    Energy Technology Data Exchange (ETDEWEB)

    King, James F [ORNL

    2007-04-01

    The Office of Space and Defense Power Systems of the Department of Energy (DOE) provides Radioisotope Power Systems (RPS) for applications where conventional power systems are not feasible. For example, radioisotope thermoelectric generators were supplied by the DOE to the National Aeronautics and Space Administration for deep space missions including the Cassini Mission launched in October of 1997 to study the planet Saturn. For the Cassini Mission, ORNL produced carbon-bonded carbon fiber (CBCF) insulator sets, iridium alloy blanks and foil, and clad vent sets (CVS) used in the generators. The Oak Ridge National Laboratory (ORNL) has been involved in developing materials and technology and producing components for the DOE for more than three decades. This report reflects program guidance from the Office of Space and Defense Power Systems for fiscal year (FY) 2006. Production activities for prime quality (prime) CBCF insulator sets, iridium alloy blanks and foil, and CVS are summarized in this report. Technology activities are also reported that were conducted to improve the manufacturing processes, characterize materials, or to develop information for new radioisotope power systems.

  11. Hazardous materials in aquatic environments of the Mississippi River Basin Project management. Technical quarterly progress report, April 1, 1996--June 30, 1996

    Energy Technology Data Exchange (ETDEWEB)

    McLachlan, J.; Ide, C.F.; O`Connor, S.

    1996-08-01

    This quarterly report summarizes accomplishments for the Project examining hazardous materials in aquatic environments of the Mississippi River Basin. Among the many research areas summarized are the following: assessment of mechanisms of metal-induced reproductive toxicity in aquatic species as a biomarker of exposure; hazardous wastes in aquatic environment;ecological sentinels of aquatic contamination in the lower Mississippi River System; remediation of selected contaminants; rapid on-site immunassay for heavy metal contamination; molecular mechanisms of developmental toxicity induced by retinoids and retinoid-like molecules; resuseable synthetic membranes for the removal of aromatic and halogenated organic pollutants from waste water; Effects of steroid receptor activation in neurendocrine cell of the mammalian hypothalamus; modeling and assessment of environmental quality of louisiana bayous and swamps; enhancement of environmental education. The report also contains a summary of publications resulting from this project and an appendix with analytical core protocals and target compounds and metals.

  12. 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

  13. 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.)

  14. FY2016 Lightweight Materials Annual Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2017-10-31

    The Lightweight Materials research and development (R&D) area within the DOE Vehicle Technologies Office (VTO) provides support and guidance for many cutting-edge automotive technologies under development. Research focuses on addressing critical barriers to commercializing lightweight materials for passenger and commercial vehicles. This report describes the progress made on the research and development projects funded by the Lightweight Materials area.

  15. Technical considerations in materials management policy development

    International Nuclear Information System (INIS)

    Avci, H.; Goldberg, M.

    1996-01-01

    Under the Materials-in-Inventory (MIN) initiative, US DOE intends to develop policies to ensure that materials are managed and use efficiently, cost-effectively, and safely throughout DOE. The MIN initiative covers depleted uranium, scrap metals, chemicals, explosives, spent nuclear fuel, lead, alkali metals, etc.; by far the largest component is depleted uranium hexafluoride (DUF6). A technically defensible approach has been developed and is being used to select a long-term management strategy for DOE's DUF6 inventory. The same approach can be adapted to management of other materials in inventory that have the potential to be reutilized

  16. Sandia Laboratories technical capabilities: materials and processes

    International Nuclear Information System (INIS)

    Lundergan, C.D.; Mead, P.L.

    1977-08-01

    Materials and process activities have emphasized the balance between research and development necessary to provide materials compatible with the extreme environments and performance requirements associated with nuclear ordnance. Specific technical areas which have continuing emphasis include metallurgy, composites, surface characterization and thin films, polymers, ceramics, and high-temperature characterization. Complete processing and fabrication facilities assure the capability for early evaluation and use of tailored materials. Efforts are focused on material applications involving structural and electronic materials, thermal and electrical insulation, radiation shields, and shock mitigation. Key elements in these efforts are functionability, reliability, and longevity. This interdisciplinary approach to scientific materials engineering results from the recognition that many disciplines are required to understand, characterize, and apply materials, and from the fact that material design is an essential element in meeting the objectives of quality, functionality, and life. In effect, the responsibility of a materials group extends beyond the development of a material into the understanding and description of its behavior in the extreme environments to which it will be subjected

  17. 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.

  18. FY2016 Propulsion Materials Annual Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2017-05-01

    The Propulsion Materials Program actively supports the energy security and reduction of greenhouse emissions goals of VTO by investigating and identifying the materials properties that are most essential for continued development of cost-effective, highly efficient, and environmentally friendly next-generation heavy and light-duty powertrains. The technical approaches available to enhance propulsion systems focus on improvements in both vehicle efficiency and fuel substitution, both of which must overcome the performance limitations of the materials currently in use. Propulsion Materials Program activities work with national laboratories, industry experts, and VTO powertrain systems (e.g., Advanced Combustion Engines and Fuels) teams to develop strategies that overcome materials limitations in future powertrain performance. The technical maturity of the portfolio of funded projects ranges from basic science to subsystem prototype validation. Projects within a Propulsion Materials Program activity address materials concerns that directly impact critical technology barriers within each of the above programs, including barriers that impact fuel efficiency, thermal management, emissions reduction, improved reliability, and reduced manufacturing costs. The program engages only the barriers that result from material property limitations and represent fundamental, high-risk materials issues.

  19. 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.

  20. Plant materials program. Progress report, June 1980-May 1981

    International Nuclear Information System (INIS)

    Childs, W.; Cubicciotti, D.; Fox, M.; Giannuzzi, A.; Gilman, J.; Jones, R.; McIlree, A.

    1981-11-01

    This is the first annual progress report of the Plant Materials Subprogram, which was organized in May 1980 to address corrosion-related materials problems in light water reactors. The first section of the report provides an overview of plant materials problems which have a high impact on plant availability. These include pipe and pressure vessel cracking, condenser leakage, turbine disc cracking, and steam generator tube denting and cracking. The status and goals of research and development work related to each of these problems are reviewed briefly. Subsequent report sections provide more detailed reviews of significant progress in the relevant technical topic areas: intergranular stress corrosion cracking of austenitic stainless steels; environmentally-assisted cracking of carbon and low alloy steels; intergranular stress corrosion cracking of nickel-base alloys; and improved fabrication technology

  1. Plant Materials Program: progress June 1981 to May 1982

    International Nuclear Information System (INIS)

    Childs, W.; Cubicciotti, D.; Fox, M.; Giannuzzi, A.; Gilman, J.; Jones, R.

    1983-02-01

    This is the second annual progress report of the Plant Materials Subprogram, which was organized in May 1980 to address corrosion-related materials problems in light water reactors. The first section of the report provides an overview of plant materials problems which have a high impact on plant availability. These include pipe and pressure vessel cracking, condenser leakage, turbine disc cracking, steam geerator tube attack and cracking, and cracking of nickel alloy springs, beams and pins. The status and goals of research and development work related to each of these problems are reviewed briefly. Subsequent report sections provide more detailed reviews of significant progress in the relevant technical topic areas: intergranular stress corrosion cracking of austenitic stainless steels; environmentally-assisted cracking of carbon and low alloy steels; intergranular stress corrosion cracking of nickel-base alloys; and improved fabrication technology

  2. Plant Materials Program: progress June 1981-May 1982

    International Nuclear Information System (INIS)

    Childs, W.; Cubicciotti, D.; Fox, M.; Giannuzzi, A.; Gilman, J.; Jones, R.

    1983-02-01

    This is the second annual progress report of the Plant Materials Subprogram, which was organized in May 1980 to address corrosion-related materials problems in light water reactors. The first section of the report provides an overview of plant materials problems which have impact on plant availability. These include pipe and pressure vessel cracking, condenser leakage, turbine disc cracking, steam generator tube attack and cracking, and cracking of nickel alloy springs, beams and pins. The status and goals of research and development work related to each of these problems are reviewed briefly. Subsequent report sections provide more detailed reviews of significant progress in the relevant technical topic area: integranular stress corrosion cracking of austenitic stainless steels; environmentally-assisted cracking of carbon and low alloy steels; intergranular stress corrosion cracking of nickel-base alloys; and improved fabrication technology

  3. Progress in molecular precursors for electronic materials

    Energy Technology Data Exchange (ETDEWEB)

    Buhro, W.E. [Washington Univ., St. Louis, MO (United States)

    1996-09-01

    Molecular-precursor chemistry provides an essential underpinning to all electronic-materials technologies, including photovoltaics and related areas of direct interest to the DOE. Materials synthesis and processing is a rapidly developing field in which advances in molecular precursors are playing a major role. This article surveys selected recent research examples that define the exciting current directions in molecular-precursor science. These directions include growth of increasingly complex structures and stoichiometries, surface-selective growth, kinetic growth of metastable materials, growth of size-controlled quantum dots and quantum-dot arrays, and growth at progressively lower temperatures. Continued progress in molecular-precursor chemistry will afford precise control over the crystal structures, nanostructures, and microstructures of electronic materials.

  4. 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.

  5. 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.

  6. 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

  7. 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.

  8. Fusion materials semiannual progress report for period ending December 31, 1999

    Energy Technology Data Exchange (ETDEWEB)

    Burn, G.

    2000-03-01

    This is the twenty-seventh in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components.

  9. Fusion materials semiannual progress report for period ending December 31, 1999

    International Nuclear Information System (INIS)

    Burn, G.

    2000-01-01

    This is the twenty-seventh in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components

  10. 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.

  11. 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

  12. Assessment of material and technical resources of crop production technologies

    Directory of Open Access Journals (Sweden)

    V. M. Beylis

    2017-01-01

    Full Text Available The author explains the general principles of influence of the material and technical resources (MTR on performance and efficiency of the main technological operations in crop production. Various technologies from the point of view of MTR expenses were estimated. The general tendencies in development of crop production technologies were revealed. The distribution of costs of materials and equipment to perform a variety of agricultural activities was determined. Cost indicators should be a guide in the search of innovative technological processes and working elements of agricultural machins. The greatest values of expenses of work, fuel, metal, and also, money where found. The concepts allowing to provide costs production reduction were formulated. To achieve the maximum productivity with the minimum expenses, the perspective calculations shoul be based on «progressive» agrotechnologies. When determining progressive agrotechnology it is necessary on reasonable grounds to approach indicators of crop productivity in various agrozones and regions of the country. For an assessment of efficiency of MTR by crop production and ensuring decrease in resource intensity of agricultural products by search and use of essentially new technologies for energy saving when performing agricultural operations, an integrated percentage indicator of comparison of progressive technologies with the applied ones was developed. MTR at application of new progressive crop production technologies by integrated percentage index were estimated. This indicator can be used for definition of efficiency of MTR. Application of the offered technique will promote an effective assessment of MTR, decrease in resource intensity by search and developments of essentially new technologies of performance of operations in crop production.

  13. 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...

  14. 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.

  15. FY2011 Annual Progress Report for Propulsion Materials

    Energy Technology Data Exchange (ETDEWEB)

    Davis, Patrick B. [Office of Energy Efficiency and Renewable Energy (EERE), Washington, DC (United States); Schutte, Carol L. [Office of Energy Efficiency and Renewable Energy (EERE), Washington, DC (United States); Gibbs, Jerry L. [Office of Energy Efficiency and Renewable Energy (EERE), Washington, DC (United States)

    2011-12-01

    Annual Progress Report for Propulsion Materials focusing on enabling and innovative materials technologies that are critical in improving the efficiency of advanced engines by providing enabling materials support for combustion, hybrid, and power electronics development.

  16. Fusion reactor materials. Semiannual progress report for period ending September 30, 1993

    Energy Technology Data Exchange (ETDEWEB)

    Rowcliffe, A.F.; Burn, G.L.; Knee`, S.S.; Dowker, C.L. [comps.

    1994-02-01

    This is the fifteenth in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following progress reports: Alloy Development for Irradiation Performance; Damage Analysis and Fundamental Studies; Special purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the U.S. Department of Energy. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide.

  17. Logistic management materials-technical support railway enterprises

    OpenAIRE

    Dykan, V.; Borozenetc, T.

    2014-01-01

    The essence of logistics management. Determine the feasibility of applying the principles of logistics management in organizing the logistics of railway transport. Discussed measures to develop suppliers in the implementation of logistics management logistics. Identified the need to develop and implement regulatory and methodical system to improve materials-technical support through the introduction of modern logistics principles. Applied systemic campaign to organize the materials-technical ...

  18. 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)

  19. FY2009 Annual Progress Report for Propulsion Materials

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2010-01-16

    The Propulsion Materials program focuses on enabling and innovative materials technologies that are critical in improving the efficiency of advanced engines. Projects within the Propulsion Materials Program address materials concerns that directly impact the critical technical barriers in each of these programs—barriers such as fuel efficiency, thermal management, emissions reduction, and reduced manufacturing costs.

  20. 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.

  1. Heavy Vehicle Propulsion Materials Program: Progress and Highlights

    International Nuclear Information System (INIS)

    D. Ray Johnson; Sidney Diamond

    2000-01-01

    The Heavy Vehicle Propulsion Materials Program was begun in 1997 to support the enabling materials needs of the DOE Office of Heavy Vehicle Technologies (OHVT). The technical agenda for the program grew out of the technology roadmap for the OHVT and includes efforts in materials for: fuel systems, exhaust aftertreatment, valve train, air handling, structural components, electrochemical propulsion, natural gas storage, and thermal management. A five-year program plan was written in early 2000, following a stakeholders workshop. The technical issues and planned and ongoing projects are discussed. Brief summaries of several technical highlights are given

  2. Materials Department annual progress report for 1993

    International Nuclear Information System (INIS)

    Horsewell, A.; Hansen, N.

    1994-06-01

    Selected activities of the Materials Department at Risoe National Laboratory during 1993 are described. The work is presented in three chapters: Materials Science, Materials Engineering and Materials Technology. A survey is given of the Department's participation in international collaboration and of its activities within education and training. Furthermore, the main figures outlining the funding and expenditure of the Department are given. Lists of staff members, visiting scientists, publications, lectures and poster presentations are included. (au) (220 refs.)

  3. 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

  4. Fusion Materials Semiannual Progress Report for Period Ending December 31, 1998

    Energy Technology Data Exchange (ETDEWEB)

    Rowcliff, A.F.; Burn, G.

    1999-04-01

    This is the twenty-fifth in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the U.S. Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately.

  5. Fusion Materials Semiannual Progress Report for the Period Ending June 30, 1999

    Energy Technology Data Exchange (ETDEWEB)

    Rowcliffe, A.F.

    1999-09-01

    This is the twenty-sixth in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and its reported separately.

  6. Heavy Vehicle Propulsion Materials: Recent Progress and Future Plans

    International Nuclear Information System (INIS)

    D. Ray Johnson; Sidney Diamond

    2001-01-01

    The Heavy Vehicle Propulsion Materials Program provides enabling materials technology for the U.S. DOE Office of Heavy Vehicle Technologies (OHVT). The technical agenda for the program is based on an industry assessment and the technology roadmap for the OHVT. A five-year program plan was published in 2000. Major efforts in the program are materials for diesel engine fuel systems, exhaust aftertreatment, and air handling. Additional efforts include diesel engine valve-train materials, structural components, and thermal management. Advanced materials, including high-temperature metal alloys, intermetallics, cermets, ceramics, amorphous materials, metal- and ceramic-matrix composites, and coatings, are investigated for critical engine applications. Selected technical issues and planned and ongoing projects as well as brief summaries of several technical highlights are given

  7. Energy Materials Coordinating Committee, fiscal year 1997. Annual technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-31

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department`s materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. This report summarizes EMaCC activities for FY 1997 and describes the materials research programs of various offices and divisions within the Department.

  8. 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

  9. 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)

  10. 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

  11. 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

  12. 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

  13. Progress in the materials science of silicene.

    Science.gov (United States)

    Yamada-Takamura, Yukiko; Friedlein, Rainer

    2014-12-01

    In its freestanding, yet hypothetical form, the Si counterpart of graphene called silicene is predicted to possess massless Dirac fermions and to exhibit an experimentally accessible quantum spin Hall effect. Such interesting electronic properties are not realized in two-dimensional (2D) Si honeycomb lattices prepared recently on metallic substrates where the crystal and hybrid electronic structures of these 'epitaxial silicene' phases are strongly influenced by the substrate, and thus different from those predicted for isolated 2D structures. While the realization of such low-dimensional Si π materials has hardly been imagined previously, it is evident that the materials science behind silicene remains challenging. In this contribution, we will review our recent results that lead to an enhanced understanding of epitaxial silicene formed on diboride thin films, and discuss the remaining challenges that must be addressed in order to turn Si 2D nanostructures into technologically interesting nanoelectronic materials.

  14. Fusion reactor materials semiannual progress report for the period ending March 31, 1993

    International Nuclear Information System (INIS)

    1993-07-01

    This is the fourteenth in a series of semiannual technical progress reports on fusion reactor materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the US Depart of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. Separate abstracts were prepared for each individual section

  15. Fusion materials semiannual progress report for the period ending June 30, 1998

    International Nuclear Information System (INIS)

    Burn, G.

    1998-09-01

    This is the twenty-fourth in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database

  16. Fusion materials semiannual progress report for the period ending June 30, 1998

    Energy Technology Data Exchange (ETDEWEB)

    Burn, G. [ed.] [comp.

    1998-09-01

    This is the twenty-fourth in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

  17. Fusion reactor materials semiannual progress report for the period ending March 31, 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-07-01

    This is the fourteenth in a series of semiannual technical progress reports on fusion reactor materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the US Depart of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. Separate abstracts were prepared for each individual section.

  18. FY2015 Lightweight Materials R&D Annual Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2016-09-30

    The Lightweight Materials research and development (R&D) area within the DOE Vehicle Technologies Office (VTO) provides support and guidance for many cutting-edge automotive technologies under development. Research focuses on addressing critical barriers to commercializing lightweight materials for passenger and commercial vehicles. This report describes the progress made on the research and development projects funded by the Lightweight Materials area.

  19. Fusion materials semiannual progress report for the period ending March 31, 1995

    International Nuclear Information System (INIS)

    1995-07-01

    This is the eighteenth in a series of semiannual technical progress reports on fusion materials. This report combines research and development activities which were previously reported separately in the following progress reports: sm-bullet Alloy Development for Irradiation Performance. sm-bullet Damage Analysis and Fundamental Studies. sm-bullet Special Purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide. This report has been compiled and edited under the guidance of A.F. Rowcliffe by Gabrielle Burn, Oak Ridge National Laboratory. Their efforts, and the efforts of the many persons who made technical contributions, are gratefully acknowledged

  20. Fusion reactor materials semiannual progress report for period ending September 30, 1990

    International Nuclear Information System (INIS)

    1991-04-01

    This is the ninth in series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following technical progress reports: Alloy Development of Irradiation Performance; Damage Analysis and Fundamental Studies; and Special Purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials program being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide

  1. Fusion reactor materials: Semiannual progress report for period ending September 30, 1987

    International Nuclear Information System (INIS)

    1988-03-01

    This is the third in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following technical progress reports: Alloy Development for Irradiation Performances; Damage Analysis and Fundamental Studies; Special Purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials program being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide

  2. Fusion materials semiannual progress report for the period ending March 31, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This is the eighteenth in a series of semiannual technical progress reports on fusion materials. This report combines research and development activities which were previously reported separately in the following progress reports: {sm_bullet} Alloy Development for Irradiation Performance. {sm_bullet} Damage Analysis and Fundamental Studies. {sm_bullet} Special Purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide. This report has been compiled and edited under the guidance of A.F. Rowcliffe by Gabrielle Burn, Oak Ridge National Laboratory. Their efforts, and the efforts of the many persons who made technical contributions, are gratefully acknowledged.

  3. 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.

  4. Progress in III-V materials technology

    Science.gov (United States)

    Grant, Ian R.

    2004-12-01

    Compound semiconductors, in the form of GaAs and InP have achieved major commercial significance in areas of application such as mobile communications, displays and telecoms and offer a versatility of function beyond the capabilities of Si. III-V compounds, and in particular GaAs, have since their early development been the subject of defence related interest. Support from this sector established the basic materials technologies and nurtured development up until their commercial breakthrough into consumer products. GaAs, for example, now provides essential components for mobile phones and CD / DVD players. An overview is presented of the crystal growth and processing methods used in the manufacture of these materials. Current state of the art characteristics on crystal form and quality are discussed, together with the evolution of single crystal growth techniques. Consideration is given to how these principal compounds together with the minor materials, InSb, GaSb and InAs are employed in diverse applications over a broad spectral range, together with information on markets and future perspectives.

  5. 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.

  6. 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

  7. 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.

  8. 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)

  9. 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.

  10. 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

  11. 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

  12. Thermoelectric materials evaluation program. Quarterly technical task report No. 46

    International Nuclear Information System (INIS)

    Hampl, E.F. Jr.

    1976-02-01

    This forty-sixth Technical Task Report prepared under contract E(11-1)-2331 with the U.S. AEC and U.S. ERDA covers the performance period from October 1, 1975, to December 31, 1975. Highlights include the following tasks: N-type material development (material synthesis--gadolinium selenide compositions; material analyses; material processing; element contacting; ingradient compatibility and life testing; mechanical property characterization), TPM-217 P-type characterization (material preparation and analyses; element contacting; thermodynamic stability; isothermal chemical compatibility; ingradient compatibility and ingradient life testing; performance mapping of contacted and noncontacted elements; high-temperature partitioned P-legs), couple development (design and development of TPM-217/gadolinium selenide rare earth chalcogenide couple; design and development of TPM-217/3N-PbTe couples; advanced generator concepts), module development, liaison with Jet Propulsion Laboratory and material supply, liaison with GGA, and program management. 24 figures, 27 tables

  13. 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.)

  14. 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.)

  15. Fusion materials semiannual progress report for period ending June 30, 1997

    International Nuclear Information System (INIS)

    1997-08-01

    This is the twenty-second in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. Topics covered here are: vanadium alloys; silicon carbide composites; ferritic/martensitic steels; austenitic stainless steels; insulating ceramics and optical materials; solid breeding materials; radiation effects mechanistic studies and experimental methods; dosimetry damage parameters; activation calculations; materials engineering and design requirements; irradiation facilities; test matrices; and experimental methods

  16. Fusion materials semiannual progress report for period ending June 30, 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-08-01

    This is the twenty-second in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. Topics covered here are: vanadium alloys; silicon carbide composites; ferritic/martensitic steels; austenitic stainless steels; insulating ceramics and optical materials; solid breeding materials; radiation effects mechanistic studies and experimental methods; dosimetry damage parameters; activation calculations; materials engineering and design requirements; irradiation facilities; test matrices; and experimental methods.

  17. 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.

  18. 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.)

  19. Progress report, Chemistry and Materials Division

    International Nuclear Information System (INIS)

    1981-05-01

    Laser radiation has been used to anneal damage created by implantation of arsenic ions into silicon single-crystal wafers. The threshold for recovery of lattice order, as measured by ion channeling methods, appeared at an energy density of 1.2 J.cm -2 . Deuterium-enriched water has been recovered for the first time in visible amounts from a process based on laser photolysis. High performance liquid chromatography has been applied to the determination of U(VI) in ground water and urine. Results with low ground water concentrations were judged to be successful, while only limited success was achieved with urine. The first analyses in support of the production of (Th,Pu)O 2 fuel elements were completed successfully. Experiments performed during the quarter have shown that cracking of Zr-2.5 percent Nb alloy by gaseous hydrogen is inhibited by traces of oxygen. It was found that there was no inhibition by helium in the absence of trace oxygen. Excellent agreement has been obtained between the growth and creep constants derived from ion-irradiated cantilever beam specimens and those from reactor irradiation of the same materials. (O.T.)

  20. 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)

  1. Second quarter technical progress report for Thermally Modified Sand

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-14

    The objective was to have the Alaska Department of Transportation & Public Facilities Operation & Maintenance Section use Thermally Modified Sand (TMS) for treatment of icy state roadways. The project included the evaluation on the workability of a large stockpile of TMS material left undisturbed throughout the 1993/94 winter season.

  2. Material and energy balances of technical means in horticulture and farming - from production to disposal

    International Nuclear Information System (INIS)

    1993-01-01

    The twenty papers of this progress report, which are not individually recorded, belong to either one of the subject areas ''material and energy balances of technical means in horticulture and forming from production to disposal'' and ''plastics in construction and technical systems''. The first-mentioned subject area deals with balances for technical means at horticultural enterprises, greenhouse constructions, and styrofoam in farm buildings, and comprises short papers on sewage treatment plants in the form of beds of plants and ecological aspects of horticultural activities in open spaces. The second subject area mainly concerns recycling and multiple uses of plastics (silage and protective foils) as well as air-flow thermal collector systems. Advances in the construction and use of foil-covered greenhouses and experience with protective nets for plant cultures, energy shields, and shading are reported. (UWA) [de

  3. 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

  4. Nuclear Safety: Technical progress review, January--March 1989

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E. G. [ed.

    1989-01-01

    This review journal covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  5. Nuclear Safety: Technical progress review, January-March 1988

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1988-01-01

    This journal covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  6. 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.

  7. Near-real-time material accountancy - A technical status report

    International Nuclear Information System (INIS)

    Lovett, J.; Ikawa, K.; Sellinschegg, D.; Shipley, J.

    1983-01-01

    Near-Real-time materials accountancy as applied to reprocessing plants involves two major elements, measurement of the in-process physical inventory at frequent intervals, and statistical evaluation of the resulting sequential material balance data. For most reprocessing plants the bulk of the in-process inventory is in measurable intermediate ''buffer'' tanks. The plutonium inventory in the solvent extraction system, which does not appear to be directly measureable, could cause a reduction in sensitivity of the sequential data analysis. Studies are in progress, and it is hoped that an acceptable means for accounting for these variations can be found. Consultants at a meeting in January 1982 agreed that statistical tests for evaluating sequential material balance data will increase both detection timeliness and detection sensitivity. IAEA verification of operator-generated measurement data is an area requiring significantly increased effort, but here too studies are in progress which should help to reduce inspection effort in increased effectiveness

  8. 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

  9. Technical Division quarterly progress report, April 1--June 30, 1977

    Energy Technology Data Exchange (ETDEWEB)

    Slansky, C.M.; Dickey, B.R.; Musgrave, B.C.; Rohde, K.L.

    1977-07-01

    Fuel Cycle Research and Development: Results are presented on the fluidized-bed calcination of high-level radioactive waste from reprocessing on the post treatment of the calcine, and on the removal of actinide elements from the waste prior to calcination. Other projects include the development of storage technology for /sup 85/Kr waste; a study of the hydrogen mordenite catalyzed reaction between NO/sub x/ and NH/sub 3/; the adsorption and storage of /sup 129/I on silver exchanged mordenite; physical properties, materials of construction, and unit operations studies on the evaporation of high-level waste; the behavior of volatile radionuclides during the combustion of HTGR graphite-based fuel; and the use of the uranium-ruthenium system in age-dating uranium ore bodies. Special Materials Production: The long-term management of defense waste from the ICPP covers postcalcination treatment of ICPP calcined waste; the removal of actinide elements from first-cycle raffinate; the retrieval and handling of calcined waste from ICPP storage vaults; and the preparation of the ''Defense Waste Document''. Process improvements are reported on the Fluorinel headend process for Zircaloy-clad fuels and on uranium accountability measurements. Other development results cover the process for recovering spent Rover fuel, buried pipeline transfer systems, support to the Waste Management Program, and effluent monitoring methods evaluation and development. Other Projects Supporting Energy Development: In this category are studies on nuclear materials security; application of a liquid-solid fluidized-bed heat exchanger to the recovery of geothermal heat; in-plant reactor source term measurements; burnup methods for fast breeder reactor fuels; absolute thermal fission yield measurements; analytical support to light water breeder reactor development; research on analytical methods; and the behavior of environmental species of iodine.

  10. Nulcear Safety: Technical progress review, October--December 1988

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1988-01-01

    Nuclear Safety is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  11. 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

  12. Nuclear Safety: Volume 29, No. 3: Technical progress review

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1988-07-01

    Nuclear Safety is a review journal that covers significant development in the field of nuclear safety. Its scope included the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated. Individual papers have been cataloged separately.

  13. Recent Progress in Advanced Materials for Lithium Ion Batteries

    Directory of Open Access Journals (Sweden)

    Jiajun Chen

    2013-01-01

    Full Text Available The development and commercialization of lithium ion batteries is rooted in material discovery. Promising new materials with high energy density are required for achieving the goal toward alternative forms of transportation. Over the past decade, significant progress and effort has been made in developing the new generation of Li-ion battery materials. In the review, I will focus on the recent advance of tin- and silicon-based anode materials. Additionally, new polyoxyanion cathodes, such as phosphates and silicates as cathode materials, will also be discussed.

  14. FY2014 Propulsion Materials R&D Annual Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    None

    2015-05-01

    The Propulsion Materials Program actively supports the energy security and reduction of greenhouse emissions goals of VTO by investigating and identifying the materials properties that are most essential for continued development of cost-effective, highly efficient, and environmentally friendly next-generation heavy and light-duty powertrains. The technical approaches available to enhance propulsion systems focus on improvements in both vehicle efficiency and fuel substitution, both of which must overcome the performance limitations of the materials currently in use. Propulsion Materials Program activities work with national laboratories, industry experts, and VTO powertrain systems (e.g., Advanced Combustion Engines [ACE], Advanced Power Electronics and Electrical Machines [APEEM], and fuels) teams to develop strategies that overcome materials limitations in future powertrain performance. The technical maturity of the portfolio of funded projects ranges from basic science to subsystem prototype validation. Projects within a Propulsion Materials Program activity address materials concerns that directly impact critical technology barriers within each of the above programs, including barriers that impact fuel efficiency, thermal management, emissions reduction, improved reliability, and reduced manufacturing costs. The program engages only the barriers that result from material property limitations and represent fundamental, high-risk materials issues.

  15. Fusion Reactor Materials semiannual progress report for the period ending March 31, 1992

    Energy Technology Data Exchange (ETDEWEB)

    1992-07-01

    This is the twelfth in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following progress reports: Alloy Development for Irradiation Performance; Damage Analysis and Fundamental Studies; and Special Purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide.

  16. Fusion Reactor Materials semiannual progress report for the period ending March 31, 1992

    International Nuclear Information System (INIS)

    1992-07-01

    This is the twelfth in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following progress reports: Alloy Development for Irradiation Performance; Damage Analysis and Fundamental Studies; and Special Purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide

  17. Fusion reactor materials semiannual progress report for the period ending March 31, 1991

    Energy Technology Data Exchange (ETDEWEB)

    none,

    1991-07-01

    This is the tenth in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following progress reports: alloy development for irradiation performance; damage analysis and fundamental studies; special purpose materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials program being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of program participants, and to provide a means of communicating the efforts of materials scientists to the test of the fusion community, both nationally and worldwide.

  18. Fusion materials semiannual progress report for the period ending September 30, 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    This is the sixteenth in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following Progress reports: Alloy Development for Irradiation Performance; Damage Analysis and Fundamental Studies; and Special Purpose Materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide. The individual papers in this paper have been cataloged separately elsewhere.

  19. Fusion reactor materials semiannual progress report for the period ending March 31, 1991

    International Nuclear Information System (INIS)

    1991-07-01

    This is the tenth in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately in the following progress reports: alloy development for irradiation performance; damage analysis and fundamental studies; special purpose materials. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials program being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Reactor Materials Program is a national effort involving several national laboratories, universities, and industries. The purpose of this series of reports is to provide a working technical record for the use of program participants, and to provide a means of communicating the efforts of materials scientists to the test of the fusion community, both nationally and worldwide

  20. Computerized access to materials data. A progress report

    International Nuclear Information System (INIS)

    Rumble, J. Jr.

    1985-01-01

    As the effort to build a comprehensive computerized materials data system grows, it becomes more obvious that the benefits will be far-reaching. During this workshop, the enthusiasm of the participants grew steadily until the questions became not''What,'' but ''When?''. The engineering community within the United States has banded together many times to advance progress in engineering capability. The computerized materials data system requires such an effort, and the rewards will be substantial. Chapter 3 identifies changes in the use of materials data in the Nuclear Power Industry. Chapter 4 describes the EPRI experience in building computerized materials databases. In Chapter 5, the National Materials Property Data Network is discussed. The next four chapters present summaries of the workshop discussions and its conclusions. Chapter 6 discusses the content of the proposed system, Chapter 7 its size and the data sources, and Chapter 8 the user interfaces and system capabilities. In Chapter 9, ways of making further progress are outlined

  1. Technical regulations for road transport of radioactive materials

    International Nuclear Information System (INIS)

    Juul-Jensen, P.; Ulbak, K.

    1990-01-01

    The technical regulations for the transport of radioactive materials in Denmark are set down by the (Danish) National Board of Health in collaboration with the (Danish) National Institute for Radiation Hygiene in accordance with paragraph 3 of the Danish Ministry of Justice's Executive Order no. 2 of 2, January 1985 on the national road transport of dangerous goods by road, as amended by exutive order no. 251 of April 29th 1987 and no. 704 of November 1989. These regulations are presented here. They are almost identical, with only very few exceptions indicated in the publication, with the rules for Class 7 of the European convention on international transport of dangerous goods by road (ADR). In addition to the aforementioned regulations for national road transport of radioactive materials the general rules for the transport of radioactive materials found in the National Board of Health's executive order no. 721 of November 27th 1989 on the transport of radioactive materials are valid. The abovementioned executive orders, with the exception of certain supplements which are not part of the technical regulations, are also contained in this publication. (AB)

  2. 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.

  3. Technical limitations of nuclear fuel materials and structures

    International Nuclear Information System (INIS)

    Hansson, L.; Planman, T.; Vitikainen, E.

    1993-05-01

    This report gives a summary of the tasks carried out within the project 'Technical limitations of nuclear fuel materials and structures' which belongs to the Finnish national research programme called 'Systems behaviour and operational aspects of safety'. The duration of the project was three years from 1990 to 1992. Most western LWR utilities, including the two Finnish ones have an incentive to implement extended burnup fuel cycles in their nuclear power plants. The aim of this project has been authorities to support them in the assessment and licensing of new fuel designs and materials. The research work of the project was focused on collecting and qualifying fuel performance data and on performing laboratory tests on fresh and irradiated cladding and structural materials. Moreover, knowledge of the high burnup phenomena was obtained through participation in international research projects such as OECD Halden Project and several Studsvik projects. Experimental work within the framework of the VVER fuel cooperative effort was also continued. (orig.)

  4. MISSE in the Materials and Processes Technical Information System (MAPTIS )

    Science.gov (United States)

    Burns, DeWitt; Finckenor, Miria; Henrie, Ben

    2013-01-01

    Materials International Space Station Experiment (MISSE) data is now being collected and distributed through the Materials and Processes Technical Information System (MAPTIS) at Marshall Space Flight Center in Huntsville, Alabama. MISSE data has been instrumental in many programs and continues to be an important source of data for the space community. To facilitate great access to the MISSE data the International Space Station (ISS) program office and MAPTIS are working to gather this data into a central location. The MISSE database contains information about materials, samples, and flights along with pictures, pdfs, excel files, word documents, and other files types. Major capabilities of the system are: access control, browsing, searching, reports, and record comparison. The search capabilities will search within any searchable files so even if the desired meta-data has not been associated data can still be retrieved. Other functionality will continue to be added to the MISSE database as the Athena Platform is expanded

  5. 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)

  6. 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

  7. 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

  8. 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

  9. The Natural Hospital Environment: a Socio-Technical-Material perspective.

    Science.gov (United States)

    Fernando, Juanita; Dawson, Linda

    2014-02-01

    This paper introduces two concepts into analyses of information security and hospital-based information systems-- a Socio-Technical-Material theoretical framework and the Natural Hospital Environment. The research is grounded in a review of pertinent literature with previously published Australian (Victoria) case study data to analyse the way clinicians work with privacy and security in their work. The analysis was sorted into thematic categories, providing the basis for the Natural Hospital Environment and Socio-Technical-Material framework theories discussed here. Natural Hospital Environments feature inadequate yet pervasive computer use, aural privacy shortcomings, shared workspace, meagre budgets, complex regulation that hinders training outcomes and out-dated infrastructure and are highly interruptive. Working collaboratively in many cases, participants found ways to avoid or misuse security tools, such as passwords or screensavers for patient care. Workgroup infrastructure was old, architecturally limited, haphazard in some instances, and was less useful than paper handover sheets to ensure the quality of patient care outcomes. Despite valiant efforts by some participants, they were unable to control factors influencing the privacy of patient health information in public hospital settings. Future improvements to hospital-based organisational frameworks for e-health can only be made when there is an improved understanding of the Socio-Technical-Material theoretical framework and Natural Hospital Environment contexts. Aspects within control of clinicians and administrators can be addressed directly although some others are beyond their control. An understanding and acknowledgement of these issues will benefit the management and planning of improved and secure hospital settings. Copyright © 2013 Elsevier Ireland Ltd. All rights reserved.

  10. Technical Education Outreach in Materials Science and Technology Based on NASA's Materials Research

    Science.gov (United States)

    Jacobs, James A.

    2003-01-01

    The grant NAG-1 -2125, Technical Education Outreach in Materials Science and Technology, based on NASA s Materials Research, involves collaborative effort among the National Aeronautics and Space Administration s Langley Research Center (NASA-LaRC), Norfolk State University (NSU), national research centers, private industry, technical societies, colleges and universities. The collaboration aims to strengthen math, science and technology education by providing outreach related to materials science and technology (MST). The goal of the project is to transfer new developments from LaRC s Center for Excellence for Structures and Materials and other NASA materials research into technical education across the nation to provide educational outreach and strengthen technical education. To achieve this goal we are employing two main strategies: 1) development of the gateway website and 2) using the National Educators Workshop: Update in Engineering Materials, Science and Technology (NEW:Updates). We have also participated in a number of national projects, presented talks at technical meetings and published articles aimed at improving k-12 technical education. Through the three years of this project the NSU team developed the successful MST-Online site and continued to upgrade and update it as our limited resources permitted. Three annual NEW:Updates conducted from 2000 though 2002 overcame the challenges presented first by the September 11,2001 terrorist attacks and the slow U.S. economy and still managed to conduct very effective workshops and expand our outreach efforts. Plans began on NEW:Update 2003 to be hosted by NASA Langley as a part of the celebration of the Centennial of Controlled Flight.

  11. 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)

  12. Mixing of incompatible materials in waste tanks technical basis document

    International Nuclear Information System (INIS)

    SANDGREN, K.R.

    2003-01-01

    This technical basis document was developed to support the Tank Farms Documented Safety Analysis (DSA) and describes the risk binning process, the technical basis for assigning risk bins, and the controls selected for the mixing of incompatible materials representative accident and associated represented hazardous conditions. The purpose of the risk binning process is to determine the need for safety-significant structures, systems, and components (SSCs) and/or technical safety requirement (TSR)-level controls for a given representative accident or represented hazardous conditions based on an evaluation of the FR-equency and consequence. Note that the risk binning process is not applied to facility workers, because all facility worker hazardous conditions are considered for safety-significant SSCs and/or TSR level controls. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, ''Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'', as described in this report

  13. 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

  14. RELEASE OF DRIED RADIOACTIVE WASTE MATERIALS TECHNICAL BASIS DOCUMENT

    International Nuclear Information System (INIS)

    KOZLOWSKI, S.D.

    2007-01-01

    This technical basis document was developed to support RPP-23429, Preliminary Documented Safety Analysis for the Demonstration Bulk Vitrification System (PDSA) and RPP-23479, Preliminary Documented Safety Analysis for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Facility. The main document describes the risk binning process and the technical basis for assigning risk bins to the representative accidents involving the release of dried radioactive waste materials from the Demonstration Bulk Vitrification System (DBVS) and to the associated represented hazardous conditions. Appendices D through F provide the technical basis for assigning risk bins to the representative dried waste release accident and associated represented hazardous conditions for the Contact-Handled Transuranic Mixed (CH-TRUM) Waste Packaging Unit (WPU). The risk binning process uses an evaluation of the frequency and consequence of a given representative accident or represented hazardous condition to determine the need for safety structures, systems, and components (SSC) and technical safety requirement (TSR)-level controls. A representative accident or a represented hazardous condition is assigned to a risk bin based on the potential radiological and toxicological consequences to the public and the collocated worker. Note that the risk binning process is not applied to facility workers because credible hazardous conditions with the potential for significant facility worker consequences are considered for safety-significant SSCs and/or TSR-level controls regardless of their estimated frequency. The controls for protection of the facility workers are described in RPP-23429 and RPP-23479. Determination of the need for safety-class SSCs was performed in accordance with DOE-STD-3009-94, Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses, as described below

  15. 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

  16. Transportation of nuclear material in France: regulatory and technical aspects

    International Nuclear Information System (INIS)

    Flory, D.; Renard, C.

    1995-01-01

    Legislative and regulatory documentation define responsibilities in the field of security and physical protection for transportation of nuclear material. Any transportation activity has to conform to an advance authorization regime delivered by the Ministry of Industry. Responsibility for physical protection of nuclear material rests with the carrier under control of the public authority. Penalties reinforce this administrative regime. Operational responsibility for management and control of transport operations has been entrusted by the ministry to the operational transport unit (Echelon Operationnel des Transports - EOT) of IPSN (Institute for Nuclear Protection and Safety). To guarantee en efficient protection of transport operations, the various following means are provided for: -specialized transport means; - devices for real time tracking of road vehicles; - administrative authorization and declaration procedures; -intervention capacities in case of sabotage... This set of technical means and administrative measures is completed by the existence of a body of inspectors who may control every step of the operations. (authors). 3 tabs

  17. Materials And Processes Technical Information System (MAPTIS) LDEF materials data base

    Science.gov (United States)

    Funk, Joan G.; Strickland, John W.; Davis, John M.

    1993-01-01

    A preliminary Long Duration Exposure Facility (LDEF) Materials Data Base was developed by the LDEF Materials Special Investigation Group (MSIG). The LDEF Materials Data Base is envisioned to eventually contain the wide variety and vast quantity of materials data generated from LDEF. The data is searchable by optical, thermal, and mechanical properties, exposure parameters (such as atomic oxygen flux) and author(s) or principal investigator(s). Tne LDEF Materials Data Base was incorporated into the Materials and Processes Technical Information System (MAPTIS). MAPTIS is a collection of materials data which has been computerized and is available to engineers, designers, and researchers in the aerospace community involved in the design and development of spacecraft and related hardware. The LDEF Materials Data Base is described and step-by-step example searches using the data base are included. Information on how to become an authorized user of the system is included.

  18. Recent Progress in First-Principles Methods for Computing the Electronic Structure of Correlated Materials

    Directory of Open Access Journals (Sweden)

    Fredrik Nilsson

    2018-03-01

    Full Text Available Substantial progress has been achieved in the last couple of decades in computing the electronic structure of correlated materials from first principles. This progress has been driven by parallel development in theory and numerical algorithms. Theoretical development in combining ab initio approaches and many-body methods is particularly promising. A crucial role is also played by a systematic method for deriving a low-energy model, which bridges the gap between real and model systems. In this article, an overview is given tracing the development from the LDA+U to the latest progress in combining the G W method and (extended dynamical mean-field theory ( G W +EDMFT. The emphasis is on conceptual and theoretical aspects rather than technical ones.

  19. Materials of 3. scientific-technical seminar: Materials Investigation for Power Industry

    International Nuclear Information System (INIS)

    1996-01-01

    The report is an assembly of the papers concerning material problems during the exploitation of power stations as well as during construction and exploitation of gas pipelines. The accreditation problems according to the European Standards and Office of Technical Inspection prescription are also discussed

  20. 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...

  1. 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.

  2. Fusion materials semiannual progress report for the period ending December 31, 1997

    International Nuclear Information System (INIS)

    Burn, G.

    1998-03-01

    This is the twenty-third in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The Fusion Materials Program is a national effort involving several national laboratories, universities, and industries. A large fraction of this work, particularly in relation to fission reactor experiments, is carried out collaboratively with their partners in Japan, Russia, and the European Union. The purpose of this series of reports is to provide a working technical record for the use of the program participants, and to provide a means of communicating the efforts of materials scientists to the rest of the fusion community, both nationally and worldwide

  3. 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.

  4. Advanced Industrial Materials (AIM) Program: Annual progress report FY 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    In many ways, the Advanced Industrial Materials (AIM) Program underwent a major transformation in Fiscal Year 1995 and these changes have continued to the present. When the Program was established in 1990 as the Advanced Industrial Concepts (AIC) Materials Program, the mission was to conduct applied research and development to bring materials and processing technologies from the knowledge derived from basic research to the maturity required for the end use sectors for commercialization. In 1995, the Office of Industrial Technologies (OIT) made radical changes in structure and procedures. All technology development was directed toward the seven ``Vision Industries`` that use about 80% of industrial energy and generated about 90% of industrial wastes. The mission of AIM has, therefore, changed to ``Support development and commercialization of new or improved materials to improve productivity, product quality, and energy efficiency in the major process industries.`` Though AIM remains essentially a National Laboratory Program, it is essential that each project have industrial partners, including suppliers to, and customers of, the seven industries. Now, well into FY 1996, the transition is nearly complete and the AIM Program remains reasonably healthy and productive, thanks to the superb investigators and Laboratory Program Managers. This Annual Report for FY 1995 contains the technical details of some very remarkable work by the best materials scientists and engineers in the world. Areas covered here are: advanced metals and composites; advanced ceramics and composites; polymers and biobased materials; and new materials and processes.

  5. Application of Nanostructures in Electrochromic Materials and Devices: Recent Progress

    Directory of Open Access Journals (Sweden)

    Jin Min Wang

    2010-11-01

    Full Text Available The recent progress in application of nanostructures in electrochromic materials and devices is reviewed. ZnO nanowire array modified by viologen and WO3, crystalline WO3 nanoparticles and nanorods, mesoporous WO3 and TiO2, poly(3,4-ethylenedioxythiophene nanotubes, Prussian blue nanoinks and nanostructures in switchable mirrors are reviewed. The electrochromic properties were significantly enhanced by applying nanostructures, resulting in faster switching responses, higher stability and higher optical contrast. A perspective on the development trends in electrochromic materials and devices is also proposed.

  6. 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...

  7. 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.

  8. Fusion materials semiannual progress report for the period ending December 31, 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-04-01

    This is the twenty-first in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The report covers the following topics: vanadium alloys; silicon carbide composite materials; ferritic/martensitic steels; copper alloys and high heat flux materials; austenitic stainless steels; insulating ceramics and optical materials; solid breeding materials; radiation effects, mechanistic studies and experimental methods; dosimetry, damage parameters, and activation calculations; materials engineering and design requirements; and irradiation facilities, test matrices, and experimental methods.

  9. Fusion materials semiannual progress report for the period ending December 31, 1996

    International Nuclear Information System (INIS)

    1997-04-01

    This is the twenty-first in a series of semiannual technical progress reports on fusion materials. This report combines the full spectrum of research and development activities on both metallic and non-metallic materials with primary emphasis on the effects of the neutronic and chemical environment on the properties and performance of materials for in-vessel components. This effort forms one element of the materials program being conducted in support of the Fusion Energy Sciences Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. The report covers the following topics: vanadium alloys; silicon carbide composite materials; ferritic/martensitic steels; copper alloys and high heat flux materials; austenitic stainless steels; insulating ceramics and optical materials; solid breeding materials; radiation effects, mechanistic studies and experimental methods; dosimetry, damage parameters, and activation calculations; materials engineering and design requirements; and irradiation facilities, test matrices, and experimental methods

  10. Nuclear measurements and reference materials annual progress report, january - december 1988

    International Nuclear Information System (INIS)

    1989-01-01

    The 1988 progress report of the Central Bureau for Nuclear Measurements (CBNM) is presented. The major changes in the role and orientation of the Joint Research Center, of which CBNM is an institute, are included. The main tasks of CBNM, which involve the program on Nuclear Measurements and Reference Materials, are given. Technical activities concerning the GELINA electron beam and Van de Graaff accelerators are reported. The study of transition radiation at linear electron accelerators, and the development of isotope dilution mass spectrometry, for trace analysis and isotope abundance measurements in iron and gallium, are summarized. The scientific and technical support to the commission, work for third parties, and contribution to conferences are presented

  11. Progress of flame gunning materials; Yosha hoshuzai no shinpo

    Energy Technology Data Exchange (ETDEWEB)

    Murakami, Kakuichi [Harima Ceramic Corp., Hyogo (Japan)

    1999-04-01

    This report concerns to progress in the thermal spraying for repairing refractory, to say more precisely the flame-gunning materials. Gunning method using wet-slurry materials, in spite of its simplicity in execution, possesses a shortcoming of forming the porous deposit around spraying spot. Contrarily, the flame-gunning method is becoming popular in Japan because this method provides us with the minutely organized deposit having high tenacity and corrosion-resisting property. Flame is made from propane/oxygen mixture to assure the efficient melting of powdered clay. Magnesia/Dromite/slag system is preferable to converter furnace to produce a deposit layer less than 10% porosity. Materials based on alumina are preferable, although giving a relatively elevated porosity, to vacuum degassing vessel, converter furnace of stainless steel, hot stove for blast furnace, etc. Silca-rich system is characterized by the resistivity to recycled thermal procedure which brings about application to coke furnace. (NEDO)

  12. 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

  13. Defense Virtual Library: Technical Metadata for the Long-Term Management of Digital Materials: Preliminary Guidelines

    National Research Council Canada - National Science Library

    Flynn, Marcy

    2002-01-01

    ... of the digital materials being preserved. This report, prepared by Silver Image Management (SIM), proposes technical metadata elements appropriate for digital objects in the Defense Virtual Library...

  14. 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.

  15. Engineered Materials for Cesium and Strontium Storage Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Sean M. McDeavitt

    2010-04-14

    Closing the nuclear fuel cycle requires reprocessing spent fuel to recover the long-lived components that still have useful energy content while immobilizing the remnant waste fission products in stable forms. At the genesis of this project, next generation spent fuel reprocessing methods were being developed as part of the U.S. Department of Energy's Advanced Fuel Cycle Initiative. One of these processes was focused on solvent extraction schemes to isolate cesium (Cs) and strontium (Sr) from spent nuclear fuel. Isolating these isotopes for short-term decay storage eases the design requirements for long-term repository disposal; a significant amount of the radiation and decay heat in fission product waste comes from Cs-137 and Sr-90. For the purposes of this project, the Fission Product Extraction (FPEX) process is being considered to be the baseline extraction method. The objective of this project was to evaluate the nature and behavior of candidate materials for cesium and strontium immobilization; this will include assessments with minor additions of yttrium, barium, and rubidium in these materials. More specifically, the proposed research achieved the following objectives (as stated in the original proposal): (1) Synthesize simulated storage ceramics for Cs and Sr using an existing labscale steam reformer at Purdue University. The simulated storage materials will include aluminosilicates, zirconates and other stable ceramics with the potential for high Cs and Sr loading. (2) Characterize the immobilization performance, phase structure, thermal properties and stability of the simulated storage ceramics. The ceramic products will be stable oxide powders and will be characterized to quantify their leach resistance, phase structure, and thermophysical properties. The research progressed in two stages. First, a steam reforming process was used to generate candidate Cs/Sr storage materials for characterization. This portion of the research was carried out at

  16. Engineered Materials for Cesium and Strontium Storage. Final Technical Report

    International Nuclear Information System (INIS)

    McDeavitt, Sean M.

    2010-01-01

    Closing the nuclear fuel cycle requires reprocessing spent fuel to recover the long-lived components that still have useful energy content while immobilizing the remnant waste fission products in stable forms. At the genesis of this project, next generation spent fuel reprocessing methods were being developed as part of the U.S. Department of Energy's Advanced Fuel Cycle Initiative. One of these processes was focused on solvent extraction schemes to isolate cesium (Cs) and strontium (Sr) from spent nuclear fuel. Isolating these isotopes for short-term decay storage eases the design requirements for long-term repository disposal; a significant amount of the radiation and decay heat in fission product waste comes from Cs-137 and Sr-90. For the purposes of this project, the Fission Product Extraction (FPEX) process is being considered to be the baseline extraction method. The objective of this project was to evaluate the nature and behavior of candidate materials for cesium and strontium immobilization; this will include assessments with minor additions of yttrium, barium, and rubidium in these materials. More specifically, the proposed research achieved the following objectives (as stated in the original proposal): (1) Synthesize simulated storage ceramics for Cs and Sr using an existing labscale steam reformer at Purdue University. The simulated storage materials will include aluminosilicates, zirconates and other stable ceramics with the potential for high Cs and Sr loading. (2) Characterize the immobilization performance, phase structure, thermal properties and stability of the simulated storage ceramics. The ceramic products will be stable oxide powders and will be characterized to quantify their leach resistance, phase structure, and thermophysical properties. The research progressed in two stages. First, a steam reforming process was used to generate candidate Cs/Sr storage materials for characterization. This portion of the research was carried out at Purdue

  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. Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics. Working Material

    International Nuclear Information System (INIS)

    2013-01-01

    In recent years, engineering oriented work, rather than basic research and development (R&D), has led to significant progress in improving the economics of innovative fast reactors and associated fuel cycle facilities, while maintaining and even enhancing the safety features of these systems. Optimization of plant size and layout, more compact designs, reduction of the amount of plant materials and the building volumes, higher operating temperatures to attain higher generating efficiencies, improvement of load factor, extended core lifetimes, high fuel burnup, etc. are good examples of achievements to date that have improved the economics of fast neutron systems. The IAEA, through its Technical Working Group on Fast Reactors (TWG-FR) and Technical Working Group on Nuclear Fuel Cycle Options and Spent Fuel Management (TWG-NFCO), devotes many of its initiatives to encouraging technical cooperation and promoting common research and technology development projects among Member States with fast reactor and advanced fuel cycle development programmes, with the general aim of catalysing and accelerating technology advances in these fields. In particular the theme of fast reactor deployment, scenarios and economics has been largely debated during the recent IAEA International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios, held in Paris in March 2013. Several papers presented at this conference discussed the economics of fast reactors from different national and regional perspectives, including business cases, investment scenarios, funding mechanisms and design options that offer significant capital and energy production cost reductions. This Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics addresses Member States’ expressed need for information exchange in the field, with the aim of identifying the main open issues and launching possible initiatives to help and

  4. Composite Beam Theory with Material Nonlinearities and Progressive Damage

    Science.gov (United States)

    Jiang, Fang

    Beam has historically found its broad applications. Nowadays, many engineering constructions still rely on this type of structure which could be made of anisotropic and heterogeneous materials. These applications motivate the development of beam theory in which the impact of material nonlinearities and damage on the global constitutive behavior has been a focus in recent years. Reliable predictions of these nonlinear beam responses depend on not only the quality of the material description but also a comprehensively generalized multiscale methodology which fills the theoretical gaps between the scales in an efficient yet high-fidelity manner. The conventional beam modeling methodologies which are built upon ad hoc assumptions are in lack of such reliability in need. Therefore, the focus of this dissertation is to create a reliable yet efficient method and the corresponding tool for composite beam modeling. A nonlinear beam theory is developed based on the Mechanics of Structure Genome (MSG) using the variational asymptotic method (VAM). The three-dimensional (3D) nonlinear continuum problem is rigorously reduced to a one-dimensional (1D) beam model and a two-dimensional (2D) cross-sectional analysis featuring both geometric and material nonlinearities by exploiting the small geometric parameter which is an inherent geometric characteristic of the beam. The 2D nonlinear cross-sectional analysis utilizes the 3D material models to homogenize the beam cross-sectional constitutive responses considering the nonlinear elasticity and progressive damage. The results from such a homogenization are inputs as constitutive laws into the global nonlinear 1D beam analysis. The theoretical foundation is formulated without unnecessary kinematic assumptions. Curvilinear coordinates and vector calculus are utilized to build the 3D deformation gradient tensor, of which the components are formulated in terms of cross-sectional coordinates, generalized beam strains, unknown warping

  5. Fusion materials semiannual progress report for the period ending March 31, 1994

    International Nuclear Information System (INIS)

    1994-09-01

    This is the sixteenth in a series of semiannual technical progress reports on fusion reactor materials. This report combines research and development activities which were previously reported separately. These activities are concerned principally with the effects of the neutronic and chemical environment on the properties and performance of reactor materials; together they form one element of the overall materials programs being conducted in support of the Magnetic Fusion Energy Program of the US Department of Energy. The other major element of the program is concerned with the interactions between reactor materials and the plasma and is reported separately. This report is divided into the following areas: (1) irradiation facilities, test matrices, and experimental methods; (2) dosimetry, damage parameters, transmutation, and activation calculations; (3) materials engineering and design requirements; (4) fundamental mechanical behavior; (5) radiation effects, mechanistic studies, theory and modelings; (6) development of structural alloys; (7) solid breeding materials and beryllium; and (8) ceramics. Selected papers were indexed separately for inclusion in the Energy Science and Technology Database

  6. Strengthening the material-technical base of modern agrarian ...

    African Journals Online (AJOL)

    At present, in agriculture there is a tendency of equipment obsolescence and break ... by means of acquisition of high-energy, high-performance equipment and the ... and to make recommendations for the development of technical capacity.

  7. Recent progresses in materials for the direct methanol fuel cell

    Energy Technology Data Exchange (ETDEWEB)

    Lamy, C; Leger, J M [Centre National de la Recherche Scientifique (CNRS), 86 - Poitiers (France)

    1998-12-31

    Research programs are being conducted worldwide to develop a clean, zero emissions electric vehicle. However, even with the most advanced batteries, such as nickel/metal hydride, or lithium ion batteries, the driving range is limited and the recharging time is long. Only fuel cells which can convert chemical energy directly into electrical energy can compete with internal combustion engines. This paper reviewed the recent progress made in the development of a direct methanol fuel cell using the concept developed for the proton exchange membrane fuel cell (PEMFC). It was noted that the electrode materials, at the methanol anode and oxygen cathode need to be improved by using multifunctional electrocatalysts. The development of new temperature resistant proton exchange membranes with good ionic conductivity and low methanol cross-over, which resulted from the need to increase operating temperatures above 100 degrees C was also reviewed. 35 refs., 1 tab., 2 figs.

  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. 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.

  10. Control assembly materials for water reactors: Experience, performance and perspectives. Proceedings of a technical committee meeting

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-02-01

    The safe, reliable and economic operation of water cooled nuclear power reactors depends to a large extent upon the reliable operation of control assemblies for the regulation and shutdown of the reactors. These consist of neutron absorbing materials clad in stainless steel or zirconium based alloys, guide tubes and guide cards, and other structural components. Current designs have worked extremely well in normal conditions, but less than ideal behaviour limits the lifetimes of control materials, imposing an economic penalty which acts as a strong incentive to produce improved materials and designs that are more reliable. Neutron absorbing materials currently in use include the ceramic boron carbide, the high melting point metal hafnium and the low melting point complex alloy Ag-In-Cd. Other promising neutron absorbing materials, such as dysprosium titanate, are being evaluated in the Russian Federation. These control materials exhibit widely differing mechanical, physical and chemical properties, which must be understood in order to be able to predict the behaviour of control rod assemblies. Identification of existing failure mechanisms, end of life criteria and the implications of the gradual introduction of extended burnup, mixed oxide (MOX) fuels and more complex fuel cycles constitutes the first step in a search for improved materials and designs. In the early part of this decade, it was recognized by the International Working Group on Fuel Performance and Technology (IWGFPT) that international conferences, symposia and published reviews on the materials science aspects of control assemblies were few and far between. Consequently, the IWGFPT recommended that the IAEA should rectify this situation with a series of Technical Committee meetings (TCMs) devoted entirely to the materials aspects of reactor control assemblies. The first was held in 1993 and in the intervening five years considerable progress has been made. In bringing together experts in the

  11. Control assembly materials for water reactors: Experience, performance and perspectives. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    2000-02-01

    The safe, reliable and economic operation of water cooled nuclear power reactors depends to a large extent upon the reliable operation of control assemblies for the regulation and shutdown of the reactors. These consist of neutron absorbing materials clad in stainless steel or zirconium based alloys, guide tubes and guide cards, and other structural components. Current designs have worked extremely well in normal conditions, but less than ideal behaviour limits the lifetimes of control materials, imposing an economic penalty which acts as a strong incentive to produce improved materials and designs that are more reliable. Neutron absorbing materials currently in use include the ceramic boron carbide, the high melting point metal hafnium and the low melting point complex alloy Ag-In-Cd. Other promising neutron absorbing materials, such as dysprosium titanate, are being evaluated in the Russian Federation. These control materials exhibit widely differing mechanical, physical and chemical properties, which must be understood in order to be able to predict the behaviour of control rod assemblies. Identification of existing failure mechanisms, end of life criteria and the implications of the gradual introduction of extended burnup, mixed oxide (MOX) fuels and more complex fuel cycles constitutes the first step in a search for improved materials and designs. In the early part of this decade, it was recognized by the International Working Group on Fuel Performance and Technology (IWGFPT) that international conferences, symposia and published reviews on the materials science aspects of control assemblies were few and far between. Consequently, the IWGFPT recommended that the IAEA should rectify this situation with a series of Technical Committee meetings (TCMs) devoted entirely to the materials aspects of reactor control assemblies. The first was held in 1993 and in the intervening five years considerable progress has been made. In bringing together experts in the

  12. Technical records as material evidence in criminal proceedings

    Directory of Open Access Journals (Sweden)

    Fitim Shishani

    2017-03-01

    Full Text Available Nowadays, with the aid of technical records - recordings (audio, visual or combined audiovisual events and occurrences can be registered in the outside world in detail. The recording enables the creator or anyone who has it in disposal that at any moment of its reproduction, it can be found in detail how the recorded event has happened or how an occurrence seemed at the time of the recording. Among the current formats of technical records are included: photography, filming, magnetic, magnetoscope, and videophone recording etc. (Sahiti & Murati 2016, 295. The possibility provided by the rapid technical development is also of interest to criminal procedure because technical records containing any fact that may be proved in criminal proceedings may serve as a source of knowledge about facts. In other words, they may serve as evidence to establish facts in criminal proceedings. Given the extensive options that technical fact recordings provide, entities that use the aid of various devices from this fi eld, as well as the different purposes of the author of the recording which have led to the case of making the recording, there is a reasonable question of the permission on their use as evidence in criminal proceedings. In Kosovo, the situation is clear in terms of recordings made in the criminal procedure, as Kosovo CCP 1 provides the possibility of photographing, filming, sketching, etc., of the crime scene, audio visual recording etc. examination of persons (defendant, witness, expert or recordings of any action on judicial review.

  13. 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

  14. 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...

  15. 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...

  16. ARCHER Project: Progress on Material and component activities for the Advanced High Temperature Reactor

    International Nuclear Information System (INIS)

    Buckthorpe, D.E.

    2014-01-01

    The ARCHER (Advanced High-Temperature Reactors for Cogeneration of Heat and Electricity R&D) integrated project is a four year project which was started in 2011 as part of the European Commission 7th Framework Programme (FP7) to perform High Temperature Reactor technology R&D in support of reactor demonstration. The project consortium encompasses conventional and Nuclear Industry, Utilities, Technical Support Organizations, Research & Development Organizations and Academia. The activities involved contribute to the Generation IV (GIF) International Forum and collaborate with related projects in the US, China, Japan, and the Republic of Korea in cooperation with IAEA and ISTC. This paper addresses the progress of the work on ARCHER materials and component activities since the start of the project and underlines some of the main conclusions reached. (author)

  17. Material and component progress within ARCHER for advanced high temperature reactor

    International Nuclear Information System (INIS)

    Buckthorpe, D.E.; Davies, M.; Pra, F.; Bonnamy, P.; Fokkens, J.; Heijna, M.; Bout, N. de; Vreeling, A.; Bourlier, F.; Lhachemi, D.; Woayehune, A.; Dubiez-le-Goff, S.; Hahner, P.; Futterer, M.; Berka, J.; Kalivodora, J.; Pouchon, M.A.; Schmitt, R.; Homerin, P.; Marsden, B.; Mummery, P.; Mutch, G.; Ponca, D.; Buhl, P.; Hoffmann, M.; Rondet, F.; Pecherty, A.; Baurand, F.; Alenda, F.; Esch, M.; Kohlz, N.; Reed, J.; Fachinger, J.; Klower, Dr.

    2014-01-01

    The ARCHER (Advanced High-Temperature Reactors for Cogeneration of Heat and Electricity R and D) integrated project started in 2011 as part of the European Commission 7. Framework Programme (FP7) for a period of four years to perform High Temperature Reactor technology R and D in support of reactor demonstration. The project consortium encompasses conventional and Nuclear Industry, Utilities, Technical Support Organizations, Research and Development Organizations and Academia. The activities involved contribute to the Generation IV (GIF) International Forum and collaborate with related projects in the US, China, Japan, and the Republic of Korea in cooperation with IAEA and ISTC. This paper addresses the progress of the work on materials and component technologies within ARCHER over the first two years of the project. (authors)

  18. 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

  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. 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)

  1. Behavioural response of Phytoseiulus persimilisin inert materials for technical application.

    Science.gov (United States)

    Wendorf, Dennis; Sermann, Helga; Katz, Peter; Lerche, Sandra; Büttner, Carmen

    2009-01-01

    A large scale application of the predatory mite Phytoseiulus persimilis Athias-Henriot for use in the biological control of spider mites in the field requires testing the behaviour of Phytoseiulus persimilis in inert materials, like millet pelts and Vermiculite (1-3 mm). In laboratory studies, the distribution of the individuals in such materials, the time of remaining in the material were proved. To examine the abiotic influences on the time of remaining in the material, the dampness of the materials was varied (0%, 5% and 10%). Moreover, the influence of attitude of materials was tested. The time of emigration from the material was noted for each individual. Emigration from all dry materials was completed 15 minutes at the latest after set up of the mites. The increase of dampness had an obvious effect on the time of remaining in the material. In this respect the material millet pelts showed the most favourable effect with 10% dampness. Increasing attitude of material the mobility of predatory mites will be influenced negatively above 75 cm. Up to 50 cm, mites have not a problem to move in the material and the time of remaining can be prolonged considerably.

  2. Fluoride removal studies in water using natural materials : technical ...

    African Journals Online (AJOL)

    Excess fluoride in water causes health hazards to the natural environment. The removal of fluoride was attempted using natural materials such as red soil, charcoal, brick, fly-ash and serpentine. Each material was set up in a column for a known volume and the defluoridation capacities of these materials were studied with ...

  3. 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

  4. 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)

  5. 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

  6. 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

  7. 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

  8. Technical Meeting on Liquid Metal Reactor Concepts: Core Design and Structural Materials. Presentations

    International Nuclear Information System (INIS)

    2013-01-01

    The objective of the Technical Meeting is to present and discuss innovative liquid metal fast reactor (LMFR) core designs with special focus on the choice, development, testing and qualification of advanced reactor core structural materials

  9. Properties of selected superconductive materials, 1978 supplement. Technical note

    International Nuclear Information System (INIS)

    Roberts, B.W.

    1978-10-01

    This report includes data on additional superconductive materials extracted from the world literature up to fall 1977 and is an addendum to the data set published in J. Phys. Chem. Ref. Data 5, no. 3, 581-821 (1976) (Reprint no. 84). The data presented are new values and have not been selected or compared to values (except for selected values of the elements) previously assembled by the Superconductive Materials Data Center. The properties included are composition, critical temperature, critical magnetic field, crystal structure and the results of negative experiments. Special tabulations of high magnetic field materials with Type II behavior and materials with organic components are included. All entries are keyed to the literature. A list of recent reviews centered on superconductive materials is included

  10. Suitability of technical materials for machinery subsoilers for soil tillage

    Directory of Open Access Journals (Sweden)

    Radek Bednář

    2013-01-01

    Full Text Available Agricultural soil processing belongs to the basic elements in the process of crop production. Currently classic tillage method is decreasing and the only trend has stated as a shallow plowing. Suitable post harvest soil tillage greatly affects yields in the next cycle. The aim of the study is the analysis of abrasive wear of selected construction materials and their subsequent use for DXRV-HD cultivator. The performed tests are focused on monitoring the mechanical properties of the materials and their use for variable cutting tip of cultivator body. Tested materials are divided into four categories. These materials include tool steel (19436, carbon steel (12050, cast iron with globular graphite and welding material supplied as a functional complex on low carbon steel by the Abraweld company. These materials are tested together with the original part of share cultivator. The present experiment is focused on metallorgraphic, mechanical and abrasive analysis. Structural component of the material is identified by metallographic photos and then compared with the impact strength tested on Charpy hammer. Followed the abrasion resistance according to CSN 01 5084 and the total evaluation of the tested samples are done.

  11. Accounting systems for special nuclear material control. Technical report

    International Nuclear Information System (INIS)

    Korstad, P.A.

    1980-05-01

    Nuclear material accounting systems were examined and compared to financial double-entry accounting systems. Effective nuclear material accounting systems have been designed using the principles of double-entry financial accounting. The modified double-entry systems presently employed are acceptable if they provide adequate control over the recording and summarizing of transactions. Strong internal controls, based on principles of financial accounting, can help protect nuclear materials and produce accurate, reliable accounting data. An electronic data processing system can more accurately maintain large volumes of data and provide management with more current, reliable information

  12. Development of small-bore, high-current-density railgun as testbed for study of plasma-materials interaction. Progress report for October 16, 2000 - May 13, 2003

    International Nuclear Information System (INIS)

    Kyekyoon, Kim-Kevin

    2003-01-01

    The present document is a final technical report summarizing the progress made during 10/16/2000 - 05/13/2003 toward the development of a small-bore railgun with transaugmentation as a testbed for investigating plasma-materials interaction

  13. Energy Materials Coordinating Committee (EMaCC): Annual technical report, Fiscal year 1987

    International Nuclear Information System (INIS)

    1988-09-01

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further the effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. This annual technical report is mandated by the EMaCC terms of reference. This report summarizes EMaCC activities for FY 1987 and describes the materials research programs of various offices and divisions within the Department

  14. Technical committee meeting on material-coolant interactions and material movement and relocation in liquid metal fast reactors

    International Nuclear Information System (INIS)

    1994-01-01

    The Technical Committee Meeting on Material-Coolant Interactions and Material Movement and Relocation in Liquid Metal Fast Reactors was sponsored by the International Working Group on Fast Reactors (IWGFR), International Atomic Energy Agency (IAEA) and hosted by PNC, on behalf of the Japanese government. A broad range of technical subjects was discussed in the TCM, covering entire aspects of material motion and interactions relevant to the safety of LMFRs. Recent achievement and current status in research and development in this area were presented including European out-of-pile test of molten material movement and relocation; molten material-sodium interaction; molten fuel-coolant interaction; core disruptive accidents; sodium boiling; post accident material relocation, heat removal and relevant experiments already performed or planned

  15. Technical committee meeting on material-coolant interactions and material movement and relocation in liquid metal fast reactors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-07-01

    The Technical Committee Meeting on Material-Coolant Interactions and Material Movement and Relocation in Liquid Metal Fast Reactors was sponsored by the International Working Group on Fast Reactors (IWGFR), International Atomic Energy Agency (IAEA) and hosted by PNC, on behalf of the Japanese government. A broad range of technical subjects was discussed in the TCM, covering entire aspects of material motion and interactions relevant to the safety of LMFRs. Recent achievement and current status in research and development in this area were presented including European out-of-pile test of molten material movement and relocation; molten material-sodium interaction; molten fuel-coolant interaction; core disruptive accidents; sodium boiling; post accident material relocation, heat removal and relevant experiments already performed or planned.

  16. Supplemental Journal Article Materials: A progress report on an information industry initiative

    Science.gov (United States)

    Schwarzman, A. B.

    2011-12-01

    also intend to address roles and responsibilities of authors, editors, peer reviewers, publishers, libraries, abstracting and indexing services, and official data centers and institutional repositories. Finally, the document is going to contain broad principles and detailed technical implementation related to metadata, linking, packaging, and accessibility of supplemental materials. In this presentation, a co-chair of the NISO/NFAIS Working Group will report on the Group's latest progress in developing the Recommended Practices for Supplemental Journal Article Materials.

  17. 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)

  18. 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)

  19. ESTIMATION OF THE MODERN STATE OF PROVISION OF AGRICULTURAL ENTERPRISES IN MYKOLAIV REGION BY MATERIAL AND TECHNICAL RESOURCES

    Directory of Open Access Journals (Sweden)

    Natalya Potryvaieva

    2017-09-01

    , the search for prospective ways of its renewal is urgent. In particular, the authors proposed to intensify the formation of the secondary market of restored agricultural machinery based on the experience of foreign countries. Progressive improvement of material and technical resources is seen in the development of a network of local leasing funds and funds of preferential lending to agricultural commodity producers; expansion of cooperative forms of acquisition and exploitation of high-tech; the growth of dealer centres that provide rural commodity producers with equipment on leasing terms. In the conclusions, it is proved that the reduction of the number of the main types of equipment at agricultural enterprises in Mykolaiv region led to the fact that most of the technics are used longer the normative lifetime, on-load for each type of equipment is constantly increasing due to its scarcity. Improvement of the efficiency and growth of agricultural production and the level of its intensification needs updating of the material and technical base of agricultural enterprises, which requires significant investments. Taking into account the implementation of the region targeted programs, the role of public authorities is to develop measures aimed at a comprehensive solution to problems related not only to the implementation of technical, investment, and innovation policies but also to the coordinated co-operation between the industrial, commercial, and financial strategy.

  20. Energy Materials Coordinating Committee (EMaCC): Fiscal year 1996. Annual technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-08-01

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department`s materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. The EMaCC reports to the Director of the Office of Energy Research in his or her capacity as overseer of the technical programs of the Department. This annual technical report is mandated by the EMaCC terms of reference. This report summarizes EMaCC activities for FY 1996 and describes the materials research programs of various offices and divisions within the Department.

  1. Energy Materials Coordinating Committee (EMaCC): Fiscal year 1996. Annual technical report

    International Nuclear Information System (INIS)

    1997-08-01

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. The EMaCC reports to the Director of the Office of Energy Research in his or her capacity as overseer of the technical programs of the Department. This annual technical report is mandated by the EMaCC terms of reference. This report summarizes EMaCC activities for FY 1996 and describes the materials research programs of various offices and divisions within the Department

  2. HA and MAVL technical dialogue - Seminar - Transports of radioactive materials

    International Nuclear Information System (INIS)

    Charron, Sylvie; Eckert, Benoit; Lizot, Marie-Therese; Moutarde, Marianne; Mermaz, Frederic; Brisson, Nicolas; Sene, Monique; Demet, Michel; Jacquet, Benoit; Tran-Thien, Vivien; Ferran, Ghislain; Michel, Maurice; Barbey, Pierre; Miquel, Thierry-Paul; Monot, Bernard; Syren, Julien; Quintin, Christophe; Gilbert, Alain; Lhuillier, Daniel; Domeneghetti, Bertrand; LOURTIE, Guy; Manessier, Joffray

    2016-03-01

    This document gathers the content of a debate and Power Point presentations as contributions to this seminar on transports of nuclear materials. After an introduction, the different sessions addressed the actors of the transport of nuclear materials (regulation, parcel design, organisation on the shipper side and on the transporter side), transport safety and radiation protection (returns on experience by different actors and on event follow-up), the follow-up and safety of transports of nuclear materials (protection against malevolent acts, operational follow-up, case of rail transport), and issues related to crisis management (organisation in case of crisis, means of intervention implemented by the IRSN, return on experience for two accidents)

  3. 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.

  4. 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

  5. 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.

  6. Energy Materials Coordinating Committee (EMaCC). Annual technical report, Fiscal Year 2001

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2002-08-01

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations.

  7. Material Not Categorized As Waste (MNCAW) data report. Radioactive Waste Technical Support Program

    Energy Technology Data Exchange (ETDEWEB)

    Casey, C.; Heath, B.A.

    1992-11-01

    The Department of Energy (DOE), Headquarters, requested all DOE sites storing valuable materials to complete a questionnaire about each material that, if discarded, could be liable to regulation. The Radioactive Waste Technical Support Program entered completed questionnaires into a database and analyzed them for quantities and type of materials stored. This report discusses the data that TSP gathered. The report also discusses problems revealed by the questionnaires and future uses of the data. Appendices contain selected data about material reported.

  8. PSI condensed matter research and material sciences progress report 1990

    International Nuclear Information System (INIS)

    Gaeggeler, H.W.; Lorenzen, R.

    1991-01-01

    A brief overview is given of the research performed in 1990 at PSI's research department F3 in the fields of muon spectroscopy, neutron scattering, accelerator mass spectroscopy, applied and technical physics, geochemistry, trace elements, aerosol chemistry, heavy elements, defect physics, PIREX and spallation neutron source project. figs., tabs., refs

  9. Radioactive materials transport: a story of steady technical improvement

    International Nuclear Information System (INIS)

    Price, M.

    1991-01-01

    The transport of radioactive material is a fundamental part of the nuclear industry and equally vital to the use of radioisotopes in medical diagnosis and therapy. The safety record is impressively good and this aids open discussion of the subject. An independent consultant formerly with Atomic Energy Authority Technology reports on the Second International Conference on Transportation for the Nuclear Industry. (Author)

  10. Material Identification Technology (MIT) concept technical feasibility study

    International Nuclear Information System (INIS)

    Jones, J.L.; Harker, Y.D.; Yoon, W.Y.; Johnson, L.O.

    1993-09-01

    The Idaho National Engineering Laboratory (INEL) has initiated the design and development of a novel pulsed accelerator-based, active interrogation concept. The proposed concept, referred to as the Material Identification Technology (MIT), enables rapid (between accelerator pulses), non-destructive, elemental composition analysis of both nuclear and non-nuclear materials. Applications of this technique include material monitoring in support of counter-proliferation activities, such as export controls (at domestic and international inspection locations), SNM controls, nuclear weapon dismantlement, and chemical weapon verification. Material Identification Technology combines a pulsed, X-ray source (an electron accelerator) and a gamma detection system. The accelerator must maximize neutron production (pulse width, beam current, beam energy, and repetition rate) and minimize photon dose to the object. Current available accelerator technology can meet these requirements. The detection system must include detectors which provide adequate gamma energy resolution capability, rapid recovery after the initial X-ray interrogation pulse, and multiple single gamma event detection between accelerator pulses. Further research is required to develop the detection system. This report provides the initial feasibility assessment of the MIT concept

  11. MIXING OF INCOMPATIBLE MATERIALS IN WASTE TANKS TECHNICAL BASIS DOCUMENT

    International Nuclear Information System (INIS)

    SANDGREN, K.R.

    2006-01-01

    This document presents onsite radiological, onsite toxicological, and offsite toxicological consequences, risk binning, and control decision results for the mixing of incompatible materials in waste tanks representative accident. Revision 4 updates the analysis to consider bulk chemical additions to single shell tanks (SSTs)

  12. Research Progress of Building Materials Used in Construction Land

    Science.gov (United States)

    Niu, Yan

    2018-01-01

    Construction land preparation is an important aspect of land remediation project. The research of materials in the process of land improvement is the foundation and the core. Therefore, it is necessary to study the materials that may be involved in the process of building land preparation. In this paper, the research on the construction materials such as recycled concrete, geosynthetics, soil stabilizers, soil improvers, building insulation materials and inorganic fibrous insulation materials, which are commonly used in construction sites, is reviewed and discussed in this paper. Land remediation project involved in the construction of land materials to provide reference.

  13. Progress on research of materials science and biotechnology by ion beam application

    Energy Technology Data Exchange (ETDEWEB)

    Ishigaki, Isao [Japan Atomic Energy Research Inst., Takasaki, Gunma (Japan). Takasaki Radiation Chemistry Research Establishment

    1997-03-01

    Research of materials science and biotechnology by ion beam application in Takasaki Establishment was reviewed. Especially, the recent progresses of research on semiconductors in space, creation of new functional materials and topics in biotechnology were reported. (author)

  14. Advances in materials science, Metals and Ceramics Division. Triannual progress report, October 1979-January 1980

    Energy Technology Data Exchange (ETDEWEB)

    1980-03-31

    Progress is summarized concerning magnetic fusion energy materials, laser fusion energy, aluminium-air battery and vehicle, geothermal research, oil-shale research, nuclear waste management, office of basic energy sciences research, and materials research notes. (FS)

  15. 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.

  16. Special Purpose Materials annual progress report, October 1, 1979

    International Nuclear Information System (INIS)

    1980-04-01

    The scope of Special Purpose Materials covers fusion reactor materials problems other than the first-wall and blanket structural materials, which are under the purview of the ADIP, DAFS, and PMI task groups. Components that are considered as special purpose materials include breeding materials, coolants, neutron multipliers, barriers for tritium control, materials for compression and OH coils and waveguides, graphite and SiC, heat-sink materials, ceramics, and materials for high-field (> 10-T) superconducting magnets. It is recognized that there will be numerous materials problems that will arise during the design and construction of large magnetic-fusion energy devices such as the Engineering Test Facility (ETF) and Demonstration Reactor (DEMO). Most of these problems will be specific to a particular design or project and are the responsibility of the project, not the Materials and Radiation Effects Branch. Consequently, the Task Group on Special Purpose Materials has limited its concern to crucial and generic materials problems that must be resolved if magnetic-fusion devices are to succeed. Important areas specifically excluded include low-field (8-T) superconductors, fuels for hybrids, and materials for inertial-confinement devices. These areas may be added in the future when funding permits

  17. FY2008 Annual Progress Report for Propulsion Materials

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2009-01-01

    This program focuses on enabling and innovative materials technologies that are critical in improving the efficiency of advanced engines providing enabling materials support for combustion, hybrid, and power electronics development.

  18. FY2010 Annual Progress Report for Propulsion Materials

    Energy Technology Data Exchange (ETDEWEB)

    Davis, Patrick B. [Office of Energy Efficiency and Renewable Energy (EERE), Washington, DC (United States); Schutte, Carol L. [Office of Energy Efficiency and Renewable Energy (EERE), Washington, DC (United States); Gibbs, Jerry L. [Office of Energy Efficiency and Renewable Energy (EERE), Washington, DC (United States)

    2011-01-01

    The Propulsion Materials Technology actively supports the energy security and reduction of greenhouse emissions goals of the Vehicle Technologies Program by developing advanced materials that enable development of higher efficiency powertrains for ground transportation. Propulsion Materials works closely with the other disciplines within the VT Program to identify the materials properties essential for the development of cost-effective, highly efficient, and environmentally friendly next-generation heavy and light duty powertrains.

  19. Technically enhanced naturally occurring radioactive materials; identification, characterization and treatment

    International Nuclear Information System (INIS)

    Aly, H.F.

    2001-01-01

    Radioactive materials (TENORM) is produced in a relatively large amount with relatively small radioactivity, however in many instances the radioactivity levels exceeds that permissible. In this presentation, the different industries where enhanced levels of natural radioactivity is identified and characterized will be given. The different approaches for treatment of this enhanced radioactivity will be addressed. Finally, our research and development activities in characterization and treatment of TENORM produced from the oil fields in Egypt will be presented. (authors)

  20. Technical meeting on materials for in-vessel components of ITER

    International Nuclear Information System (INIS)

    Kalinin, G.; Barabash, V.

    2000-01-01

    The Technical meeting on materials for in-vessel components of ITER was held at the ITER Joint Work Site in Garching from 31 January to 4 February. The main objectives of the meetings were: 1. to summarize the requirements, 2. to review new data, 3. to discuss in detail the R and D program and to discuss the material assessment report

  1. 78 FR 65265 - Materials Technical Advisory Committee; Notice of Open Meeting

    Science.gov (United States)

    2013-10-31

    .... Report on regime-based activities. 7. SHUTDOWN Feedback. 8. Public Comments and New Business. The open...; Notice of Open Meeting The Materials Technical Advisory Committee will meet on November 14, 2013, 10:00 a... materials and related technology. Agenda Open Session 1. Opening Remarks and Introductions. 2. Remarks from...

  2. 77 FR 23117 - Rigging Equipment for Material Handling Construction Standard; Correction and Technical Amendment

    Science.gov (United States)

    2012-04-18

    ... Equipment for Material Handling Construction Standard; Correction and Technical Amendment AGENCY... AND HEALTH REGULATIONS FOR CONSTRUCTION Subpart H--Materials Handling, Storage, Use, and Disposal 0 1... amendment. SUMMARY: OSHA is correcting its sling standard for construction titled ``Rigging Equipment for...

  3. Research status on radiation damage in nuclear materials and recommendations for IAEA activities. Technical report

    International Nuclear Information System (INIS)

    Caro, Alfredo; Caro, Magdalena

    2002-03-01

    This report addresses the synergy between the continuous progress of parallel computing and the spectacular advances in the theoretical framework that describes materials. Together, they contributed to significantly advance our comprehension of materials properties like mechanical behavior. It also highlights its impact on nuclear technology, as it provides physical insight into the complex processes responsible for the degradation of structural materials under neutron irradiation

  4. Workshop on technical assessment of industrial thermal insulation materials: summary

    International Nuclear Information System (INIS)

    Peterson, S.

    1976-07-01

    Over 80 participants representing 50 organizations met to discuss the report, Industrial Thermal Insulation--An Assessment, ORNL/TM-5283. Presentations on the performance of available materials, economic considerations, and measurement problems were followed by discussion. A final wrap-up session concluded that the report was valuable in pointing the direction for needed effort in the area, confirmed the indicated actions needed to further industrial application of insulation, and called for future meetings to continue the dialogue between the various facets of the industry

  5. Recent Progress in Some Amorphous Materials for Supercapacitors.

    Science.gov (United States)

    Li, Qing; Xu, Yuxia; Zheng, Shasha; Guo, Xiaotian; Xue, Huaiguo; Pang, Huan

    2018-05-14

    A breakthrough in technologies having "green" and sustainable energy storage conversion is urgent, and supercapacitors play a crucial role in this area of research. Owing to their unique porous structure, amorphous materials are considered one of the best active materials for high-performance supercapacitors due to their high specific capacity, excellent cycling stability, and fast charging rate. This Review summarizes the synthesis of amorphous materials (transition metal oxides, carbon-based materials, transition metal sulfides, phosphates, hydroxides, and their complexes) to highlight their electrochemical performance in supercapacitors. © 2018 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  6. Advanced Industrial Materials Program. Annual progress report, FY 1993

    Energy Technology Data Exchange (ETDEWEB)

    Stooksbury, F. [comp.

    1994-06-01

    Mission of the AIM program is to commercialize new/improved materials and materials processing methods that will improve energy efficiency, productivity, and competitiveness. Program investigators in the DOE national laboratories are working with about 100 companies, including 15 partners in CRDAs. Work is being done on intermetallic alloys, ceramic composites, metal composites, polymers, engineered porous materials, and surface modification. The program supports other efforts in the Office of Industrial Technologies to assist the energy-consuming process industries. The aim of the AIM program is to bring materials from basic research to industrial application to strengthen the competitive position of US industry and save energy.

  7. Reducing nuclear danger through intergovernmental technical exchanges on nuclear materials safety management

    International Nuclear Information System (INIS)

    Jardine, L.J.; Peddicord, K.L.; Witmer, F.E.; Krumpe, P.F.; Lazarev, L.; Moshkov, M.

    1997-01-01

    The United States and Russia are dismantling nuclear weapons and generating hundreds of tons of excess plutonium and high enriched uranium fissile nuclear materials that require disposition. The U.S. Department of Energy and Russian Minatom organizations.are planning and implementing safe, secure storage and disposition operations for these materials in numerous facilities. This provides a new opportunity for technical exchanges between Russian and Western scientists that can establish an improved and sustained common safety culture for handling these materials. An initiative that develops and uses personal relationships and joint projects among Russian and Western participants involved in fissile nuclear materials safety management contributes to improving nuclear materials nonproliferation and to making a safer world. Technical exchanges and workshops are being used to systematically identify opportunities in the nuclear fissile materials facilities to improve and ensure the safety of workers, the public, and the environment

  8. Recent progress of atomic layer deposition on polymeric materials

    Energy Technology Data Exchange (ETDEWEB)

    Guo, Hong Chen; Ye, Enyi [Institute of Materials Research and Engineering, A*STAR (Agency for Science, Technology and Research), 2 Fusionopolis Way, Innovis, #08-03, Singapore 138634 (Singapore); Li, Zibiao, E-mail: lizb@imre.a-star.edu.sg [Institute of Materials Research and Engineering, A*STAR (Agency for Science, Technology and Research), 2 Fusionopolis Way, Innovis, #08-03, Singapore 138634 (Singapore); Han, Ming-Yong [Institute of Materials Research and Engineering, A*STAR (Agency for Science, Technology and Research), 2 Fusionopolis Way, Innovis, #08-03, Singapore 138634 (Singapore); Loh, Xian Jun, E-mail: lohxj@imre.a-star.edu.sg [Institute of Materials Research and Engineering, A*STAR (Agency for Science, Technology and Research), 2 Fusionopolis Way, Innovis, #08-03, Singapore 138634 (Singapore); Department of Materials Science and Engineering, National University of Singapore, Singapore 117574 (Singapore); Singapore Eye Research Institute, 20 College Road, Singapore 169856 (Singapore)

    2017-01-01

    As a very promising surface coating technology, atomic layer deposition (ALD) can be used to modify the surfaces of polymeric materials for improving their functions and expanding their application areas. Polymeric materials vary in surface functional groups (number and type), surface morphology and internal structure, and thus ALD deposition conditions that typically work on a normal solid surface, usually do not work on a polymeric material surface. To date, a large variety of research has been carried out to investigate ALD deposition on various polymeric materials. This paper aims to provide an in-depth review of ALD deposition on polymeric materials and its applications. Through this review, we will provide a better understanding of surface chemistry and reaction mechanism for controlled surface modification of polymeric materials by ALD. The integrated knowledge can aid in devising an improved way in the reaction between reactant precursors and polymer functional groups/polymer backbones, which will in turn open new opportunities in processing ALD materials for better inorganic/organic film integration and potential applications. - Highlights: • ALD deposition on different natural and synthetic polymer materials • Reaction mechanism based on the surface functional groups of polymers • Application of ALD-modified polymers in different fields.

  9. FY2014 Lightweight Materials R&D Annual Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    None

    2015-03-01

    The Lightweight Materials research and development (R&D) area within the DOE Vehicle Technologies Office (VTO) provides support and guidance for many cutting-edge automotive technologies under development. Research focuses on addressing critical barriers to commercializing lightweight materials for passenger and commercial vehicles.

  10. FY2013 Lightweight Materials R&D Annual Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2014-02-01

    As part of the U.S. Department of Energy’s (DOE’s) Vehicle Technologies Program (VTO), the Lightweight Materials (LM) activity focuses on the development and validation of advanced materials and manufacturing technologies to significantly reduce light and heavy duty vehicle weight without compromising other attributes such as safety, performance, recyclability, and cost.

  11. FY2010 Annual Progress Report for Lightweighting Materials

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2011-01-15

    The Lightweight Materials activity (LM) within the Vehicle Technologies Program focuses on the development and validation of advanced materials and manufacturing technologies to significantly reduce light and heavy duty vehicle weight without compromising other attributes such as safety, performance, recyclability, and cost.

  12. 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.

  13. 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.

  14. Special purpose materials. Annual progress report, October 1, 1979

    International Nuclear Information System (INIS)

    1980-04-01

    Fusion reactor materials problems other than the first-wall and blanket structural materials are investigated. Components that are considered as special purpose materials include breeding materials, coolants, neutron multipliers, barriers for tritium control, materials for compression and OH coils and waveguides, grahite and SiC, heat-sink materials, ceramics, and materials for high-field (>10-T) superconducting magnets. Radiation-induced conductivity of three forms of Al 2 O 3 was measured as a function of ionizing dose rate and temperature. Increases observed are large enough to affect performance of insulators under some fusion reactor operating conditions. Single-crystal MgAl 2 O 4 was shown to exhibit zero swelling when irradiated to approx. 2 x 10 26 n/m 2 at 925 and 1100 K. This ceramic is resistant to nucleation and growth of defect aggregates, and is not characterized by those microstructural conditions which lead to void formation and swelling in Al 2 O 3 . Fracture toughness of single-crystal Al 2 O 3 was significantly increased by elevated-temperature irradiation to approx. 2 x 10 26 n/m 2 , while that for MgAl 2 O 4 and Y 3 Al 5 O 12 showed little or no change. These results show that ceramics can retain their original resistance to crack propagation after high-dose neutron irradiation

  15. Advanced Industrial Materials (AIM) Program. Annual progress report, FY 1994

    Energy Technology Data Exchange (ETDEWEB)

    Sorrell, C.A.

    1995-05-01

    The Advanced Industrial Materials Program is a part of the Office of Industrial Technologies (OIT), Energy Efficiency and Renewable Energy in the Department of Energy. The mission of the AIM Program is to conduct applied research, development, and applications engineering work, in partnership with industry, to commercialize new or improved materials and materials processing methods that will improve energy efficiency, productivity, and competitiveness. AIM is responsible for identifying, supporting, and coordinating multidisciplinary projects to solve identified industrial needs and transferring the technology to the industrial sector. Program investigators in the DOE National Laboratories are working closely with approximately 100 companies, including 15 partners in Cooperative Research and Development Agreements. Work is being done in a wide variety of materials technologies, including intermetallic alloys, ceramic composites, metal composites, polymers, engineered porous materials, and surface modification. The Program supports other efforts in the Office of Industrial Technologies to assist the energy consuming process industries, including forest products, glass, steel, aluminum, foundries, chemicals, and refineries. To support OITs {open_quotes}Industries of the Future{close_quotes} initiatives and to improve the relevance of materials research, assessments of materials needs and opportunities in the process industries are being made. These assessments are being used for program planning and priority setting; support of work to satisfy those needs is being provided. Many new materials that have come into the marketplace in recent years, or that will be available for commercial use within a few more years, offer substantial benefits to society. This document contains 28 reports on advanced materials research. Individual reports have been processed separately for entry onto the Department of Energy databases.

  16. Science of materials. Progress report, January 1-December 31, 1979

    International Nuclear Information System (INIS)

    1979-01-01

    The research program includes studies of the microchemistry, microstructure, deformation, corrosion and fracture of metals, ceramics and alloy materials, of the hydrogen embrittlement of metals, the mechanism of heat transfer across interfacts, catalytic properties of surfaces, and erosion of surfaces by fluid suspended particles. The structure of liquids, polymers and disordered solids is under investigation with emphasis on molecular interactions and bonding, on ionic conduction, phase transitions and radiation damage. Ferro- and pyro-electric materials with potential for solar energy applications are under development. The study of optical properties includes the mechanism of luminescence, the design of molecular photoreceptors, and new semiconductor materials for photovoltaic devices

  17. Chemistry and Materials Science progress report, first half FY 1992

    International Nuclear Information System (INIS)

    1992-07-01

    This report contains sections on: Fundamentals of the physics and processing of metals; interfaces, adhesion, and bonding; energetic materials; plutonium research; synchrotron radiation-based materials science; atomistic approach to the interaction of surfaces with the environment: actinide studies; properties of carbon fibers; buried layer formation using ion implantation; active coherent control of chemical reaction dynamics; inorganic and organic aerogels; synthesis and characterization of melamine-formaldehyde aerogels; structural transformation and precursor phenomena in advanced materials; magnetic ultrathin films, surfaces, and overlayers; ductile-phase toughening of refractory-metal intermetallics; particle-solid interactions; electronic structure evolution of metal clusters; and nanoscale lithography induced chemically or physically by modified scanned probe microscopy

  18. Science of materials. Progress report, January 1-December 31, 1979

    Energy Technology Data Exchange (ETDEWEB)

    1979-01-01

    The research program includes studies of the microchemistry, microstructure, deformation, corrosion and fracture of metals, ceramics and alloy materials, of the hydrogen embrittlement of metals, the mechanism of heat transfer across interfacts, catalytic properties of surfaces, and erosion of surfaces by fluid suspended particles. The structure of liquids, polymers and disordered solids is under investigation with emphasis on molecular interactions and bonding, on ionic conduction, phase transitions and radiation damage. Ferro- and pyro-electric materials with potential for solar energy applications are under development. The study of optical properties includes the mechanism of luminescence, the design of molecular photoreceptors, and new semiconductor materials for photovoltaic devices.

  19. Energy Materials Coordinating Committee (EMaCC) Fiscal Year 1999 annual technical report

    Energy Technology Data Exchange (ETDEWEB)

    None

    2000-10-31

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department`s materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. This report summarizes EMaCC activities for FY 1999 and describes the materials research programs of various offices and divisions within the Department.

  20. 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

  1. Review of progress on fusion materials technology, Harwell, December 1980

    International Nuclear Information System (INIS)

    Harries, D.R.

    1981-03-01

    The programme has been aimed specifically at investigating and furthering an understanding of: (a) the evolution of the radiation damage structure, void and gas bubble swelling and surface blistering effects in both model and potential first wall materials for a D-T fusion reactor system of the TOKAMAK type. (b) Radiation effects in inorganic insulator materials. In addition, investigations were carried out into the effects of irradiation on organic insulators and on the performance of rubber seals. The principal achievements to date are summarised and a list of 50 references is given. (author)

  2. Recent Progress on PEDOT-Based Thermoelectric Materials.

    Science.gov (United States)

    Wei, Qingshuo; Mukaida, Masakazu; Kirihara, Kazuhiro; Naitoh, Yasuhisa; Ishida, Takao

    2015-02-16

    The thermoelectric properties of poly(3,4-ethylenedioxythiophene) (PEDOT)-based materials have attracted attention recently because of their remarkable electrical conductivity, power factor, and figure of merit. In this review, we summarize recent efforts toward improving the thermoelectric properties of PEDOT-based materials. We also discuss thermoelectric measurement techniques and several unsolved problems with the PEDOT system such as the effect of water absorption from the air and the anisotropic thermoelectric properties. In the last part, we describe our work on improving the power output of thermoelectric modules by using PEDOT, and we outline the potential applications of polymer thermoelectric generators.

  3. 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

  4. Advanced Industrial Materials (AIM) Program annual progress report, FY 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-05-01

    The Advanced Industrial Materials (AIM) Program is a part of the Office of Industrial Technologies (OIT), Energy Efficiency and Renewable Energy, US Department of Energy (DOE). The mission of AIM is to support development and commercialization of new or improved materials to improve energy efficiency, productivity, product quality, and reduced waste in the major process industries. OIT has embarked on a fundamentally new way of working with industries--the Industries of the Future (IOF) strategy--concentrating on the major process industries that consume about 90% of the energy and generate about 90% of the waste in the industrial sector. These are the aluminum, chemical, forest products, glass, metalcasting, and steel industries. OIT has encouraged and assisted these industries in developing visions of what they will be like 20 or 30 years into the future, defining the drivers, technology needs, and barriers to realization of their visions. These visions provide a framework for development of technology roadmaps and implementation plans, some of which have been completed. The AIM Program supports IOF by conducting research and development on materials to solve problems identified in the roadmaps. This is done by National Laboratory/industry/university teams with the facilities and expertise needed to develop new and improved materials. Each project in the AIM Program has active industrial participation and support.

  5. Chemistry and Materials Science. Progress report, first half, FY 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-07-01

    Thrust areas of the weapons-supporting research are growth, structure, and reactivity of surfaces and thin films; uranium research; physics and processing of metals; energetic materials; etc. The laboratory-directed R and D include director`s initiatives and individual projects, and transactinium institute studies.

  6. Skull repair materials applied in cranioplasty: History and progress

    Institute of Scientific and Technical Information of China (English)

    Qingsheng Yu; Lin Chen; Zhiye Qiu; Yuqi Zhang; Tianxi Song; Fuzhai Cui

    2017-01-01

    The skull provides protection and mechanical support, and acts as a container for the brain and its accessory organs. Some defects in the skull can fatally threaten human life. Many efforts have been taken to repair defects in the skull, among which cranioplasty is the most prominent technique. To repair the injury, numerous natural and artificial materials have been adopted by neurosurgeons. Many cranioprostheses have been tried in the past decades, from autoplast to bioceramics. Neurosurgeons have been evaluating their advantages andshortages through clinical practice. Among those prostheses, surgeons gradually prefer bionic ones due to their marvelous osteoconductivity, osteoinductivity, biocompatibility,and biodegradability. Autogeneic bone has been widely recognized as the"gold standard" for renovating large-sized bone defects. However, the access to this technique is restricted by limited availability and complications associated with its use. Many metal and polymeric materials with mechanical characteristics analogous to natural bones were consequently applied to cranioplasty. But most of them were unsatisfactory concerning osteoconductiion and biodegradability owe to their intrinsic properties. With the microstructures almost identical to natural bones, mineralized collagen hasbiological performance nearly identical to autogeneic bone, such as osteoconduction. Implants made of mineralized collagen can integrate themselves into the newly formed bones through a process called"creeping substitution". In this review, the authors retrospect the evolution of skull repair material applied in cranioplasty. The ultimate skull repair material should have microstructure and bioactive qualities that enable osteogenesis induction and intramembranous ossification.

  7. Progress in the activities on prevention and combating of illicit trafficking of nuclear material in Lithuania

    International Nuclear Information System (INIS)

    Kurselis, S.; Stadalnikas, A.

    2001-01-01

    Full text: The paper gives a general overview of the progress which has been made in the activities on prevention and combating of illicit trafficking of nuclear material in Lithuania. It describes the measures which were taken to strengthen nuclear material accounting and control and physical protection. The current status of the national legislation and the functions of institutions involved in control of nuclear material and combating of illicit trafficking are discussed. Lithuania, similar to many countries, did not avoid a new type of a crime - smuggling of nuclear materials - which was observed in the 1990's. The most serious case in Lithuania happened in 1993 when fresh fuel assembly was stolen from Ignalina NPP. This assembly contains approximately 124 kg of UO 2 (enrichment 2%). 100 kg of the pellets from this assembly was found later in several pieces at different places. This case served as a strong stimulus to strengthen prevention measures of Illicit trafficking. The legal basis was created and governmental institutions were obliged with special duties related with nuclear material. The laws and regulations set the order for the shipment and handling of nuclear material. The penalties for violation of these laws and regulations specified in Penal Code and Administrative Code were made stricter. The State system of accounting for and control of nuclear material (SSAC) is a very important element in prevention of the illicit trafficking. The Regulations of Accounting for and Control of Nuclear Material at Nuclear Facilities and LOFs was issued by the State Nuclear Power Safety Inspectorate (VATESI) on 10 December 1997 following the provisions of the Law on Nuclear Energy. Lithuania extended its international obligations by ratifying the Protocol Additional to the Safeguards Agreement (entered into force on 5 July 2000). The fully computerized nuclear material accountancy system was created at Ignalina NPP. The system gives the possibility to find the

  8. 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.

  9. 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

  10. Fourth Collaborative Materials Exercise of the Nuclear Forensics International Technical Working Group

    International Nuclear Information System (INIS)

    Schwantes, J.M.; Reilly, D.; Marsden, O.

    2018-01-01

    The Nuclear Forensics International Technical Working Group is a community of nuclear forensic practitioners who respond to incidents involving nuclear and other radioactive material out of regulatory control. The Group is dedicated to advancing nuclear forensic science in part through periodic participation in materials exercises. The Group completed its fourth Collaborative Materials Exercise in 2015 in which laboratories from 15 countries and one multinational organization analyzed three samples of special nuclear material in support of a mock nuclear forensic investigation. This special section of the Journal for Radioanalytical and Nuclear Chemistry is devoted to summarizing highlights from this exercise. (author)

  11. Waste management issues and their potential impact on technical specifications of CANDU fuel materials

    Energy Technology Data Exchange (ETDEWEB)

    Tait, J.C.; Johnson, L.H. [Atomic Energy of Canada Limited, Pinawa, Manitoba (Canada)

    1997-07-01

    The technical specifications for the composition of nuclear fuels and materials used in Canada's CANDU reactors have been developed by AECL and materials manufacturers, taking into account considerations specific to their manufacture and the effect of minor impurities on fuel behaviour in reactor. Nitrogen and chlorine are examples of UO{sub 2} impurities, however, where there is no technical specification limit. These impurities are present in the source materials or introduced in the fabrication process and are neutron activated to {sup 14}C and {sup 36}C1, which after {sup 129}I , are the two most significant contributors to dose in safety assessments for the disposal of used fuel. For certain impurities, environmental factors, particularly the safety of the disposal of used fuels, should be taken into consideration when deriving 'allowable' impurity limits for nuclear fuel materials. (author)

  12. Waste management issues and their potential impact on technical specifications of CANDU fuel materials

    International Nuclear Information System (INIS)

    Tait, J.C.; Johnson, L.H.

    1997-01-01

    The technical specifications for the composition of nuclear fuels and materials used in Canada's CANDU reactors have been developed by AECL and materials manufacturers, taking into account considerations specific to their manufacture and the effect of minor impurities on fuel behaviour in reactor. Nitrogen and chlorine are examples of UO 2 impurities, however, where there is no technical specification limit. These impurities are present in the source materials or introduced in the fabrication process and are neutron activated to 14 C and 36 C1, which after 129 I , are the two most significant contributors to dose in safety assessments for the disposal of used fuel. For certain impurities, environmental factors, particularly the safety of the disposal of used fuels, should be taken into consideration when deriving 'allowable' impurity limits for nuclear fuel materials. (author)

  13. Recent progress in supercapacitors: from materials design to system construction.

    Science.gov (United States)

    Wang, Yonggang; Xia, Yongyao

    2013-10-04

    Supercapacitors are currently attracting intensive attention because they can provide energy density by orders of magnitude higher than dielectric capacitors, greater power density, and longer cycling ability than batteries. The main challenge for supercapacitors is to develop them with high energy density that is close to that of a current rechargeable battery, while maintaining their inherent characteristics of high power and long cycling life. Consequently, much research has been devoted to enhance the performance of supercapacitors by either maximizing the specific capacitance and/or increasing the cell voltage. The latest advances in the exploration and development of new supercapacitor systems and related electrode materials are highlighted. Also, the prospects and challenges in practical application are analyzed, aiming to give deep insights into the material science and electrochemical fields. Copyright © 2013 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  14. Materials Science Division progress report 1986-1988

    International Nuclear Information System (INIS)

    Kumar, Vijay; Vasumathi, D.; Chandra Sekhar, N.V.

    1990-01-01

    This is a report on the various Research and Developmental (R and D) activities carried out in the Materials Science Division during the period 1986-88. Most contributions have been presented in the form of abstracts and wherever possible results of several contributions on a related problem have been consolidated into one. The R and D activities covered the following areas: (1) quasicrystalline phase, (2) high temperature superconducting behaviour in metal oxides, (3) physics of colloidal suspensions, (4) behaviour of materials under high pressure, (5) radiation effects in complex alloy systems, (6) inert gas behaviour in metals, and production of crystals, particularly of volatile semiconducting compounds. The lists of publications by the members of the Division and seminars held during 1986-88 are given at the end of the report. (a uthor)

  15. Advanced Industrial Materials (AIM) program. Annual progress report. FY 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-04-01

    The Advanced Industrial Materials (AIM) Program underwent a major transformation in Fiscal Year 1995 and these changes have continued to the present. When the Program was established in 1990 as the Advanced Industrial Concepts (AIC) Materials Program, the mission was to conduct applied research and development to bring materials and processing technologies from the knowledge derived from basic research to the maturity required for the end use sectors for commercialization. In 1995, the Office of Industrial Technologies (OIT) made radical changes in structure and procedures. All technology development was directed toward the seven `Vision Industries` that use about 80% of industrial energy and generated about 90% of industrial wastes. These are: aluminium; chemical; forest products; glass; metal casting; refineries; and steel. OIT is working with these industries, through appropriate organizations, to develop Visions of the desired condition of each industry some 20 or 25 years in the future and then to prepare Road Maps and Implementation Plans to enable them to reach their goals. The mission of AIM has, therefore, changed to `Support development and commercialization of new or improved materials to improve productivity, product quality, and energy efficiency in the major process industries.` Though AIM remains essentially a National Laboratory Program, it is necessary that each project have industrial partners, including suppliers to, and customers of, the seven industries. Now, well into FY 1996, the transition is nearly complete and the AIM Program remains healthy and productive, thanks to the superb investigators and Laboratory Program Managers. Separate abstracts have been indexed into the energy database for articles from this report.

  16. Entomology Specialist 1-1. Military Curriculum Materials for Vocational and Technical Education.

    Science.gov (United States)

    Jones, Jimmie L.

    This individualized, self-paced course for training an entomology specialist was adapted from military curriculum materials for use in vocational and technical education. Completion of the course should provide students with basic information needed to accomplish the following duties of an entomology specialist: perform entomological work, apply…

  17. Medical Laboratory Technician--Microbiology, 10-3. Military Curriculum Materials for Vocational and Technical Education.

    Science.gov (United States)

    Ohio State Univ., Columbus. National Center for Research in Vocational Education.

    This course, the second of three courses in the medical laboratory technician field adapted from military curriculum materials for use in vocational and technical education, was designed as a refresher course for student self-study and evaluation. It is suitable for use by advanced students or beginning students participating in a supervised…

  18. Annual Technical Report, Materials Research Laboratory, 1 July 1982 - 30 June 1983.

    Science.gov (United States)

    1983-06-30

    Technical Report 41 SECTION 6 PROPERTIES OF MATERIALS AT LOW TEMPERATURES Introduction The general motivation for this work is that certain interesting...Professor, Chemis- "Photoelectronic Properties of Cu 3 PS4 and try. Cu 3 PS Se Single Crystals," J. V. Marzik, A. K. Hsieh, K. Dwight and A. Wold. J

  19. Energy materials coordinating committee (EMACC) Fiscal Year 1982. Annual technical report

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    1983-03-01

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further the effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/ workshops on selected topics involving both DOE and major contractors. In addition, the EMaCC aids in obtaining materials - related inputs for both intra- and interagency compilations. Membership in the EMaCC is open to any Department organizational unit; participants are appointed by Division or Office Directors. The current membership is listed in Table 1. The EMACC reports to the Director of the Office of Energy Research in his capacity as overseer of the technical programs of the Department. This annual technical report is mandated by the EMACC terms of reference. In this report are described 1) EMACC activities for FY 1982; 2) a summary of materials funding in the Department from FY 1978 to the present; and 3) on-going materials programs in the Department.

  20. Progress Report of the Materials Department. First Quarter 1971. RCN Report

    International Nuclear Information System (INIS)

    Sens, P.F.

    1971-06-01

    A description of the progress in the various projects concerning the materials development of water cooled reactors, sodium cooled fast reactors and gas cooled reactors. Similar reports have been issued regularly with an internal distribution only. (author)

  1. Research and Application Progress of Silicone Rubber Materials in Aviation

    Directory of Open Access Journals (Sweden)

    HUANG Yanhua

    2016-06-01

    Full Text Available The research progress of heat resistance, cold resistance, electrical conductivity and damping properties of aviation silicone rubber were reviewed in this article. The heat resistance properties of silicone rubber can be enhanced by changing the molecular structure (main chain, end-group, side chain and molecular weight of the gum and adding special heat-resistance filler. The cold resistance of aviation silicone rubber can be enhanced by adjusting the side chain molecular structure of the gum and the content of different gum chain. The electrical conductivity of silicone rubber can be improved by optimizing, blending and dispersing of conductive particles. The damping property of silicone rubber can be improved by designing and synthesizing of high-molecular polysiloxane damping agent. Furthermore, the application of aviation silicone rubber used in high-low temperature seal, electrical conduction and vibration damping technology are also summarized, and the high performance (for example long-term high temperature resistance, ultralow temperature resistance, high electromagnetic shelding, long-term fatigue resistance vibration damping, quasi constant modulus and so on of special silicone rubber is the future direction of aviation silicone rubber.

  2. 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.)

  3. Materials selection as an interdisciplinary technical activity: basic methodology and case studies

    Directory of Open Access Journals (Sweden)

    M. Ferrante

    2000-04-01

    Full Text Available The technical activity known as Materials Selection is reviewed in its concepts and methodologies. Objectives and strategies are briefly presented and two important features are introduced and discussed; (i Merit Indices: a combination of materials properties, which maximises the objectives chosen by the designer and (ii Materials Properties Maps: a bi-dimensional space whose coordinates are pairs of properties in which materials can be plotted and compared directly in terms of their merit indices. A general strategy for the deduction of these indices is explained and a formal methodology to establish a ranking of candidate materials when multiple constraints intervene is presented. Finally, two case studies are discussed in depth, one related to materials substitution in the context of mechanical design and a less conventional case linking material selection to physical comfort in the home furniture industry.

  4. 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)

  5. 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.

  6. 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

  7. Materials studies for magnetic fusion energy applications at low temperatures. VIII. Technical reports

    International Nuclear Information System (INIS)

    Reed, R.P.

    1985-05-01

    This report contains results of a research progam to produce material property data that will facilitte design and development of cryogenic structures for the superconducting magnets of magnetic fusion energy power plants and prototypes. Research results for 1984 are summarized in an initial ''Highlights of Results'' section and reported in detail in the technical papers that form the main body of this report. The technical papers are presented under four headings reflecting the main program areas: Welding, Nonmetallics, Structural Alloys, and Technology Transfer. Objectives, approaches, and achievements are summarized in an introduction to each program area

  8. Papers of 10. Scientific Technical Seminar on Materials Investigation for Power Industry

    International Nuclear Information System (INIS)

    2003-01-01

    The Report is an assembly of the papers concerning the material and diagnostic problems occurring in the exploitation of power station as well as gas pipelines and underground gas storage technical condition survey. Education and training in welding and non-destructive testing according european rules are also presented as well as provisions of European standards concerning welding consumables. Technical supervision in the light of Poland accession to the european union and quality management system in face of the new standards requirements is described. (author)

  9. Nuclear power plant diagnostics - Safety aspects and licensing. Report of a technical committee meeting. Working material

    International Nuclear Information System (INIS)

    1997-01-01

    The aim of the Technical Committee Meeting (TCM) was to review developed systems and methods in diagnostics in the scope of their impacts and importance to the safety of Nuclear Power Plants. Papers presented on TCM came from different sources, from developers, from manufacturers, from licensing authorities and from NPP personal. They reflect up to date status in the given subject. Participants of TCM formulated three working groups to elaborate different questions which were raised during the discussions. Their results are reflected in the three chapter titles of the given material. Annex 1 to this document contains presentations made at the Technical Committee Meeting. Refs, figs, tabs

  10. 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.

  11. 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

  12. 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

  13. 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

  14. Energy Materials Coordinating Committee (EMaCC): Annual technical report, fiscal year 1993

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department`s materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. This report summarizes EMaCC activities for FY 1993 and describes the materials research programs of various offices and divisions within the Department. The program descriptions consist of a funding summary for each Assistant Secretary office and the Office of Energy Research, and detailed project summaries with project goals and accomplishments. The FY 1993 budget summary table for DOE Materials Activities in each of the programs is presented.

  15. 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)

  16. Exploiting Novel Radiation-Induced Electromagnetic Material Changes for Remote Detection and Monitoring: Final Progress Report

    Science.gov (United States)

    2016-04-01

    Exploiting Novel Radiation -Induced Electromagnetic Material Changes for Remote Detection and Monitoring: Final Progress Report Distribution...assess the effects of ionizing radiation on at least three classes of electromagnetic materials. The proposed approach for radiation detection was...that was desired to be monitored remotely. Microwave or low millimeter wave electromagnetic radiation would be used to interrogate the device

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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.

  3. 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

  4. 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

  5. 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

  6. 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…

  7. 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)

  8. Energy materials coordinating committee (EMaCC). Annual technical report, fiscal year 2003

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2004-10-18

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. Topical subcommittees of the EMaCC are responsible for conducting seminars and otherwise facilitating information flow between DOE organizational units in materials areas of particular importance to the Department. The EMaCC Terms of Reference were recently modified and developed into a Charter that was approved on June 5, 2003. As a result of this reorganization, the existing subcommittees were disbanded and new subcommittees are being formed.

  9. [Fortieth Annual] Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

    International Nuclear Information System (INIS)

    2008-01-01

    The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 39th TWG-FR Annual Meeting, including the status of the actions; - Consider meeting arrangements for 2007, 2008 and 2009; - Review the Agency’s ongoing information exchange and co-ordinated research activities in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations; - Discuss future joint activities in view of the Agency’s Programme and Budget Cycle 2008–2009 (and beyond)

  10. Using constitutive equation gap method for identification of elastic material parameters: Technical insights and illustrations

    KAUST Repository

    Florentin, Éric

    2011-08-09

    The constitutive equation gap method (CEGM) is a well-known concept which, until now, has been used mainly for the verification of finite element simulations. Recently, CEGM-based functional has been proposed to identify local elastic parameters based on experimental full-field measurement. From a technical point of view, this approach requires to quickly describe a space of statically admissible stress fields. We present here the technical insights, inspired from previous works in verification, that leads to the construction of such a space. Then, the identification strategy is implemented and the obtained results are compared with the actual material parameters for numerically generated benchmarks. The quality of the identification technique is demonstrated that makes it a valuable tool for interactive design as a way to validate local material properties. © 2011 Springer-Verlag.

  11. 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

  12. Amarillo National Resource Center for Plutonium. Quarterly technical progress report, February 1, 1998--April 30, 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-06-01

    Activities from the Amarillo National Resource Center for Plutonium are described. Areas of work include materials science of nuclear and explosive materials, plutonium processing and handling, robotics, and storage.

  13. Progress on laboratory studies of the immobilisation of plutonium contaminated materials (pcm)

    International Nuclear Information System (INIS)

    Awmack, A.F.; Hemingway, K.

    1984-09-01

    This report describes progress on laboratory scale investigations into immobilisation of Plutonium Contaminated Materials for the year ending August 1984. The work is a continuation of that previously reported though some new work is also included. The samples tested were shredded plastic materials and latex. Three areas of work are covered (1) ISO Leach Tests (2) Radiolysis and degradation of organic materials (3) Equilibrium Leach Tests. (author)

  14. Technical committee meeting on evaluation of radioactive materials release and sodium fires in fast reactors

    International Nuclear Information System (INIS)

    1996-01-01

    The objectives of the Technical Committee Meeting was to review the activities of research on radioactive materials release and sodium fires in fast reactors in each of the participating countries. It covered: out-of-pile experiments and analysis codes on source term; in-pile experiments on source term; core disruptive accidents; sodium leak experience in liquid metal fast reactors; evaluation of sodium fire; and aerosol behaviour

  15. Technical committee meeting on evaluation of radioactive materials release and sodium fires in fast reactors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-07-01

    The objectives of the Technical Committee Meeting was to review the activities of research on radioactive materials release and sodium fires in fast reactors in each of the participating countries. It covered: out-of-pile experiments and analysis codes on source term; in-pile experiments on source term; core disruptive accidents; sodium leak experience in liquid metal fast reactors; evaluation of sodium fire; and aerosol behaviour.

  16. Progress in the US program to develop low-activation structural materials for fusion

    International Nuclear Information System (INIS)

    Kurtz, R.J.; Jones, R.H.; Bloom, E.E.; Rowcliffe, A.F.; Smith, D.L.; Odette, G.R.; Wiffen, F.W.

    1999-01-01

    It has long been recognized that attainment of the safety and environmental potential of fusion energy requires the successful development of low-activation materials for the first wall, blanket and other high heat flux structural components. Only a limited number of materials potentially possess the physical, mechanical and low-activation characteristics required for this application. The current US structural materials research effort is focused on three candidate materials: advanced ferritic steels, vanadium alloys, and silicon carbide composites. Recent progress has been made in understanding the response of these materials to neutron irradiation. (author)

  17. Progress in the U.S. program to develop low-activation structural materials for fusion

    International Nuclear Information System (INIS)

    Kurtz, R.J.; Jones, R.H.; Bloom, E.E.; Rowcliffe, A.F.; Smith, D.L.; Odette, G.R.; Wiffen, F.W.

    2001-01-01

    It has long been recognized that attainment of the safety and environmental potential of fusion energy requires the successful development of low-activation materials for the first wall, blanket and other high heat flux structural components. Only a limited number of materials potentially possess the physical, mechanical and low-activation characteristics required for this application. The current U.S. structural materials research effort is focused on three candidate materials: advanced ferritic steels, vanadium alloys, and silicon carbide composites. Recent progress has been made in understanding the response of these materials to neutron irradiation. (author)

  18. 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....

  19. 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

  20. 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.

  1. 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....

  2. 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

  3. 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

  4. Technical criteria for terminating or reducing domestic safeguards on low-grade special nuclear material

    International Nuclear Information System (INIS)

    Crawford, D.W.

    1996-01-01

    A graded table for terminating or reducing domestic safeguards has been developed for use by programs and facilities within the Department of Energy in decisions regarding the need for or levels of protection of low-grade nuclear materials. Contained in this table are technical criteria which can allow for complete removal of safeguards over many special nuclear material forms and concentrations of typical low-grade materials either currently located at generating or processing sites and materials which may arise from processing operations related to stabilization and disposition activities. In addition, these criteria include higher concentration levels which may warrant maintaining some level of (albeit reduced) security on low-grade materials while allowing reductions in materials control and accountability requirements. These reductions can range from complete removal of these materials from materials control and accountability requirements such as measurements, physical inventories and recordkeeping, to deferring these measurements and physical inventories until a time that either the material is removed from the site or resubmitted for processing. It is important to note that other conditions contained in current Departmental safeguards and security policy be met prior to safeguards termination or reduction

  5. 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.

  6. Improvement of technical purpose materials performance characteristics with the radio frequency low pressure plasma

    Science.gov (United States)

    Makhotkina, L. Yu; Khristoliubova, V. I.

    2017-11-01

    The main aim of the work is to solve the actual problem of increasing the competitiveness of tanning products by reducing the prime cost and improving the quality of finished products due to the increased durability of the working elements of tanneries. The impact of the low pressure radio frequency (RF) plasma in the processes of treating for modification of the materials for special purposes is considered in the article. The results of working elements of tanneries and the materials for special purposes sample processing by a RF low pressure plasma are described. As a result of leather materials nano structuring and nano modifying physical, mechanical and hygienic characteristics were increased. Processing of the technical purpose materials allows to increase operational performance of products and extend their lifespan.

  7. Conceptualising Digital Materiality and its Socio-Technical Implications through the Phenomenon of Crowdsourcing

    Directory of Open Access Journals (Sweden)

    Patricia Morizio

    2014-10-01

    Full Text Available Digital materiality is a relatively new concept in the information systems literature that attempts to give “substance” to, or explain the material properties of, digital artefacts. These artefacts, such as software programs, are challenging our traditional assumptions of what is “materiality”. Crowdsourcing or the aggregation of publicly-reported data for a variety of purposes – from tracking instances of violence within a geographic area, to coordinating information for aid agencies working in humanitarian emergency situations – is an example technology that transcends the line of a purely physical or digital object. This paper will briefly touch on the definition of digital materiality within IS thought, followed by a discussion of how crowdsourcing fits into its conceptualisation, namely in terms of its characteristics and organisational consequences. The purpose is to instantiate the more theoretical notion of digital materiality through a tangible technology with far-reaching socio-technical implications.

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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.

  14. 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

  15. 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…

  16. 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…

  17. 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…

  18. 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…

  19. 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…

  20. 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…

  1. 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…

  2. 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…

  3. Technical Meeting on Liquid Metal Reactor Concepts: Core Design and Structural Materials. Working Material

    International Nuclear Information System (INIS)

    2013-01-01

    The objective of the TM on “Liquid metal reactor concept: core design and structural materials” was to present and discuss innovative liquid metal fast reactor (LMFR) core designs with special focus on the choice, development, testing and qualification of advanced reactor core structural materials. Main results arising from national and international R&D programmes and projects in the field were reviewed, and new activities to be carried out under the IAEA aegis were identified on the basis of the analysis of current research and technology gaps

  4. [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.''

  5. International cooperation in combating illicit trafficking of nuclear materials by technical means

    International Nuclear Information System (INIS)

    Herbillon, J; Koch, L; Mason, G; Niemeyer, S; Nikiforov, N

    1999-01-01

    A consensus has been emerging during the past several years that illicit trafficking of nuclear materials is a problem that needs a more focused international response. One possible component of a program to combat illicit trafficking is nuclear forensics whereby intercepted nuclear materials are analyzed to provide clues for answering attribution questions. In this report we focus on international cooperation that is specifically addressing the development of nuclear forensics. First we will describe the role of the Nuclear Smuggling International Technical Working Group (ITWG) in developing nuclear forensics, and then we will present some specific examples of cooperative work by the Institute for Transuranium Elements of the European Commission with various European states. Recognizing the potential importance of a nuclear forensics capability, the P-8 countries in 1995 encouraged technical experts to evaluate the role of nuclear forensics in combating nuclear smuggling and possibly developing mechanisms for international cooperation. As a result, an International Conference on Nuclear Smuggling Forensic Analysis was held in November, 1995, at Lawrence Livermore National Laboratory to investigate technical cooperation on nuclear forensics. The International Conference provided a unique mix of scientists, law enforcement, and intelligence experts from 14 countries and organizations. All participants were invited to make presentations, and the format of the Conference was designed to encourage open discussion and broad participation

  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 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.)

  16. Recent progress in research on tungsten materials for nuclear fusion applications in Europe

    Science.gov (United States)

    Rieth, M.; Dudarev, S. L.; Gonzalez de Vicente, S. M.; Aktaa, J.; Ahlgren, T.; Antusch, S.; Armstrong, D. E. J.; Balden, M.; Baluc, N.; Barthe, M.-F.; Basuki, W. W.; Battabyal, M.; Becquart, C. S.; Blagoeva, D.; Boldyryeva, H.; Brinkmann, J.; Celino, M.; Ciupinski, L.; Correia, J. B.; De Backer, A.; Domain, C.; Gaganidze, E.; García-Rosales, C.; Gibson, J.; Gilbert, M. R.; Giusepponi, S.; Gludovatz, B.; Greuner, H.; Heinola, K.; Höschen, T.; Hoffmann, A.; Holstein, N.; Koch, F.; Krauss, W.; Li, H.; Lindig, S.; Linke, J.; Linsmeier, Ch.; López-Ruiz, P.; Maier, H.; Matejicek, J.; Mishra, T. P.; Muhammed, M.; Muñoz, A.; Muzyk, M.; Nordlund, K.; Nguyen-Manh, D.; Opschoor, J.; Ordás, N.; Palacios, T.; Pintsuk, G.; Pippan, R.; Reiser, J.; Riesch, J.; Roberts, S. G.; Romaner, L.; Rosiński, M.; Sanchez, M.; Schulmeyer, W.; Traxler, H.; Ureña, A.; van der Laan, J. G.; Veleva, L.; Wahlberg, S.; Walter, M.; Weber, T.; Weitkamp, T.; Wurster, S.; Yar, M. A.; You, J. H.; Zivelonghi, A.

    2013-01-01

    The current magnetic confinement nuclear fusion power reactor concepts going beyond ITER are based on assumptions about the availability of materials with extreme mechanical, heat, and neutron load capacity. In Europe, the development of such structural and armour materials together with the necessary production, machining, and fabrication technologies is pursued within the EFDA long-term fusion materials programme. This paper reviews the progress of work within the programme in the area of tungsten and tungsten alloys. Results, conclusions, and future projections are summarized for each of the programme's main subtopics, which are: (1) fabrication, (2) structural W materials, (3) W armour materials, and (4) materials science and modelling. It gives a detailed overview of the latest results on materials research, fabrication processes, joining options, high heat flux testing, plasticity studies, modelling, and validation experiments.

  17. Recent progress in research on tungsten materials for nuclear fusion applications in Europe

    International Nuclear Information System (INIS)

    Rieth, M.; Dudarev, S.L.; Gonzalez de Vicente, S.M.; Aktaa, J.; Ahlgren, T.; Antusch, S.; Armstrong, D.E.J.; Balden, M.; Baluc, N.; Barthe, M.-F.; Basuki, W.W.; Battabyal, M.; Becquart, C.S.; Blagoeva, D.; Boldyryeva, H.

    2013-01-01

    The current magnetic confinement nuclear fusion power reactor concepts going beyond ITER are based on assumptions about the availability of materials with extreme mechanical, heat, and neutron load capacity. In Europe, the development of such structural and armour materials together with the necessary production, machining, and fabrication technologies is pursued within the EFDA long-term fusion materials programme. This paper reviews the progress of work within the programme in the area of tungsten and tungsten alloys. Results, conclusions, and future projections are summarized for each of the programme’s main subtopics, which are: (1) fabrication, (2) structural W materials, (3) W armour materials, and (4) materials science and modelling. It gives a detailed overview of the latest results on materials research, fabrication processes, joining options, high heat flux testing, plasticity studies, modelling, and validation experiments.

  18. Recent progress in research on tungsten materials for nuclear fusion applications in Europe

    Energy Technology Data Exchange (ETDEWEB)

    Rieth, M., E-mail: Michael.rieth@kit.edu [Karlsruhe Institute of Technology, Institute for Applied Materials, Karlsruhe (Germany); Dudarev, S.L. [EURATOM/CCFE Fusion Association, Culham Science Centre, Abingdon OX14 3DB (United Kingdom); Gonzalez de Vicente, S.M. [EFDA-Close Support Unit, Garching (Germany); Aktaa, J. [Karlsruhe Institute of Technology, Institute for Applied Materials, Karlsruhe (Germany); Ahlgren, T. [University of Helsinki, Department of Physics, Helsinki (Finland); Antusch, S. [Karlsruhe Institute of Technology, Institute for Applied Materials, Karlsruhe (Germany); Armstrong, D.E.J. [Department of Materials, University of Oxford (United Kingdom); Balden, M. [Max-Planck-Institut fuer Plasmaphysik, EURATOM Association, Garching (Germany); Baluc, N. [Centre de Recherches en Physique des Plasmas, CRPP EPFL - Materials, 5232 Villigen/PSI (Switzerland); Barthe, M.-F. [CNRS, UPR3079 CEMHTI, 1D Avenue, de la Recherche Scientifique, 45071 Orleans cedex 2 (France); Universite d' Orleans, Polytech ou Faculte des Sciences, Avenue du Parc Floral, BP 6749, 45067 Orleans cedex 2 (France); Basuki, W.W. [Karlsruhe Institute of Technology, Institute for Applied Materials, Karlsruhe (Germany); Battabyal, M. [Centre de Recherches en Physique des Plasmas, CRPP EPFL - Materials, 5232 Villigen/PSI (Switzerland); Becquart, C.S. [Unite Materiaux et Transformations, UMR 8207, 59655 Villeneuve d' Ascq (France); Blagoeva, D. [NRG, Nuclear Research and consultancy Group, Petten (Netherlands); Boldyryeva, H. [Institute of Plasma Physics, Za Slovankou 3, 18200 Praha (Czech Republic); and others

    2013-01-15

    The current magnetic confinement nuclear fusion power reactor concepts going beyond ITER are based on assumptions about the availability of materials with extreme mechanical, heat, and neutron load capacity. In Europe, the development of such structural and armour materials together with the necessary production, machining, and fabrication technologies is pursued within the EFDA long-term fusion materials programme. This paper reviews the progress of work within the programme in the area of tungsten and tungsten alloys. Results, conclusions, and future projections are summarized for each of the programme's main subtopics, which are: (1) fabrication, (2) structural W materials, (3) W armour materials, and (4) materials science and modelling. It gives a detailed overview of the latest results on materials research, fabrication processes, joining options, high heat flux testing, plasticity studies, modelling, and validation experiments.

  19. Amarillo National Resource Center for Plutonium quarterly technical progress report, August 1--October 31, 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-11-01

    This paper describes activities of the Center under the following topical sections: Electronic resource library; Environmental restoration and protection; Health and safety; Waste management; Communication program; Education program; Training; Analytical development; Materials science; Plutonium processing and handling; and Storage.

  20. LOA-1: prevent accidents. Quarterly technical progress report, FRSP program - July through September 1981

    International Nuclear Information System (INIS)

    1981-01-01

    Information related to LMFBR reactor safety is presented concerning common cause failures; shutdown by self-activated system; shutdown heat removal system operation; sodium burning; core catcher material interactions; accident release of sodium oxide aerosol; and LMFBR risk assessment

  1. Introduction to the special issue on the technical status of materials for a fusion reactor

    Science.gov (United States)

    Stork, D.; Zinkle, S. J.

    2017-09-01

    Materials determine in a fundamental way the performance and environmental attractiveness of a fusion reactor: through the size (power fluxes to the divertor, neutron fluxes to the first wall); economics (replacement lifetime of critical in-vessel components, thermodynamic efficiency through operating temperature etc); plasma performance (erosion by plasma fluxes to the divertor surfaces); robustness against off-normal accidents (safety); and the effects of post-operation radioactivity on waste disposal and maintenance. The major philosophies and methodologies used to formulate programmes for the development of fusion materials are outlined, as the basis for other articles in this special issue, which deal with the fundamental understanding of the issues regarding these materials and their technical status and prospects for development.

  2. Glass melter materials technical options for the French vitrification process and operations experience authors

    International Nuclear Information System (INIS)

    Bonniaud, R.; Roznad, L.; Demay, R.

    1986-09-01

    The French vitrification process for solidifying high-level radioactive waste which has been under industrial application since 1978, is mentioned briefly. This technique involves glass melting at 1,150 deg.C, using an induction heated metallic vessel. The molten glass pouring is controlled by a thermal gate, which is also heated by induction. Two types of vessel are in use. Both are remotely removable and disposable to permit replacement at regular intervals. The technical criteria (the materials used have to meet) are described. The behaviour of the materials has been investigated using the industrial experience gained in the AVM facility during 8 years of operation, as well as with operation of a prototype for the new vitrification facilities under construction at La Hague. A short description of the use of these materials is also presented

  3. Conceptual framework and technical basis for clearance of materials with residual radioactivity

    International Nuclear Information System (INIS)

    Chen, S.Y.

    1997-01-01

    The primary impediment to the release of materials containing residual radioactivity from a controlled environment is the lack of a suitable framework within which release standards can be developed. Recently, the 'risk-based' approach has been proposed as an appropriate means of setting standards. The term 'clearance' has been introduced by the International Atomic Energy Commission as a regulatory process for releasing radioactive materials posing trivial risks. A 'trivial' risk level has been determined to be on the order of 10[sup -6] to 10[sup -7] annual risk to an exposed individual, and a population risk of no more than 0.1 annually. Under these strict constraints, exposure scenarios may account for processing, disposal, and product end-use of materials. This paper discusses these scenarios and also describes the technical basis for deriving release levels under the suggested risk (or dose) constraints

  4. Progress report for 1984/85 from the Plutonium Contaminated Materials Working Party

    International Nuclear Information System (INIS)

    Higson, S.G.

    1985-01-01

    The progress report for 1984/5 from the 'Plutonium Contaminated Materials Working Party' is presented. The report is divided into eight main topics, each discussed separately, and include: reduction of arisings, plutonium measurement, sorting and packaging, washing of shredded combustible plutonium contaminated materials (PCM), decommissioning and non-combustible PCM treatment, PCM immobilization, treatment of alpha bearing liquid wastes, and engineering objectives. (U.K.)

  5. Progress report for 1982/83 from the Plutonium Contaminated Materials Working Party

    International Nuclear Information System (INIS)

    Higson, S.G.

    1983-01-01

    The report falls under the headings: introduction (definitions of plutonium contaminated materials (PCM)); organisation and role of the Plutonium Contaminated Materials Working Party; management practices in relation to PCM; 1982/1983 Progress Report (engineering objectives; reduction of PCM arisings; plutonium measurement; development of treatment processes; decommissioning and non-combustible PCM treatment; washing of shredded combustible PCM; PCM immobilisation; liquid effluent treatment; actinide chemistry); programme management. (U.K.)

  6. Characterization of the Material Microstructure for Reactive Material Design. 3rd Quarterly Progress Report II/2008

    Science.gov (United States)

    2008-08-05

    metallic) materials, which fragment under certain dynamic loading conditions into small particles, which can chemically react with a suitable ambient ...medium, such as shock heated ambient air or hot detonation products. Such materials could be effectively used to devise new or improved weapons with...test is blue. The impacto conditions of the the center of the the opposite surfa reflection of the w Figure 6.1: Example o specimen. Another aspect

  7. 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)

  8. 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)

  9. 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)

  10. 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)

  11. 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)

  12. 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.)

  13. 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)

  14. 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.

  15. 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.

  16. 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

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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

  3. 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

  4. 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

  5. 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

  6. 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)

  7. 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

  8. Plutonium contaminated materials research programme. Progress Report for 1983/84 from the Plutonium Contaminated Materials Working Party

    International Nuclear Information System (INIS)

    Higson, S.G.

    1984-01-01

    Plutonium contaminated material (PCM) is a generic term applied to a wide variety of materials which have become contaminated by plutonium compounds, by virtue of their use inside the primary containment of fuel cycle plants, but which generally have low beta gamma content. The report falls under the headings: introduction; organisation and role of the PCMWP; management practices; 1983/84 progress report (a) reduction of arisings; (b) plutonium measurement; (c) treatment of solid PCM; (d) treatment of alpha bearing liquid wastes; (e) actinide chemistry; (f) engineering objectives. (U.K.)

  9. Metals and ceramics division materials science program. Aunnual progress report for period ending June 30, 1979

    International Nuclear Information System (INIS)

    McHargue, C.J.; b.

    1979-10-01

    Progress is reported concerning theoretical studies of metals and alloys, deformation and mechanical properties, physical properties and transport phenomena, radiation effects, and engineering materials. During this period emphasis was shifted from support of nuclear technologies to support of nonnuclear energy systems

  10. Metals and ceramics division materials science program. Aunnual progress report for period ending June 30, 1979

    Energy Technology Data Exchange (ETDEWEB)

    McHargue, C.J.

    1979-10-01

    Progress is reported concerning theoretical studies of metals and alloys, deformation and mechanical properties, physical properties and transport phenomena, radiation effects, and engineering materials. During this period emphasis was shifted from support of nuclear technologies to support of nonnuclear energy systems. (FS)

  11. Progress report for 1986 from the Plutonium Contaminated Materials Working Party

    International Nuclear Information System (INIS)

    Higson, S.G.

    1987-11-01

    The paper covers progress during 1986 under the joint BNFL/MOD/DoE funded PCM Working Party studying the management, treatment and immobilization of plutonium contaminated materials. Development is reported under each of seven main programme headings including reduction of arisings, Pu measurement, decommissioning and non-combustible PCM treatment, liquid effluent treatment, sorting and packaging, PCM immobilisation and engineering objectives. (author)

  12. 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

  13. 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

  14. 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)

  15. Applications of Research Reactors Towards Research on Materials for Nuclear Fusion Technology. Proceedings of a Technical Meeting

    International Nuclear Information System (INIS)

    2013-11-01

    of materials under development for Generation IV concepts. International collaboration among MTRs and specialized facilities has been identified as integral to progress in fusion development as well as enhancing reactor utilization. This publication specifies which areas of research remain in the qualification of structural materials and components, and has detailed the characteristics of many research reactors and devices that can accomplish an important portion of these necessary studies. This publication is the outcome of two recent IAEA sponsored meetings under its programme to enhance the utilization and collaboration of research reactor and material test facilities: - Consultancy meeting on Role of Research Reactors in Materials Research for Nuclear Fusion Technology, 13-15 December 2010, IAEA, Vienna; - Technical meeting on Materials under High Energy and High Intensity Neutron Fluxes for Nuclear Fusion Technology, 27-29 June 2011, IAEA, Vienna. These meetings brought together representatives from MTRs, spallation neutron sources, multiple beam irradiation facilities, material scientists as well as fusion community representatives to discuss the current state of fusion research and to plot necessary studies and modes of research collaboration

  16. 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.)

  17. IAEA technical meeting on fissile material strategies for sustainable nuclear energy

    International Nuclear Information System (INIS)

    Ganguly, Chaitanyamoy; Koyama, Kazutoshi

    2005-01-01

    A Technical Meeting (TM) on 'Fissile Material Management Strategies for Sustainable Nuclear Energy' was organized by the International Atomic Energy Agency (IAEA) in Vienna from 12 to 15 September 2005. Prior to the TM, three Working Groups (WG) composed of experts from 10 countries prepared Key Issues papers on: 1) Uranium Demand and Supply through 2050; 2) Back-end Fuel Cycle Options; and 3) Sustainable Nuclear Energy beyond 2050: Cross-cutting Issues. Some 36 papers, including 3 key issue papers, were presented during the TM in 3 different sessions. The present paper summarizes the deliberations of the TM. (author)

  18. INCREASING THE EFFICIENCY OF ENTERPRISES' MATERIAL AND TECHNICAL EQUIPMENT (in Russian

    Directory of Open Access Journals (Sweden)

    Victor NORDIN

    2014-07-01

    Full Text Available The article pointed out the desirability of use of the “process approach” to material and technical equipment of enterprise, which will link its processes and develop an effective management system. It is proposed a form of table (matrix to enter data into an electronic database. In addition, it is proposed to create a unified management system and a set of information about procurement activities with the efficiency assessment of the resource purchasing processes and their quality through comprehensive quality indicators.

  19. Amarillo National Resource Center for Plutonium quarterly technical progress report, August 1, 1997--October 31, 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    This report summarizes activities of the Amarillo National Resource Center for Plutonium during the quarter. The report describes the Electronic Resource Library; DOE support activities; current and future environmental health and safety programs; pollution prevention and pollution avoidance; communication, education, training, and community involvement programs; and nuclear and other material studies, including plutonium storage and disposition studies.

  20. New imaging systems in nuclear medicine. Technical progress report, January 1, 1982-December 31, 1983

    International Nuclear Information System (INIS)

    Brownell, G.L.

    1983-01-01

    A new instrumentation concept has been developed for the analogue ring detector (PR-I) and its success has been demonstrated. Software for PRI has been developed. Studies of new instrumentation methods and materials include extension of the analog concepts to higher spatial resolution, higher data rates and cylindrical shaped detectors

  1. Neutron reflectometry: A probe for materials surfaces. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2006-01-01

    Research reactors play an important role in delivering the benefits of nuclear science and technology. The IAEA, through its project on the effective utilization of research reactors, has been providing technical support to Member States and promotes activities related to specific applications. Neutron beam research is one of the main components in materials science studies. Neutron reflectometry is extremely useful for characterizing thin films and layered structures, polymers, oxide coatings on metals and biological membranes. The neutron has been a major probe for investigating magnetic materials. Development of magnetic multilayers is important for diverse applications in sensors, memory devices, etc. The special nature of the interaction of the neutron with matter makes it an important tool to locate low z elements in the presence of high z elements, which is useful in biology and polymer science. The role of neutron reflectometry in research and development in materials science and technology was discussed in a consultants meeting held in 2003. Following this, a technical meeting was organized from 16 to 20 August 2004 in Vienna to discuss the current status of neutron reflectometry, including the instrumentation, data acquisition, data analysis and applications. Experts in the field of neutron reflectometry presented their contributions, after which there was a brainstorming session on various aspects of the technique and its applications. This publication is the outcome of deliberations during the meeting and the presentations by the participants. This publication will be of use to scientists planning to develop a neutron reflectometer at research reactors. It will also help disseminate knowledge and information to material scientists, biologists and chemists working towards characterizing and developing new materials

  2. 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

  3. 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

  4. 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

  5. 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

  6. 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)

  7. 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.

  8. 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

  9. 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

  10. [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.

  11. 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.)

  12. 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

  13. 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.)

  14. 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

  15. 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

  16. Construction demolition wastes, Waelz slag and MSWI bottom ash: a comparative technical analysis as material for road construction.

    Science.gov (United States)

    Vegas, I; Ibañez, J A; San José, J T; Urzelai, A

    2008-01-01

    The objective of the study is to analyze the technical suitability of using secondary materials from three waste flows (construction and demolition waste (CDW), Waelz slag and municipal solid waste incineration (MSWI) bottom ash), under the regulations and standards governing the use of materials for road construction. A detailed technical characterization of the materials was carried out according to Spanish General Technical Specifications for Road Construction (PG3). The results show that Waelz slag can be adequate for using in granular structural layers, while CDW fits better as granular material in roadbeds. Likewise, fresh MSWI bottom ash can be used as roadbed material as long as it does not contain a high concentration of soluble salts. This paper also discusses the adequacy of using certain traditional test methods for natural soils when characterizing secondary materials for use as aggregates in road construction.

  17. Technical basis for exemption from alpha surveys for personnel, material, and equipment in the 324 facility

    International Nuclear Information System (INIS)

    RIDDELLE, J.G.

    1998-01-01

    The purpose of this document is to establish the technical basis for characterizing grouted B-Cell waste for disposal at the Hanford Burial Grounds using the 3-82B shipping cask. The scope of this document includes establishing the technical basis for loading the shipping package, an HN-200 Grout Container, to ensure that: (1) the amount of material in the grout container does not exceed the 100 nCl alpha/g limit that would cause the waste to be designated as ''greater that Category 3'' (GC3) or transuranic (TRU) waste (2) the amount of heat generated by the waste in the grout container does not exceed the 60 Watt heat generation limit established in the 3-82B shipping cask Safety Analysis Report (SAR); and (3) the dose rate on the surface of the shipping cask after loading does not exceed the 200 mrem/h limit established in the cask SAR. This document establishes the technical basis for performing measurements and analyses that will ensure that none of these three limits are exceeded

  18. Combating illicit trafficking in nuclear and other radioactive material. Technical guidance. Reference manual. (Chinese Edition)

    International Nuclear Information System (INIS)

    2012-01-01

    This publication is intended for individuals and organizations that may be called upon to deal with the detection of and response to criminal or unauthorized acts involving nuclear or other radioactive material. It will also be useful for legislators, law enforcement agencies, government officials, technical experts, lawyers, diplomats and users of nuclear technology. This manual emphasizes the international initiatives for improving the security of nuclear and other radioactive material. However, it is recognized that effective measures for controlling the transfer of equipment, non-nuclear material, technology or information that may assist in the development of nuclear explosive devices, improvised nuclear devices (INDs) or other radiological dispersal devices (RDDs) are important elements of an effective nuclear security system. In addition, issues of personal integrity, inspection and investigative procedures are not discussed in this manual, all of which are essential elements for an effective overall security system. The manual considers a variety of elements that are recognized as being essential for dealing with incidents of criminal or unauthorized acts involving nuclear and other radioactive material. Depending on conditions in a specific State, including its legal and governmental infrastructure, some of the measures discussed will need to be adapted to suit that State's circumstances. However, much of the material can be applied directly in the context of other national programmes. This manual is divided into four main parts. Section 2 discusses the threat posed by criminal or unauthorized acts involving nuclear and other radioactive material, as well as the policy and legal bases underlying the international effort to restrain such activities. Sections 3 and 4 summarize the major international undertakings in the field. Sections 5-8 provide some basic technical information on radiation, radioactive material, the health consequences of radiation

  19. 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)

  20. 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

  1. 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).

  2. 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.

  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. 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.

  5. Nuclear Safety. Technical Progress Journal, October--December 1992: Volume 33, No. 4

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-01-01

    This review journal covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  6. Nuclear Safety. Technical progress journal, January--March 1994: Volume 35, No. 1

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1994-01-01

    This is a journal that covers significant issues in the field of nuclear safety. Its primary scope is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but it also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, and nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities.

  7. Nuclear Safety. Technical progress journal, April--June 1992: Volume 33, No.2

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1992-01-01

    This review journal covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  8. Nuclear Safety. Technical Progress Journal, January--March 1993: Volume 34, No. 1

    Energy Technology Data Exchange (ETDEWEB)

    None

    1993-01-01

    This review journal covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  9. Nuclear Safety. Technical progress journal, April--June 1996: Volume 37, No. 2

    Energy Technology Data Exchange (ETDEWEB)

    Muhlheim, M D [ed.

    1996-01-01

    This journal covers significant issues in the field of nuclear safety. Its primary scope is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but it also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities.

  10. Nuclear Safety. Technical Progress Journal, January--March 1992: Volume 33, No. 1

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-01-01

    This review journal covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  11. 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).

  12. From low cost to high tech: possible margins of technical progress in photovoltaic

    International Nuclear Information System (INIS)

    Guillemoles, J.F.

    2009-01-01

    Photovoltaic is developing in response to 3 requirements: conservation of the environment, security in energy, and economic growth. Given this, the terawatt (TW) scale should be used to measure the magnitude of energy needs. Can solar, in particular photovoltaic, power meet these needs? This has nothing to do with the availability of solar energy - in a single hour, the sun sends to the earth as much energy as the electricity consumed by all of humanity during an entire year. Instead, it raises questions about the industrial deployment and, eventually, the availability of raw materials and land. The sustainable development of photovoltaic power implies wisely using resources (raw materials, energy and capital) and improving the efficiency not only of the process for transforming resources into photovoltaic units but also of the photovoltaic units themselves for converting light into electricity. It is worth noting that the predictable change of scale in the photovoltaic industry will have implications for this industry's deployment on a large scale. This deployment depends on: the availability of technology, know-how, capital and raw materials; the cost of investments; the speed of implementation; and the rhythm of production of cells. (author)

  13. 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.

  14. Energy Materials Coordinating Committee (EMaCC), fiscal year 1985. Annual technical report

    International Nuclear Information System (INIS)

    1986-05-01

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further the effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meeting/workshops on selected topics involving both DOE and major contractors. Four topical subcommittees on Structural Ceramics, Batteries and Fuel Cells, Radioactive Waste Containment, and Steel are established and are continuing their own program. The FY 1985 and FY 1986 meeting program is given. The EMaCC aids in obtaining materials-related inputs for both intra- and inter-agency compilations. Brief summaries of the materials research programs associated with each office and division are presented, including tables listing individual projects and the FY 1985 budgets for each. More details on the individual projects within the divisions and the specific tasks or subcontracts within the various projects are given in the paragraph descriptions

  15. Assessment of international reference materials for isotope-ratio analysis (IUPAC Technical Report)

    Science.gov (United States)

    Brand, Willi A.; Coplen, Tyler B.; Vogl, Jochen; Rosner, Martin; Prohaska, Thomas

    2014-01-01

    Since the early 1950s, the number of international measurement standards for anchoring stable isotope delta scales has mushroomed from 3 to more than 30, expanding to more than 25 chemical elements. With the development of new instrumentation, along with new and improved measurement procedures for studying naturally occurring isotopic abundance variations in natural and technical samples, the number of internationally distributed, secondary isotopic reference materials with a specified delta value has blossomed in the last six decades to more than 150 materials. More than half of these isotopic reference materials were produced for isotope-delta measurements of seven elements: H, Li, B, C, N, O, and S. The number of isotopic reference materials for other, heavier elements has grown considerably over the last decade. Nevertheless, even primary international measurement standards for isotope-delta measurements are still needed for some elements, including Mg, Fe, Te, Sb, Mo, and Ge. It is recommended that authors publish the delta values of internationally distributed, secondary isotopic reference materials that were used for anchoring their measurement results to the respective primary stable isotope scale.

  16. Energy Materials Coordinating Committee (EMaCC), fiscal year 1985. Annual technical report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1986-05-01

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further the effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meeting/workshops on selected topics involving both DOE and major contractors. Four topical subcommittees on Structural Ceramics, Batteries and Fuel Cells, Radioactive Waste Containment, and Steel are established and are continuing their own program. The FY 1985 and FY 1986 meeting program is given. The EMaCC aids in obtaining materials-related inputs for both intra- and inter-agency compilations. Brief summaries of the materials research programs associated with each office and division are presented, including tables listing individual projects and the FY 1985 budgets for each. More details on the individual projects within the divisions and the specific tasks or subcontracts within the various projects are given in the paragraph descriptions.

  17. Behaviour of LWR core materials under accident conditions. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1996-12-01

    At the invitation of the Government of the Russian Federation, following a proposal of the International Working Group on Water Reactor Fuel Performance and Technology, the IAEA convened a Technical Committee Meeting on Behaviour of LWR Core Materials Under Accident Conditions from 9 to 13 October 1995 in Dimitrovgrad to analyze and evaluate the behaviour of LWR core materials under accident conditions with special emphasis on severe accidents. In-vessel severe accidents phenomena were considered in detail, but specialized thermal hydraulic aspects as well as ex-vessel phenomena were outside the scope of the meeting. Forty participants representing eight countries attended the meeting. Twenty-three papers were presented and discussed during five sessions. Refs, figs, tabs

  18. 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

  19. 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

  20. 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)

  1. 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.

  2. 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.

  3. 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

  4. 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

  5. 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

  6. 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

  7. 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.

  8. 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

  9. 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.

  10. 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

  11. 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.

  12. 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

  13. Magnetic fusion energy materials technology program annual progress report for period ending June 30, 1977

    International Nuclear Information System (INIS)

    Scott, J.L.

    1977-09-01

    The objectives of the Magnetic Fusion Energy (MFE) Materials Technology Program, which is described in this report, are to continue to solve the materials problems of the Fusion Energy Division of ORNL and to meet needs of the national MFE program, directed by the ERDA Division of Magnetic Fusion Energy (DMFE). This work is a continuation of the program described in previous annual progress reports. The principal areas of work include radiation effects, compatibility studies, materials studies related to the plasma-materials interaction, materials engineering, radiation behavior of superconducting magnet insulation, and mechanical properties of superconducting composites. The level of effort and schedules are consistent with Logic II of the DMFE Program Plan

  14. Metals and Ceramics Division materials science annual progress report for period ending June 30, 1977

    International Nuclear Information System (INIS)

    McHargue, C.J.

    1977-09-01

    Progress is reported for research programs in the metals and ceramics division of ORNL. In structure of materials, theoretical research, x-ray diffraction studies, studies of erosion of ceramics, preparation and synthesis of high temperature and special service materials, and studies of stabilities of microphases in high-temperature structural materials. Research into deformation and mechanical properties included physical metallurgy, and grain boundary segregation and embrittlement. Physical properties and transport phenomena were studied and included mechanisms of surface and solid state reactions, and properties of superconducting materials. The radiation effects program, directed at understanding the effects of composition and microstructure on the structure and properties of materials irradiated at elevated temperatures, is also described

  15. Nuclear Safety. Technical Progress Journal, October--December 1991: Volume 32, No. 4

    Energy Technology Data Exchange (ETDEWEB)

    1991-01-01

    This document is a review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  16. Support of scientific and technical progress in system of power engineering

    International Nuclear Information System (INIS)

    Khrapunov, V.V.

    1996-01-01

    The priority trends of the Republic Kazakhstan energetic policy are listed. These priorities define the principal trends in power engineering and coal industry. There are as following: creation and mastering new and modernizing existing technologies of mining, processing and combustion of fuel; electric and thermal power generation, maintaining significant reduce of a harmful exposure to environment, an economic efficiency at market economy conditions under high level of use of nature resources and raw materials; involving in power balance nontraditional and renewable energy sources, intensification works on energy conservation, reliability and vitality of power systems

  17. 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

  18. Nuclear safety. Technical progress journal, January--March 1996: Volume 37, No. 1

    Energy Technology Data Exchange (ETDEWEB)

    Muhlheim, M D [ed.

    1996-01-01

    Nuclear Safety is a journal that covers significant issues in the field of nuclear safety. Its primary scope is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but is also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, and nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities. Individual articles are indexed separately for the data base.

  19. Trends of progress in medical technics as far as automatization is concerned

    Energy Technology Data Exchange (ETDEWEB)

    Agoston, M [Medicor Muevek, Budapest (Hungary)

    1978-09-01

    Modernization of medical treatment is developing to the direction of establishing big hospitals and policlinics. Highly productive automatic equipments give possibilities for performing the mass examinations with high efficiency. Still the X-ray instruments form the most valuable and indispensable device group. One direction to develop the automatization of these machines is to achieve the best X-ray exposure. The relatively slow but continuous spreading of isotope diagnostic instruments has been connected with a number of results in automatization, too. In the field of sterilization bactericid materials, gas- and ray sterilizing methods, as well as combined systems become used. Automatization has a strong influence on the domain of epidemiology as well.

  20. 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.

  1. Nuclear Safety. Technical Progress Journal, April--June 1993: Volume 34, No. 2

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1993-01-01

    This review journal that covers significant developments in the field of Nuclear Safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations are also treated.

  2. Nuclear Safety Technical Progress Journal, January--June 1995. Volume 36, No. 1

    Energy Technology Data Exchange (ETDEWEB)

    Silver, E G [ed.

    1995-01-01

    This journal covers significant issues in the field of nuclear safety. Its primary scope is safety in the design, construction, operation, and decommissioning of nuclear power reactors worldwide and the research and analysis activities that promote this goal, but it also encompasses the safety aspects of the entire nuclear fuel cycle, including fuel fabrication, spent-fuel processing and handling, and nuclear waste disposal, the handling of fissionable materials and radioisotopes, and the environmental effects of all these activities. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  3. Nuclear Safety. Technical Progress Journal, July--September 1992: Volume 33, No. 3

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-01-01

    This review journal that covers significant developments in the field of nuclear safety. Its scope includes the analysis and control of hazards associated with nuclear energy, operations involving fissionable materials, and the products of nuclear fission and their effects on the environment. Primary emphasis is on safety in reactor design, construction, and operation; however, the safety aspects of the entire fuel cycle, including fuel fabrication, spent-fuel processing, nuclear waste disposal, handling of radioisotopes, and environmental effects of these operations, are also treated.

  4. Structural Aging Program technical progress for period, January 1, 1992--December 31, 1992

    International Nuclear Information System (INIS)

    Naus, D.J.; Oland, C.B.

    1993-07-01

    The Structural Aging (SAG) Program is conducted for the Nuclear Regulatory Commission (NRC) by the Oak Ridge National Laboratory (ORNL). The program has the overall objective of preparing an expandable handbook or report which will provide potential structural safety issues and acceptance criteria for use by the NRC in nuclear power plant evaluations of continued service. Initial focus of the program is on concrete and concrete-related materials which comprise safety-related (Category I) structures in light-water reactor facilities. The SAG Program is organized into four tasks: Task S.1 -- Program Management, Task S.2 -- Materials Property Data Base, Task S.3 -- Structural Component Assessment/Repair Technology, and Task S.4 -- Quantitative Methodology for Continued Service Determinations. In meeting the individual objectives of these tasks resources are drawn from ORNL with subcontract support from universities and other research laboratories. This report provides an overview of principal developments in each of the four program tasks from January 1, 1992 to December 31, 1992. Planned activities under each of these tasks are also presented

  5. A Duration Prediction Using a Material-Based Progress Management Methodology for Construction Operation Plans

    Directory of Open Access Journals (Sweden)

    Yongho Ko

    2017-04-01

    Full Text Available Precise and accurate prediction models for duration and cost enable contractors to improve their decision making for effective resource management in terms of sustainability in construction. Previous studies have been limited to cost-based estimations, but this study focuses on a material-based progress management method. Cost-based estimations typically used in construction, such as the earned value method, rely on comparing the planned budget with the actual cost. However, accurately planning budgets requires analysis of many factors, such as the financial status of the sectors involved. Furthermore, there is a higher possibility of changes in the budget than in the total amount of material used during construction, which is deduced from the quantity take-off from drawings and specifications. Accordingly, this study proposes a material-based progress management methodology, which was developed using different predictive analysis models (regression, neural network, and auto-regressive moving average as well as datasets on material and labor, which can be extracted from daily work reports from contractors. A case study on actual datasets was conducted, and the results show that the proposed methodology can be efficiently used for progress management in construction.

  6. 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.

  7. 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.

  8. 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

  9. 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

  10. 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

  11. Energy materials coordinating committee (EMaCC). Annual technical report, fiscal year 2004

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2005-08-31

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. Topical subcommittees of the EMaCC are responsible for conducting seminars and otherwise facilitating information flow between DOE organizational units in materials areas of particular importance to the Department. The EMaCC Terms of Reference were recently modified and developed into a Charter that was approved on June 5, 2003. As a result of this reorganization, the existing subcommittees were disbanded and new subcommittees are being formed. The FY 2004 budget summary for DOE Materials Activities is presented on page 8. The distribution of these funds between DOE laboratories, private industry, academia and other organizations is presented in tabular form on page 10. Following the budget summary is a set of detailed program descriptions for the FY 2004 DOE Materials activities. These descriptions are presented according to the organizational structure of the Department. A mission statement, a budget summary listing the project titles and FY 2004 funding, and detailed project summaries are presented for each Assistant Secretary office, the Office of Science, and the National Nuclear Security Administration. The project summaries also provide DOE, laboratory, academic and industrial contacts for each project, as appropriate.

  12. Energy materials coordinating committee (EMaCC). Annual technical report, fiscal year 2002

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2003-08-08

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. Topical subcommittees of the EMaCC are responsible for conducting seminars and otherwise facilitating information flow between DOE organizational units in materials areas of particular importance to the Department. The EMaCC Terms of Reference were recently modified and developed into a Charter that was approved on June 5, 2003. As a result of this reorganization, the existing subcommittees were disbanded and new subcommittees are being formed. The EMaCC Charter and the memorandum approving it are presented in the Appendix of this report. The FY 2002 budget summary for DOE Materials Activities is presented on page 8. The distribution of these funds between DOE laboratories, private industry, academia and other organizations is presented in tabular form on page 10. Following the budget summary is a set of detailed program descriptions for the FY 2002 DOE Materials activities. These descriptions are presented according to the organizational structure of the Department. A mission statement, a budget summary listing the project titles and FY 2002 funding, and detailed project summaries are presented for each Assistant Secretary office, the Office of Science, and the National Nuclear Security Administration. The project summaries also provide DOE, laboratory, academic and industrial contacts for each project, as appropriate.

  13. Energy materials coordinating committee (EMaCC). Annual technical report, fiscal year 2005

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2006-09-29

    The DOE Energy Materials Coordinating Committee (EMaCC) serves primarily to enhance coordination among the Department's materials programs and to further effective use of materials expertise within the Department. These functions are accomplished through the exchange of budgetary and planning information among program managers and through technical meetings/workshops on selected topics involving both DOE and major contractors. In addition, EMaCC assists in obtaining materials-related inputs for both intra- and interagency compilations. Topical subcommittees of the EMaCC are responsible for conducting seminars and otherwise facilitating information flow between DOE organizational units in materials areas of particular importance to the Department. The EMaCC Terms of Reference were recently modified and developed into a Charter that was approved on June 5, 2003. As a result of this reorganization, the existing subcommittees were disbanded and new subcommittees are being formed. The FY 2004 budget summary for DOE Materials Activities is presented on page 8. The distribution of these funds between DOE laboratories, private industry, academia and other organizations is presented in tabular form on page 10. Following the budget summary is a set of detailed program descriptions for the FY 2004 DOE Materials activities. These descriptions are presented according to the organizational structure of the Department. A mission statement, a budget summary listing the project titles and FY 2004 funding, and detailed project summaries are presented for each Assistant Secretary office, the Office of Science, and the National Nuclear Security Administration. The project summaries also provide DOE, laboratory, academic and industrial contacts for each project, as appropriate.

  14. 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)

  15. Fission product thermodynamic data: technical progress report 1 January-30 June 1991

    International Nuclear Information System (INIS)

    Ball, R.G.J.; Yates, A.D.; Bowsher, B.R.; Dickinson, S.; Freemantle, N.E.; Day, T.; Ogden, J.S.

    1991-07-01

    Thermodynamic data are being determined for a number of compounds formed from specific fission products and reactor materials. The compounds selected for experimental study and critical assessment were chosen because their thermodynamic data were inadequate or did not exist, as assessed and recommended at a specialists' meeting. These data can be used in the appropriate computer code so that the speciation and transport properties of the fission products can be predicted during a severe reactor accident. Experimental studies have focussed on the vaporization of tellurium dioxide, caesium ruthenate, strontium borate and indium hydroxide. Critical evaluations have begun for a number of tellurides of importance in severe accident assessments, and preliminary analyses have been made of the Fe-Te, Ni-Te and Cr-Te systems. (author)

  16. Structure sensitive reactions over Co, Fe and mixed metal clusters in zeolites. Annual technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    Suib, S.L.

    1992-08-01

    Transient and steady state kinetic studies of structure sensitive reactions of cyclopropane (c-C{sub 3}H{sub 6}) and hydrogen over zeolites is the first area of this studied. Low level impurity Fe{sup 3+} ions in zeolites complicate interpretation of spectroscopic and catalytic studies of these systems. We focused our efforts on selectively substituting Fe{sup 3+} ions in the frameworks of various zeolites to understand their role in catalytic reactions such as with c-C{sub 3}H{sub 6} and H{sub 2}. These studies led to isomorphous substitution of other ions like B{sup 3+} and their use in isomerization of n-butenes to isobutylene. The third area of research involves the synthesis, characterization and catalysis of a new class of molecular sieve manganese oxide tunnel structure materials.

  17. 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.

  18. Fast reactor fluence dosimetry. Technical progress report, January--November 1976

    International Nuclear Information System (INIS)

    1976-01-01

    The objectives of this task are to: (1) develop and demonstrate the use of 10 B and 6 Li helium accumulation fluence monitors (HAFM's) as a reliable and accurate method of measuring reactor neutron fluence; (2) develop and apply an expanded set of HAFM's which will provide fluence responses in different but overlapping neutron energy ranges; (3) identify, through the precise measurement of spectrum-integrated helium production cross sections, those elements which produce significant helium when used individually or as components of advanced alloys in FTR and LMFBR neutron environments, so that their use might be eliminated, minimized, or controlled; (4) use this information to predict, with confidence, the helium production rate for any alloy or material considered for fast reactor use, and (5) maintain a centralized helium measurements laboratory available to the research community, and upgrade the sample throughput capacity to handle FTR dosimetry requirements

  19. 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

  20. 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

  1. 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

  2. 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

  3. Measurement of residual stress in materials using neutrons. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2005-06-01

    One of the objectives of the IAEA's project on effective utilization of research reactors is to promote the use of the existing research reactors based on their capabilities and is implemented through workshops and technical meetings. Measurement of residual stress is one of the techniques that find wide applications in materials development and testing. The Technical Meeting on Measurement of Residual Stress Using Neutrons was organized to meet this objective. This publication is the outcome of the deliberations during the meeting and the presentations by the participants and is addressed to the research reactor managers, users and designers of facilities for reactor utilization. It will especially benefit those seeking to develop new facilities or upgrade the existing ones to enhance the utilization of their research reactors. Experts with a long experience in developing and using neutron beam instruments in high flux and medium flux research reactors participated in this technical meeting. They presented the design, development and utilization of the facilities at their respective centres and reviewed the current status of the residual stress measurements using neutron beams from research reactors. The sessions included brainstorming on the methodology and data analysis, characterization and standardization of the equipment and identifying the scope for further development. This publication refers to the determination of residual and/or applied stresses in polycrystalline materials using neutron diffraction technique. Stress is developed during the synthesis and use of materials such as alloys and compounds. Measurement of residual stress is essential to improve the quality of synthesized materials and diagnosis of failure and/or reliability of fabricated components. Neutron scattering has played an important role in studying structure and dynamics of condensed matter. Neutron scattering is a non-destructive technique and is useful for testing large samples. The

  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. Thermochemical data acquisition: technical progress report, 1 January - 30 June 1990

    International Nuclear Information System (INIS)

    Bowsher, B.R.; Dickinson, S.; Newland, M.S.; Ogden, J.S.; Potter, P.E.

    1990-07-01

    Thermochemical data are being determined for a number of compounds of fission products and reactor materials. The compounds selected for this experimental study were chosen where thermodynamic data did not exist or were inadequate, based on the assessment and recommendations of a specialists' meeting. The vaporisation behaviour of indium telluride, indium (III) iodide, caesium molybdate, cadmium iodide and a caesium-cadmium-iodine ternary salt have been studied by mass spectrometry and matrix isolation-infrared spectroscopy. The resulting vapour species have been identified, and thermodynamic quantities have been calculated for the following molecules: In 2 Te, In 2 I 6 , InI 3 , InI and Cs 2 MoO 4 . The vaporisation behaviour of Ag-In-Cd control rod alloy has been studied by simultaneous differential thermal analysis and thermogravimetry; observations are consistent with theoretical predictions for the non-ideal Ag-In system. Critical assessment of the cadmium-hydrogen-iodine-oxygen system have also begun. (author)

  6. 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

  7. Recent Progress on the Key Materials and Components for Proton Exchange Membrane Fuel Cells in Vehicle Applications

    Directory of Open Access Journals (Sweden)

    Cheng Wang

    2016-07-01

    Full Text Available Fuel cells are the most clean and efficient power source for vehicles. In particular, proton exchange membrane fuel cells (PEMFCs are the most promising candidate for automobile applications due to their rapid start-up and low-temperature operation. Through extensive global research efforts in the latest decade, the performance of PEMFCs, including energy efficiency, volumetric and mass power density, and low temperature startup ability, have achieved significant breakthroughs. In 2014, fuel cell powered vehicles were introduced into the market by several prominent vehicle companies. However, the low durability and high cost of PEMFC systems are still the main obstacles for large-scale industrialization of this technology. The key materials and components used in PEMFCs greatly affect their durability and cost. In this review, the technical progress of key materials and components for PEMFCs has been summarized and critically discussed, including topics such as the membrane, catalyst layer, gas diffusion layer, and bipolar plate. The development of high-durability processing technologies is also introduced. Finally, this review is concluded with personal perspectives on the future research directions of this area.

  8. 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

  9. Cladding and structural materials. Semi-annual progress report, July 1975--January 1976

    International Nuclear Information System (INIS)

    Claudson, T.T.

    1976-04-01

    Progress on experimental programs and evaluation of results is given for radiation damage studies to LMFBR cladding and structural materials. The primary material being studied is 316 SS in various conditions of cold work and in the welded condition. Tensile, creep, and swelling property data on unirradiated and irradiated 316 SS cladding and duct specimens at various test conditions are provided. The importance of stress on the properties of 316 SS is highlighted. Results on core dosimetry and damage analysis indicate the increasing value of detailed core characterization. 105 figures, 21 tables

  10. Controlled thermonuclear materials technology program. Annual progress report for period ending June 30, 1975

    International Nuclear Information System (INIS)

    Scott, J.L.

    1975-10-01

    Detailed descriptions are given of research progress in the following areas: (1) microstructure of irradiated 316 stainless steel containing high helium concentrations, (2) temperature and fluence limitations for a type 316 stainless steel CTR first wall, (3) swelling and microstructural changes in irradiated vanadium alloys, (4) mechanical properties of irradiated V-20 wt percent Ti, (5) radiation damage calculations, (6) evaluation of irradiation facilities for CTR materials development, (7) surface studies, compatibility studies, (8) magnet development, (9) EPR design support, and (10) the influence of structural materials on fusion-reactor blanket response. (MOW)

  11. Progress of research on plasma facing materials in University of Science and Technology Beijing

    International Nuclear Information System (INIS)

    Ge, Chang-Chun; Zhou, Zhang-Jian; Song, Shu-Xiang; Du, Juan; Zhong, Zhi-Hong

    2007-01-01

    In this paper, we report some new progress on plasma facing materials in University of Science and Technology Beijing (USTB), China. They include fabrication of tungsten coating with ultra-fine grain size by atmosphere plasma spraying; fabrication of tungsten with ultra-fine grain size by a newly developed method named as resistance sintering under ultra-high pressure; using the concept of functionally graded materials to join tungsten to copper based heat sink; joining silicon doped carbon to copper by brazing using a Ti based amorphous filler and direct casting

  12. Cladding and structural materials semi-annual progress report, January 1975--July 1975

    International Nuclear Information System (INIS)

    Claudson, T.T.

    1975-10-01

    Theoretical and experimental programs are in progress to determine the effects of fast neutron radiation on the mechanical properties and swelling of 3C4 and 316SS cladding and duct materials. Detailed specimen characterization and detailed test conditions are required in order to provide the 2 to 5 percent accuracy of results at 1γ. Preliminary swelling tests show that swelling in stressed assemblies is much larger than in unstressed structural components. Correlation of swelling data from high exposure cladding (11.4 at. percent burnup) agrees with previous data and with the current design equation for 20 percent CW 316 stainless steel. Improved techniques for TEM specimen preparation are described along with recent results on crack propagation. Initial results are given for the effects of aging on Inconel 718 base and weld materials. Compilations of these design values of materials properties have been issued in the form of the Nuclear Systems Materials Handbook

  13. Advanced development of PV encapsulants. Semiannual technical progress report, June 30, 1995--December 31, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Holley, W.A. [Springborn Laboratories, Inc., Enfield, CT (United States)

    1996-06-01

    The goals of the NREL PVMaT program are, among others, to reduce module manufacturing costs and improve the quality, and we might add here the reliability, of manufactured PV products. One component critical to the service life of PV modules is the useful life of the EVA resin-based encapsulant which is employed extensively by module manufacturers on a worldwide basis. This pottant has been in commercial use since 1982, and over that time has proven to be a dependable material from the standpoint of production, module fabrication, and end-use. But despite the widespread acceptance of the EVA resin-based A9918 and similar formulations for PV encapsulation, some module producers, end-users, and investigators have reported a yellowing or browning phenomenon with EVA resin-based encapsulants in the field. Wile the incidence of this discoloration/degradation appeared at comparatively few sites at the time that this present program was conceived, it raised serious concern as to the long term reliability of EVA resin-based encapsulation systems. Consequently, under the NREL PVMaT program, Springborn Laboratories proposed a comprehensive study of the EVA aging and discoloration problem and its possible solution(s). During the first year of this program, accelerated U.V. aging methods were surveyed. On careful review of the various types of accelerated U.V. aging equipment available, an Atlas Ci35A Weather-Ometer Xenon Exposure System was selected as appropriate equipment for this work. The following report summarizes how this accelerated aging technique has been used to develop a family of solutions to the discoloration problem, the most significant of which is a series of EVA-based encapsulants which are resistant to discoloration.

  14. 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

  15. Quarterly progress report on the evaluation of critical materials for photovoltaic cells

    Energy Technology Data Exchange (ETDEWEB)

    Watts, R.L.; Pawlewicz, W.W.; Gurwell, W.E.; Jamieson, W.M.; Long, L.W.; Smith, S.A.; Teeter, R.R.

    1979-09-01

    The scope of the activities included in this program are as follows: (1) characterize new and improved photovoltaic cell designs and production processes for subsequent analysis; (2) review or screen these designs for potential material shortages or other constraints; (3) carry out investigations of the probable costs of new sources of materials potentially in short supply, concentrating on gallium and indium; and (4) identify options for coping with or mitigating the problems identified. The methodology and data base used in the CMAP (Critical Material Analysis Program) computer program were developed as part of a broad scale DOE program to review the potential material constraints of all solar programs. The photovoltaic report screened 13 cells in 15 systems and assumed 100% material utilization (process efficiency) in producing the photovoltaic cells. This study emphasizes the availability of cell fabrication feedstock materials and the effects of process efficiencies on material availability by adding characterizations of photovoltaic production processes. This quarterly report presents the results of work with emphasis on Task I, the characterization of photovoltaic cells and their production processes. Task IIA, CMAP Modification, Data Base Development and Operation has been initiated. Task IIB, Review, Integration, Interpretation and Analysis of Screening will begin once the baseline screening has been completed in Task IIA. Work on Task IIIA, the Assessment of Future Costs and Supplies of Gallium and Indium and Task IIIB, Economics of Coal Derived PV Materials have been initiated. Progress and initial results are reported. (WHK)

  16. 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.''

  17. Sintering and dielectric properties of a technical porcelain prepared from economical natural raw materials

    Directory of Open Access Journals (Sweden)

    S. Kasrani

    Full Text Available Abstract In this study, the production of a technical porcelain, for the ceramic dielectric applications by using economical natural raw materials, was investigated. The basic porcelain composition was selected consisting of 30 wt% kaolin, 45 wt% potash-feldspar and 25 wt% quartz. The obtained phases in the sintered samples were investigated by X-ray diffraction, Fourier transform infrared spectroscopy analysis, and scanning electron microscopy images. It has been confirmed by these techniques that the main crystalline phases were quartz and mullite. Dielectric measurements of technical porcelains have been carried out at 1 kHz from room temperature to 200 °C. The dielectric constant, loss factor, dielectric loss tangent, and resistivity of the porcelain sample sintered at 1160 °C were 22-25, 0.32-1.80, 0.006-0.07, and 0.2-9 x 1013 Ω.cm, respectively. The value of dielectric constant was significantly high when compared to that of conventional porcelains which did not exceed generally 9.

  18. Sintering and dielectric properties of a technical porcelain prepared from economical natural raw materials

    Energy Technology Data Exchange (ETDEWEB)

    Kasrani, S.; Harabi, A.; Barama, S.-E.; Foughali, L.; Benhassine, M. T., E-mail: souad478@yahoo.fr, E-mail: harabi52@gmail.com, E-mail: sebarama@usa.com, E-mail: foughali_lazhar@yahoo.fr, E-mail: mtb25dz@gmail.com [Ceramics Lab. Mentouri University of Constantine (Algeria); Aldhayan, D.M., E-mail: aldhayan@ksu.edu.sa [Chemistry Department, Riyadh, King Saud University (Saudi Arabia)

    2016-10-15

    In this study, the production of a technical porcelain, for the ceramic dielectric applications by using economical natural raw materials, was investigated. The basic porcelain composition was selected consisting of 30 wt% kaolin, 45 wt% potash-feldspar and 25 wt% quartz. The obtained phases in the sintered samples were investigated by X-ray diffraction, Fourier transform infrared spectroscopy analysis, and scanning electron microscopy images. It has been confirmed by these techniques that the main crystalline phases were quartz and mullite. Dielectric measurements of technical porcelains have been carried out at 1 kHz from room temperature to 200 °C. The dielectric constant, loss factor, dielectric loss tangent, and resistivity of the porcelain sample sintered at 1160 °C were 22-25, 0.32-1.80, 0.006-0.07, and 0.2-9 x 10{sup 13} Ω.cm, respectively. The value of dielectric constant was significantly high when compared to that of conventional porcelains which did not exceed generally 9. (author)

  19. Sintering and dielectric properties of a technical porcelain prepared from economical natural raw materials

    International Nuclear Information System (INIS)

    Kasrani, S.; Harabi, A.; Barama, S.-E.; Foughali, L.; Benhassine, M. T.; Aldhayan, D.M.

    2016-01-01

    In this study, the production of a technical porcelain, for the ceramic dielectric applications by using economical natural raw materials, was investigated. The basic porcelain composition was selected consisting of 30 wt% kaolin, 45 wt% potash-feldspar and 25 wt% quartz. The obtained phases in the sintered samples were investigated by X-ray diffraction, Fourier transform infrared spectroscopy analysis, and scanning electron microscopy images. It has been confirmed by these techniques that the main crystalline phases were quartz and mullite. Dielectric measurements of technical porcelains have been carried out at 1 kHz from room temperature to 200 °C. The dielectric constant, loss factor, dielectric loss tangent, and resistivity of the porcelain sample sintered at 1160 °C were 22-25, 0.32-1.80, 0.006-0.07, and 0.2-9 x 10 13 Ω.cm, respectively. The value of dielectric constant was significantly high when compared to that of conventional porcelains which did not exceed generally 9. (author)

  20. Analysis of Technical Status on the Application of Cementitious Materials for Radwaste Repository

    International Nuclear Information System (INIS)

    Kim, Jin Seop; Kwon, Sang Ki; Cho, Won Jin

    2008-12-01

    In this report, technical status on the application of cementitious materials and related research trends in Sweden, Switzerland and Japan etc. is listed based on the example of ONKALO in Finland. SKB and POSIVA have defined a pH limit ≤ 11 for cement grout leachates. To attain this pH, blending agents must comprise at least 50 wt % of dry materials. Because low pH cement has little, or no free portlandite, the cement consists predominantly of calcium silicate hydrate(CSH) gel with a Ca/Si ratio ≤ 0.8(Savage D. 2007). Silica fume as a blending agent is considered to be most promising for repository low-pH grouts. When adding silica fume to enhance cement quality, it demands high water content in cement paste. Then it is necessary to use additives such as superplasticiser to improve the workability of low-pH cement. Posiva, SKB and NUMO co-operated in developing low-pH grouts for deep repositories 2002-2005. Additionally, it is needed to study more about long-term performance characteristics, interaction of bentonite buffer material with high pH plume, influence on the migration/sorption of radionuclides and their performance numerical modeling. In this regards, international co-research projects such as ESDRED and IAEA CRP are being actively performed

  1. Technical and management challenges associated with structural materials degradation in nuclear reactors in the future

    International Nuclear Information System (INIS)

    Ford, F.P.

    2007-01-01

    There are active plans worldwide to increase nuclear power production by significant amounts. In the near term (i.e. by 2020) this will be accomplished by, (a) increasing the power output of the existing reactors and extending their life, and by, (b) constructing new reactors that are very similar to the current water-cooled designs. Beyond 2025-2030, it is possible that new reactors (i.e. the 'GEN IV' designs) will be very different from those currently in service. A full discussion of the technical and management concerns associated with materials degradation that might arise over the next 40 years would need to address a wide range of topics. Quite apart from discussing the structural integrity issues for the materials of construction and the fuel cladding, the debate would also need to cover, for example, fuel resources and the associated issues of fuel cycle management and waste disposal, manufacturing capacity, inspection capabilities, human reliability, etc., since these all impact to one degree or another on the choice of material and the reactor operating conditions. For brevity, the scope of this article is confined to the integrity of the materials of construction for passive components in the current water-cooled reactors and the evolutionary designs (which will dominate the near term new constructions), and the very different GEN IV reactor designs. In all cases the operating environments will be more aggressive than currently encountered. For instance, the concerns for flow accelerated corrosion and flow-induced vibration will be increased under extended power uprate conditions for the current water-cooled reactors. Of greater concern, the design life will be at least 60 years for all of the new reactors and for those current reactors operating with extended licenses. This automatically presents challenges with regard to managing both irradiation damage in metallic and non-metallic materials of construction, and environmentally assisted cracking. This

  2. Synthesis and Characterization of High Aluminum Zeolite X from Technical Grade Materials

    Directory of Open Access Journals (Sweden)

    Seyed Kamal Masoudian

    2013-06-01

    Full Text Available Zeolites are widely used as ion exchangers, adsorbents, separation materials and catalyst due to their well-tailored and highly-reproducible structures; therefore, the synthesis of zeolite from low grade resources can be interested. In the present work, high aluminum zeolite X was prepared from mixing technical grade sodium aluminate and sodium silicate solutions at temperatures between 70°C and 100°C. The synthesized zeolite X was characterized by SEM and X-ray methods according to ASTM standard procedures. The results showed that aging of the synthesis medium at the room temperature considerably increased the selectivity of zeolite X formation. On the other hand, high temperature of reaction mixture during crystallization formed zeolite A in the product; therefore, it decreased the purity of zeolite X. In addition, it was found that increasing H2O/Na2O and decreasing Na2O/SiO2 molar ratios in the reaction mixture resulted product with higher purity. © 2013 BCREC UNDIP. All rights reservedReceived: 7th January 2013; Revised: 7th April 2013; Accepted: 19th April 2013[How to Cite: Masoudian, S. K., Sadighi, S., Abbasi, A. (2013. Synthesis and Characterization of High Alu-minum Zeolite X from Technical Grade Materials. Bulletin of Chemical Reaction Engineering & Catalysis, 8 (1: 54-60. (doi:10.9767/bcrec.8.1.4321.54-60][Permalink/DOI: http://dx.doi.org/10.9767/bcrec.8.1.4321.54-60] | View in  |

  3. Technical considerations for detection of and response to illicit trafficking in radioactive materials

    International Nuclear Information System (INIS)

    Duftschmid, K.E.; Arlt, R.; Cunningham, J.; Gayral, J.P.; Kravchenko, N.; Smith, D.; York, R.

    2001-01-01

    Full text: The need for guidance and recommendations explicitly directed to the problem of illicit trafficking in nuclear materials and other radioactive sources was raised by the IAEA Director General at the IAEA General Conference in December 1994, and measures were agreed by the IAEA Board of Governors in March 1995. Measures that might be taken to prevent, detect, and respond to illicit trafficking will be common for all radioactive materials, including nuclear materials. However, nuclear materials are, or should be, subject also to safeguards for nuclear non-proliferation purposes and to physical protection to prevent diversion. The IAEA has established close co-operation with intergovernmental and non-governmental organizations, in particular the World Customs Organization (WCO) and INTERPOL to conduct joint studies, meetings and training programs to support Member States in their border control activities. Within this programme technical information has been derived on requirements and methods to detect and respond to events involving inadvertent movement of and illicit trafficking in radioactive materials. The paper summarises the most important results and the experience obtained in this field. Concerning 'detection' information on strategy of detection, selection of an investigation level, techniques for radiation monitoring at borders, verification of alarms, search techniques and identification of radionuclides has been developed. This includes recommended minimum requirements for monitoring equipment, derived from the results of an extended international pilot study on border monitoring equipment ITRAP, conducted by IAEA in co-operation with the Austrian government. In order to discover illicit trafficking or inadvertent movement in radioactive materials, the following steps are required: detection of any abnormal radiation level, verification of such detection, localisation of the origin of the radiation, radiation safety measurement, and

  4. Recent progress in the development of anode materials for solid oxide fuel cells

    Energy Technology Data Exchange (ETDEWEB)

    Cowin, Peter I.; Petit, Christophe T.G.; Lan, Rong; Tao, Shanwen [Department of Chemical and Process Engineering, University of Strathclyde, Glasgow G1 1XJ (United Kingdom); Irvine, John T.S. [School of Chemistry, University of St Andrews, St Andrews, Fife KY16 9ST (United Kingdom)

    2011-05-15

    The field of research into solid oxide fuel cell (SOFC) anode materials has been rapidly moving forward. In the four years since the last in-depth review significant advancements have been made in the reduction of the operating temperature and improvement of the performance of SOFCs. This progress report examines the developments in the field and looks to draw conclusions and inspiration from this research. A brief introduction is given to the field, followed by an overview of the principal previous materials. A detailed analysis of the developments of the last 4 years is given using a selection of the available literature, concentrating on metal-fluorite cermets and perovskite-based materials. This is followed by a consideration of alternate fuels for use in SOFCs and their associated problems and a short discussion on the effect of synthesis method on anode performance. The concluding remarks compile the significant developments in the field along with a consideration of the promise of future research. The recent progress in the development of anode materials for SOFCs based on oxygen ion conducting electrolytes is reviewed. (Copyright copyright 2011 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

  5. 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)

  6. 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.

  7. The progress of the electrode materials development for lithium ion battery

    International Nuclear Information System (INIS)

    Kang Kai; Dai Shouhui; Wan Yuhua

    2001-01-01

    The structure and the charge-discharge principle of Li-ion battery are briefly discussed; the progress of electrode materials for Li-ion battery is reviewed in detail. Graphite has found wide applications in commercial Li-ion batteries, however, the hard carbon, especially the carbon with hydrogen is the most promising anode material for Li-ion battery owing to its high capacity, which has now become hot spot of investigation. Following the LiCoO 2 , LiMn 2 O 4 spinel compound becomes the most powerful contestant. On the basis of the authors' results, the synthesis methods of LiMn 2 O 4 and its characterizations are compared. Moreover, the structural properties of intercalation electrode materials that are related to the rechargeable capacity and stability during cycling of lithium ions are also discussed

  8. 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

  9. Science of materials. Progress report, July 1, 1977--June 30, 1978

    Energy Technology Data Exchange (ETDEWEB)

    1978-04-01

    Progress is reported in research which includes studies of the deformation, stress corrosion and fracture of alloys and geologic materials with emphasis on hydrogen embrittlement of metals; the mechanism of heat transfer across interfaces; catalytic properties of surfaces; and erosion of surfaces by fluid suspended particles. The structure of liquids, polymers and disordered solids is under investigation with emphasis on ionic conduction, phase transitions and radiation damage. Ferro- and pyroelectric materials with potential for solar energy applications are under development. The study of optical properties includes the mechanism of luminescence and new semiconductor materials for photovoltaic devices. The electronic properties of crystals are the subject of a continued effort to resolve current problems of magnetic behavior and photon-solid interactions. Specific quantum properties of matter are explored with emphasis on superconductivity, diffusion of hydrogen in metals and the properties of solid helium.

  10. Progress in understanding the mechanical behavior of pressure-vessel materials at elevated temperatures

    International Nuclear Information System (INIS)

    Swindeman, R.W.; Brinkman, C.R.

    1981-01-01

    Progress during the 1970's on the production of high-temperature mechanical properties data for pressure vessel materials was reviewed. The direction of the research was toward satisfying new data requirements to implement advances in high-temperature inelastic design methods. To meet these needs, servo-controlled testing machines and high-resolution extensometry were developed to gain more information on the essential behavioral features of high-temperature alloys. The similarities and differences in the mechanical response of various pressure vessel materials were identified. High-temperature pressure vessel materials that have received the most attention included Type 304 stainless steel, Type 316 stainless steel, 2 1/4 Cr-1 Mo steel, alloy 800H, and Hastelloy X

  11. Forty-Second Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Working Material

    International Nuclear Information System (INIS)

    2009-01-01

    The objectives of the meeting were to: - Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); - Review the progress since the 41st TWG-FR Annual Meeting, including the status of the actions; - Consider topical technical meetings meeting arrangements for 2009, 2010, 2011 and beyond; - Review the IAEA’s ongoing information exchange and coordinated research activities in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives; - Discuss future joint activities in view of IAEA’s Programme and Budget Cycles beyond 2010-2011

  12. 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.

  13. 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.

  14. Review on recent progress of nanostructured anode materials for Li-ion batteries

    KAUST Repository

    Goriparti, Subrahmanyam

    2014-07-01

    This review highlights the recent research advances in active nanostructured anode materials for the next generation of Li-ion batteries (LIBs). In fact, in order to address both energy and power demands of secondary LIBs for future energy storage applications, it is required the development of innovative kinds of electrodes. Nanostructured materials based on carbon, metal/semiconductor, metal oxides and metal phosphides/nitrides/sulfides show a variety of admirable properties for LIBs applications such as high surface area, low diffusion distance, high electrical and ionic conductivity. Therefore, nanosized active materials are extremely promising for bridging the gap towards the realization of the next generation of LIBs with high reversible capacities, increased power capability, long cycling stability and free from safety concerns. In this review, anode materials are classified, depending on their electrochemical reaction with lithium, into three groups: intercalation/de-intercalation, alloy/de-alloy and conversion materials. Furthermore, the effect of nanoscale size and morphology on the electrochemical performance is presented. Synthesis of the nanostructures, lithium battery performance and electrode reaction mechanisms are also discussed. To conclude, the main aim of this review is to provide an organic outline of the wide range of recent research progresses and perspectives on nanosized active anode materials for future LIBs.

  15. Review on recent progress of nanostructured anode materials for Li-ion batteries

    KAUST Repository

    Goriparti, Subrahmanyam; Miele, Ermanno; De Angelis, Francesco; Di Fabrizio, Enzo M.; Proietti Zaccaria, Remo; Capiglia, Claudio

    2014-01-01

    This review highlights the recent research advances in active nanostructured anode materials for the next generation of Li-ion batteries (LIBs). In fact, in order to address both energy and power demands of secondary LIBs for future energy storage applications, it is required the development of innovative kinds of electrodes. Nanostructured materials based on carbon, metal/semiconductor, metal oxides and metal phosphides/nitrides/sulfides show a variety of admirable properties for LIBs applications such as high surface area, low diffusion distance, high electrical and ionic conductivity. Therefore, nanosized active materials are extremely promising for bridging the gap towards the realization of the next generation of LIBs with high reversible capacities, increased power capability, long cycling stability and free from safety concerns. In this review, anode materials are classified, depending on their electrochemical reaction with lithium, into three groups: intercalation/de-intercalation, alloy/de-alloy and conversion materials. Furthermore, the effect of nanoscale size and morphology on the electrochemical performance is presented. Synthesis of the nanostructures, lithium battery performance and electrode reaction mechanisms are also discussed. To conclude, the main aim of this review is to provide an organic outline of the wide range of recent research progresses and perspectives on nanosized active anode materials for future LIBs.

  16. Using constitutive equation gap method for identification of elastic material parameters: Technical insights and illustrations

    KAUST Repository

    Florentin, É ric; Lubineau, Gilles

    2011-01-01

    based on experimental full-field measurement. From a technical point of view, this approach requires to quickly describe a space of statically admissible stress fields. We present here the technical insights, inspired from previous works in verification

  17. 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

  18. 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

  19. 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.

  20. 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