WorldWideScience

Sample records for fuels research laboratory

  1. Fuel Combustion Laboratory | Transportation Research | NREL

    Science.gov (United States)

    Fuel Combustion Laboratory Fuel Combustion Laboratory NREL's Fuel Combustion Laboratory focuses on designs, using both today's technology and future advanced combustion concepts. This lab supports the combustion chamber platform for fuel ignition kinetics research, was acquired to expand the lab's

  2. Fuels Processing Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — NETL’s Fuels Processing Laboratory in Morgantown, WV, provides researchers with the equipment they need to thoroughly explore the catalytic issues associated with...

  3. DISMANTLING OF THE FUEL CELL LABORATORY AT RESEARCH CENTRE JUELICH

    International Nuclear Information System (INIS)

    Stahn, B.; Matela, K.; Bensch, D.; Ambos, Frank

    2003-01-01

    The fuel cell laboratory was constructed in three phases and taken into operation in the years 1962 to 1966. The last experimental work was carried out in 1996. After all cell internals had been disassembled, the fuel cell laboratory was transferred to shutdown operation in 1997. Three cell complexes, which differed, in particular, by the type of shielding (lead, cast steel, concrete), were available until then for activities at nuclear components. After approval by the regulatory authority, the actual dismantling of the fuel cell laboratory started in March 2000. The BZ I laboratory area consisted of 7 cells with lead shieldings of 100 to 250 mm thickness. This area was dismantled from April to September 2000. Among other things, approx. 30,000 lead bricks with a total weight of approx. 300 Mg were dismantled and disposed of. The BZ III laboratory area essentially consisted of cells with concrete shieldings of 1200 to 1400 mm thickness. The dismantling of this area started in the fir st half of 2001 and was completed in November 2002. Among other things, approx. 900 Mg of concrete was dismantled and disposed of. Since more than 90 % of the dismantled materials was measurable for clearance, various clearance measurement devices were used during dismantling. The BZ II laboratory area essentially consists of cells with cast steel shieldings of 400 to 460 mm thickness. In September 2002 it was decided to continue using this laboratory area for future tasks. The dismantling of the fuel cell laboratory was thus completed. After appropriate refurbishment, the fuel cell laboratory will probably take up operation again in late 2003

  4. Nuclear fuel cycle safety research at Sandia Laboratories

    International Nuclear Information System (INIS)

    Ericson, D.M. Jr.

    1978-11-01

    This paper provides a brief introduction to Sandia Laboratories and an overview of Nuclear Regulatory Commission sponsored safety research with particular emphasis on light water reactor related activities. Several experimental and analytical programs are highlighted and the range of activities of a typical staff member illustrated

  5. Safety analysis report of uranium dioxide fuel laboratory, Nuclear Research Centre Inchas, Egypt

    International Nuclear Information System (INIS)

    Abdel-Azim, M.S.; Abdel-Halim, A.

    1987-07-01

    In the Nuclear Research Center Inchas a uranium dioxide fuel laboratory is planned and built by the AEA Cairo (Atomic Energy Authority). The layout of this fuel lab and the programmatical contents are subject to the bilaterial cooperation between Egypt and the Federal Republic of Germany. In this report the safety analysis as basic items for the approval procedure are started in detail. (orig.) [de

  6. GSPEL - Fuel Cell Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — The Fuel Cell Lab (FCL)Established to investigate, integrate, testand verifyperformance and technology readiness offuel cell systems and fuel reformers for use with...

  7. Remote handling equipment for laboratory research of fuel reprocessing in Nuclear Research Institute at Rez

    International Nuclear Information System (INIS)

    Fidler, J.; Novy, P.; Kyrs, M.

    1985-04-01

    Laboratory installations were developed for two nuclear fuel reprocessing methods, viz., the solvent extraction process and the fluoride volatility process. The apparatus for solvent extraction reprocessing consists of a pneumatically driven rod-chopper, a dissolver, mixer-settler extractors, an automatic fire extinguishing device and other components and it was tested using irradiated uranium. The technological line for the fluoride volatility process consists of a fluorimater, condensers, sorption columns with NaF pellets and a distillation column for the separation of volatile fluorides from UF 6 . The line has not yet been tested using irradiated fuel. Some features of the remote handling equipment of both installations are briefly described. (author)

  8. Fuel safety research 1999

    Energy Technology Data Exchange (ETDEWEB)

    Uetsuka, Hiroshi (ed.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2000-07-01

    In April 1999, the Fuel Safety Research Laboratory was newly established as a result of reorganization of the Nuclear Safety Research Center, JAERI. The laboratory was organized by combining three laboratories, the Reactivity Accident Laboratory, the Fuel Reliability Laboratory, and a part of the Sever Accident Research Laboratory. Consequently, the Fuel Safety Research Laboratory is now in charge of all the fuel safety research in JAERI. Various types of experimental and analytical researches are conducted in the laboratory by using the unique facilities such as the Nuclear Safety Research Reactor (NSRR), the Japan Material Testing Reactor (JMTR), the Japan Research Reactor 3 (JRR-3) and hot cells in JAERI. The laboratory consists of five research groups corresponding to each research fields. They are; (a) Research group of fuel behavior under the reactivity initiated accident conditions (RIA group). (b) Research group of fuel behavior under the loss-of-coolant accident conditions (LOCA group). (c) Research group of fuel behavior under the normal operation conditions (JMTR/BOCA group). (d) Research group of fuel behavior analysis (FEMAXI group). (e) Research group of FP release/transport behavior from irradiated fuel (VEGA group). This report summarizes the outline of research activities and major outcomes of the research executed in 1999 in the Fuel Safety Research Laboratory. (author)

  9. Quality Assurance in Nuclear Fuel Research at the Laboratory of High- and Medium-level Activity at SCK-CEN

    Energy Technology Data Exchange (ETDEWEB)

    Sannen, L.; Gys, A.; Verwerft, M

    1999-10-01

    Quality assurance in nuclear fuel research demands specific calibration and validation methodologies. Indeed the analytical experiments in hot-cells on highly radioactive objects are non-standard and many times unique. The standards and validation methods developed for and applied to the main nuclear fuel research experiments in the hot laboratories of the Belgian Nuclear Research Centre SCK-CEN are outlined.

  10. Quality Assurance in Nuclear Fuel Research at the Laboratory of High- and Medium-level Activity at SCK-CEN

    International Nuclear Information System (INIS)

    Sannen, L.; Gys, A.; Verwerft, M.

    1999-10-01

    Quality assurance in nuclear fuel research demands specific calibration and validation methodologies. Indeed the analytical experiments in hot-cells on highly radioactive objects are non-standard and many times unique. The standards and validation methods developed for and applied to the main nuclear fuel research experiments in the hot laboratories of the Belgian Nuclear Research Centre SCK-CEN are outlined

  11. Fuel safety research 2000

    Energy Technology Data Exchange (ETDEWEB)

    Uetsuka, Hiroshi (ed.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    In April 1999, the Fuel Safety Research Laboratory was newly established as a part of reorganization of the Nuclear Safety Research Center, JAERI. The new laboratory was organized by combining three pre-existing laboratories, Reactivity Accident Laboratory, Fuel Reliability Laboratory, and a part of Severe Accident Research Laboratory. The Fuel Safety Research Laboratory becomes to be in charge of all fuel safety research in JAERI. Various experimental and analytical researches are conducted in the laboratory by using the unique facilities such as the Nuclear Safety Research Reactor (NSRR), the Japan Material Testing Reactor (JMTR), the Japan Research Reactor 3 (JRR-3) and hot cells in JAERI. The laboratory consists of following five research groups corresponding to each research fields; (a) Research group of fuel behavior under the reactivity initiated accident conditions (RIA group). (b) Research group of fuel behavior under the loss-of-coolant accident conditions (LOCA group). (c) Research group of fuel behavior under the normal operation conditions (JMTR/BOCA group). (d) Research group of fuel behavior analysis (FEMAXI group). (e) Research group of FP release/transport behavior from irradiated fuel (VEGA group). The research activities in year 2000 produced many important data and information. They are, for example, failure of high burnup BWR fuel rod under RIA conditions, data on the behavior of hydrided Zircaloy cladding under LOCA conditions and FP release data from VEGA experiments at very high temperature/pressure condition. This report summarizes the outline of research activities and major outcomes of the research executed in 2000 in the Fuel Safety Research Laboratory. (author)

  12. Solid Oxide Fuel Cell Experimental Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — NETL’s Solid Oxide Fuel Cell Experimental Laboratory in Morgantown, WV, gives researchers access to models and simulations that predict how solid oxide fuel cells...

  13. Spent fuel reprocessing and minor actinide partitioning safety related research at the UK National Nuclear Laboratory

    International Nuclear Information System (INIS)

    Carrott, Michael; Flint, Lauren; Gregson, Colin; Griffiths, Tamara; Hodgson, Zara; Maher, Chris; Mason, Chris; McLachlan, Fiona; Orr, Robin; Reilly, Stacey; Rhodes, Chris; Sarsfield, Mark; Sims, Howard; Shepherd, Daniel; Taylor, Robin; Webb, Kevin; Woodall, Sean; Woodhead, David

    2015-01-01

    The development of advanced separation processes for spent nuclear fuel reprocessing and minor actinide recycling is an essential component of international R and D programmes aimed at closing the nuclear fuel cycle around the middle of this century. While both aqueous and pyrochemical processes are under consideration internationally, neither option will gain broad acceptance without significant advances in process safety, waste minimisation, environmental impact and proliferation resistance; at least when compared to current reprocessing technologies. The UK National Nuclear Laboratory (NNL) is developing flowsheets for innovative aqueous separation processes. These include advanced PUREX options (i.e. processes using tributyl phosphate as the extractant for uranium, plutonium and possibly neptunium recovery) and GANEX (grouped actinide extraction) type processes that use diglycolamide based extractants to co-extract all transuranic actinides. At NNL, development of the flowsheets is closely linked to research on process safety, since this is essential for assessing prospects for future industrialisation and deployment. Within this context, NNL is part of European 7. Framework projects 'ASGARD' and 'SACSESS'. Key topics under investigation include: hydrogen generation from aqueous and solvent phases; decomposition of aqueous phase ligands used in separations prior to product finishing and recycle of nitric acid; dissolution of carbide fuels including management of organics generated. Additionally, there is a strong focus on use of predictive process modelling to assess flowsheet sensitivities as well as engineering design and global hazard assessment of these new processes. (authors)

  14. Fuel safety research 2001

    Energy Technology Data Exchange (ETDEWEB)

    Uetsuka, Hiroshi (ed.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-11-01

    The Fuel Safety Research Laboratory is in charge of research activity which covers almost research items related to fuel safety of water reactor in JAERI. Various types of experimental and analytical researches are being conducted by using some unique facilities such as the Nuclear Safety Research Reactor (NSRR), the Japan Material Testing Reactor (JMTR), the Japan Research Reactor 3 (JRR-3) and the Reactor Fuel Examination Facility (RFEF) of JAERI. The research to confirm the safety of high burn-up fuel and MOX fuel under accident conditions is the most important item among them. The laboratory consists of following five research groups corresponding to each research fields; Research group of fuel behavior under the reactivity initiated accident conditions (RIA group). Research group of fuel behavior under the loss-of-coolant accident conditions (LOCA group). Research group of fuel behavior under the normal operation conditions (JMTR/BOCA group). Research group of fuel behavior analysis (FEMAXI group). Research group of radionuclides release and transport behavior from irradiated fuel under severe accident conditions (VEGA group). The research conducted in the year 2001 produced many important data and information. They are, for example, the fuel behavior data under BWR power oscillation conditions in the NSRR, the data on failure-bearing capability of hydrided cladding under LOCA conditions and the FP release data at very high temperature in steam which simulate the reactor core condition during severe accidents. This report summarizes the outline of research activities and major outcomes of the research executed in 2001 in the Fuel Safety Research Laboratory. (author)

  15. Laboratory Directed Research and Development (LDRD) on Mono-uranium Nitride Fuel Development for SSTAR and Space Applications

    International Nuclear Information System (INIS)

    Choi, J; Ebbinghaus, B; Meiers, T; Ahn, J

    2006-01-01

    The US National Energy Policy of 2001 advocated the development of advanced fuel and fuel cycle technologies that are cleaner, more efficient, less waste-intensive, and more proliferation resistant. The need for advanced fuel development is emphasized in on-going DOE-supported programs, e.g., Global Nuclear Energy Initiative (GNEI), Advanced Fuel Cycle Initiative (AFCI), and GEN-IV Technology Development. The Directorates of Energy and Environment (E and E) and Chemistry and Material Sciences (C and MS) at Lawrence Livermore National Laboratory (LLNL) are interested in advanced fuel research and manufacturing using its multi-disciplinary capability and facilities to support a design concept of a small, secure, transportable, and autonomous reactor (SSTAR). The E and E and C and MS Directorates co-sponsored this Laboratory Directed Research and Development (LDRD) Project on Mono-Uranium Nitride Fuel Development for SSTAR and Space Applications. In fact, three out of the six GEN-IV reactor concepts consider using the nitride-based fuel, as shown in Table 1. SSTAR is a liquid-metal cooled, fast reactor. It uses nitride fuel in a sealed reactor vessel that could be shipped to the user and returned to the supplier having never been opened in its long operating lifetime. This sealed reactor concept envisions no fuel refueling nor on-site storage of spent fuel, and as a result, can greatly enhance proliferation resistance. However, the requirement for a sealed, long-life core imposes great challenges to research and development of the nitride fuel and its cladding. Cladding is an important interface between the fuel and coolant and a barrier to prevent fission gas release during normal and accidental conditions. In fabricating the nitride fuel rods and assemblies, the cladding material should be selected based on its the coolant-side corrosion properties, the chemical/physical interaction with the nitride fuel, as well as their thermal and neutronic properties. The US

  16. Fuel Cell Development and Test Laboratory | Energy Systems Integration

    Science.gov (United States)

    Facility | NREL Fuel Cell Development and Test Laboratory Fuel Cell Development and Test Laboratory The Energy System Integration Facility's Fuel Cell Development and Test Laboratory supports fuel cell research and development projects through in-situ fuel cell testing. Photo of a researcher running

  17. The laboratory test rig with miniature jet engine to research aviation fuels combustion process

    Directory of Open Access Journals (Sweden)

    Gawron Bartosz

    2015-12-01

    Full Text Available This article presents laboratory test rig with a miniature turbojet engine (MiniJETRig – Miniature Jet Engine Test Rig, that was built in the Air Force Institute of Technology. The test rig has been developed for research and development works aimed at modelling and investigating processes and phenomena occurring in full scale jet engines. In the article construction of a test rig is described, with a brief discussion on the functionality of each of its main components. Additionally examples of measurement results obtained during the realization of the initial tests have been included, presenting the capabilities of the test rig.

  18. Research Combustion Laboratory (RCL)

    Data.gov (United States)

    Federal Laboratory Consortium — The Research Combustion Laboratory (RCL) develops aerospace propulsion technology by performing tests on propulsion components and materials. Altitudes up to 137,000...

  19. Combustion Research Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — The Combustion Research Laboratory facilitates the development of new combustion systems or improves the operation of existing systems to meet the Army's mission for...

  20. Fuel Cell Manufacturing Research and Development | Hydrogen and Fuel Cells

    Science.gov (United States)

    | NREL Fuel Cell Manufacturing Research and Development Fuel Cell Manufacturing Research and Development NREL's fuel cell manufacturing R&D focuses on improving quality-inspection practices for high costs. A researcher monitoring web-line equipment in the Manufacturing Laboratory Many fuel cell

  1. Aquatic Research Laboratory (ARL)

    Data.gov (United States)

    Federal Laboratory Consortium — Columbia River and groundwater well water sources are delivered to the Aquatic Research Laboratory (ARL), where these resources are used to conduct research on fish...

  2. Dealing with Historical Discrepancies: The Recovery of National Research Experiment (NRX) Reactor Fuel Rods at Chalk River Laboratories (CRL) - 13324

    International Nuclear Information System (INIS)

    Vickerd, Meggan

    2013-01-01

    Following the 1952 National Research Experiment (NRX) Reactor accident, fuel rods which had short irradiation histories were 'temporarily' buried in wooden boxes at the 'disposal grounds' during the cleanup effort. The Nuclear Legacy Liabilities Program (NLLP), funded by Natural Resources Canada (NRCan), strategically retrieves legacy waste and restores lands affected by Atomic Energy of Canada Limited (AECL) early operations. Thus under this program the recovery of still buried NRX reactor fuel rods and their relocation to modern fuel storage was identified as a priority. A suspect inventory of NRX fuels was compiled from historical records and various research activities. Site characterization in 2005 verified the physical location of the fuel rods and determined the wooden boxes they were buried in had degraded such that the fuel rods were in direct contact with the soil. The fuel rods were recovered and transferred to a modern fuel storage facility in 2007. Recovered identification tags and measured radiation fields were used to identify the inventory of these fuels. During the retrieval activity, a discrepancy was discovered between the anticipated number of fuel rods and the number found during the retrieval. A total of 32 fuel rods and cans of cut end pieces were recovered from the specified site, which was greater than the anticipated 19 fuel rods and cans. This discovery delayed the completion of the project, increased the associated costs, and required more than anticipated storage space in the modern fuel storage facility. A number of lessons learned were identified following completion of this project, the most significant of which was the potential for discrepancies within the historical records. Historical discrepancies are more likely to be resolved by comprehensive historical record searches and site characterizations. It was also recommended that a complete review of the wastes generated, and the total affected lands as a result of this historic

  3. Review of Transient Fuel Test Results at Sandia National Laboratories and the Potential for Future Fast Reactor Fuel Transient Testing in the Annular Core Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Wright, Steven A.; Pickard, Paul S.; Parma, Edward J.; Vernon, Milton E.; Kelly, John; Tikare, Veena [Sandia National Laboratories, Org 6872 MS-1146, PO Box 5800 Albuquerque, New Mexico 87185 (United States)

    2009-06-15

    Reactor driven transient tests of fast reactor fuels may be required to support the development and certification of new fuels for Fast Reactors. The results of the transient fuel tests will likely be needed to support licensing and to provide validation data to support the safety case for a variety of proposed fast fuel types and reactors. In general reactor driven transient tests are used to identify basic phenomenology during reactor transients and to determine the fuel performance limits and margins to failure during design basis accidents such as loss of flow, loss of heat sink, and reactivity insertion accidents. This paper provides a summary description of the previous Sandia Fuel Disruption and Transient Axial Relocation tests that were performed in the Annular Core Research Reactor (ACRR) for the U.S. Nuclear Regulatory Commission almost 25 years ago. These tests consisted of a number of capsule tests and flowing gas tests that used fission heating to disrupt fresh and irradiated MOX fuel. The behavior of the fuel disruption, the generation of aerosols and the melting and relocation of fuel and cladding was recorded on high speed cinematography. This paper will present videos of the fuel disruption that was observed in these tests which reveal stark differences in fuel behavior between fresh and irradiated fuel. Even though these tests were performed over 25 years ago, their results are still relevant to today's reactor designs. These types of transient tests are again being considered by the Advanced Fuel Cycle Initiative to support the Global Nuclear Energy Partnership because of the need to perform tests on metal fuels and transuranic fuels. Because the Annular Core Research Reactor is the only transient test facility available within the US, a brief summary of Sandia's continued capability to perform these tests in the ACRR will also be provided. (authors)

  4. Energy Materials Research Laboratory (EMRL)

    Data.gov (United States)

    Federal Laboratory Consortium — The Energy Materials Research Laboratory at the Savannah River National Laboratory (SRNL) creates a cross-disciplinary laboratory facility that lends itself to the...

  5. Simula Research Laboratory

    CERN Document Server

    Tveito, Aslak

    2010-01-01

    The Simula Research Laboratory, located just outside Oslo in Norway, is rightly famed as a highly successful research facility, despite being, at only eight years old, a very young institution. This fascinating book tells the history of Simula, detailing the culture and values that have been the guiding principles of the laboratory throughout its existence. Dedicated to tackling scientific challenges of genuine social importance, the laboratory undertakes important research with long-term implications in networks, computing and software engineering, including specialist work in biomedical comp

  6. Fuel cells: Trends in research and applications

    Science.gov (United States)

    Appleby, A. J.

    Various aspects of fuel cells are discussed. The subjects addressed include: fuel cells for electric power production; phosphoric acid fuel cells; long-term testing of an air-cooled 2.5 kW PAFC stack in Italy; status of fuel cell research and technology in the Netherlands, Bulgaria, PRC, UK, Sweden, India, Japan, and Brazil; fuel cells from the manufacturer's viewpoint; and fuel cells using biomass-derived fuels. Also examined are: solid oxide electrolye fuel cells; aluminum-air batteries with neutral chloride electrolyte; materials research for advanced solid-state fuel cells at the Energy Research Laboratory in Denmark; molten carbonate fuel cells; the impact of the Siemens program; fuel cells at Sorapec; impact of fuel cells on the electric power generation systems in industrial and developing countries; and application of fuel cells to large vehicles.

  7. Fuels and Petroleum, Oil & Lubricants (POL) Laboratories

    Data.gov (United States)

    Federal Laboratory Consortium — The Fuels and Lubricants Technology Team operates and maintains the Fuels and POL Labs at TARDEC. Lab experts adhere to standardized American Society for Testing and...

  8. NASA's Propulsion Research Laboratory

    Science.gov (United States)

    2004-01-01

    The grand opening of NASA's new, world-class laboratory for research into future space transportation technologies located at the Marshall Space Flight Center (MSFC) in Huntsville, Alabama, took place in July 2004. The state-of-the-art Propulsion Research Laboratory (PRL) serves as a leading national resource for advanced space propulsion research. Its purpose is to conduct research that will lead to the creation and development of innovative propulsion technologies for space exploration. The facility is the epicenter of the effort to move the U.S. space program beyond the confines of conventional chemical propulsion into an era of greatly improved access to space and rapid transit throughout the solar system. The laboratory is designed to accommodate researchers from across the United States, including scientists and engineers from NASA, the Department of Defense, the Department of Energy, universities, and industry. The facility, with 66,000 square feet of useable laboratory space, features a high degree of experimental capability. Its flexibility allows it to address a broad range of propulsion technologies and concepts, such as plasma, electromagnetic, thermodynamic, and propellant propulsion. An important area of emphasis is the development and utilization of advanced energy sources, including highly energetic chemical reactions, solar energy, and processes based on fission, fusion, and antimatter. The Propulsion Research Laboratory is vital for developing the advanced propulsion technologies needed to open up the space frontier, and sets the stage of research that could revolutionize space transportation for a broad range of applications.

  9. Fuel Cell Research

    Energy Technology Data Exchange (ETDEWEB)

    Weber, Peter M. [Brown University

    2014-03-30

    Executive Summary In conjunction with the Brown Energy Initiative, research Projects selected for the fuel cell research grant were selected on the following criteria: They should be fundamental research that has the potential to significantly impact the nation’s energy infrastructure. They should be scientifically exciting and sound. They should synthesize new materials, lead to greater insights, explore new phenomena, or design new devices or processes that are of relevance to solving the energy problems. They involve top-caliper senior scientists with a record of accomplishment, or junior faculty with outstanding promise of achievement. They should promise to yield at least preliminary results within the given funding period, which would warrant further research development. They should fit into the overall mission of the Brown Energy Initiative, and the investigators should contribute as partners to an intellectually stimulating environment focused on energy science. Based on these criteria, fourteen faculty across three disciplines (Chemistry, Physics and Engineering) and the Charles Stark Draper Laboratory were selected to participate in this effort.1 In total, there were 30 people supported, at some level, on these projects. This report highlights the findings and research outcomes of the participating researchers.

  10. Green Building Research Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Sailor, David Jean [Portland State Univ., Portland, OR (United States)

    2013-12-29

    This project provided support to the Green Building Research Laboratory at Portland State University (PSU) so it could work with researchers and industry to solve technical problems for the benefit of the green building industry. It also helped to facilitate the development of PSU’s undergraduate and graduate-level training in building science across the curriculum.

  11. The underground research laboratories

    International Nuclear Information System (INIS)

    1997-06-01

    This educational booklet is a general presentation of the selected sites for the installation of underground research laboratories devoted to the feasibility studies of deep repositories for long-life radioactive wastes. It describes the different type of wastes and their management, the management of long life radioactive wastes, the site selection and the 4 sites retained, the preliminary research studies, and the other researches carried out in deep disposal facilities worldwide. (J.S.)

  12. Navy Fuel Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — FUNCTION: Performs basic and applied research to understand the underlying chemistry that impacts the use, handling, and storage of current and future Navy mobility...

  13. Unified fuel elements development for research reactors

    International Nuclear Information System (INIS)

    Vatulin, A.; Stetsky, Y.; Dobrikova, I.

    1998-01-01

    Square cross-section rod type fuel elements have been developed for russian pool-type research reactors. new fuel elements can replace the large nomenclature of tubular fuel elements with around, square and hexahedral cross-sections and to solve a problem of enrichment reduction. the fuel assembly designs with rod type fuel elements have been developed. The overall dimensions of existing the assemblies are preserved in this one. the experimental-industrial fabricating process of fuel elements, based on a joint extrusion method has been developed. The fabricating process has been tested in laboratory conditions, 150 experimental fuel element samples of the various sizes were produced. (author)

  14. Inquiry relating to safety due to modification of usage of nuclear fuel material (establishment of waste safety testing facility) in Tokai Laboratory, Japan Atomic Energy Research Institute

    International Nuclear Information System (INIS)

    1979-01-01

    Application was made to the director of the Science and Technology Agency (STA) for the license relating to the modification of usage of nuclear fuel material (the establishment of waste safety testing facility) from the director of the Japan Atomic Energy Research Institute on November 30, 1978. After passing through the safety evaluation in the Nuclear Safety Bureau of STA, inquiry was conducted to the head of the Atomic Energy Safety Commission (AESC) on June 6, 1979, from the director of the STA. The head of AESC directed to conduct the safety examination to the head of the Nuclear Fuel Safety Examination Specialist Committee on June 7, 1979. The content of the modification of usage of nuclear fuel material is the establishment of waste safety testing facility to study and test the safety relating to the treatment and disposal of high level radioactive liquid wastes due to the reprocessing of spent fuel. As for the results of the safety examination, the siting of the waste safety testing facility which is located in the Tokai Laboratory, Japan Atomic Energy Research Institute (JAERI), and the test plan of the glass solidification of high level radioactive liquid are presented as the outline of the study plan. The building, main equipments including six cells, the isolation room and the glove box, the storage, and the disposal facilities for gas, liquid and solid wastes are explained as the outline of the facilities. Concerning the items from the viewpoint of safety, aseismatic design, slightly vacuum operation, shielding, decay heat removal, fire protection, explosion protection, criticality management, radiation management and environmental effect were evaluated, and the safety was confirmed. (Nakai, Y.)

  15. Fuel Chemistry Research | Transportation Research | NREL

    Science.gov (United States)

    Fuel Chemistry Research Fuel Chemistry Research Photo of a hand holding a beaker containing a clear oils. Photo by Dennis Schroeder, NREL NREL's fuel chemistry research explores how biofuels, advanced , emissions control catalysts, and infrastructure materials. Results from NREL's fuel chemistry studies feed

  16. History of research reactor fuel fabrication at Babcock and Wilcox

    International Nuclear Information System (INIS)

    Freim, James B.

    1983-01-01

    B and W Research Reactor Fuel Element facility at Lynchburg, Virginia now produces national laboratory and university fuel assemblies. The Company's 201000 square foot facility is devoted entirely to supplying research fuel and related products. B and W re-entered the research reactor fuel market in 1981

  17. Metallurgical Research Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — The purpose is to increase basic knowledge of metallurgical processing for controlling the microstructure and mechanical properties of metallic aerospace alloys and...

  18. Materials Behavior Research Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — The purpose is to evaluate mechanical properties of materials including metals, intermetallics, metal-matrix composites, and ceramic-matrix composites under typical...

  19. Laboratory for Large Data Research

    Data.gov (United States)

    Federal Laboratory Consortium — FUNCTION: The Laboratory for Large Data Research (LDR) addresses a critical need to rapidly prototype shared, unified access to large amounts of data across both the...

  20. The National Fire Research Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — The National Fire Research Laboratory (NFRL) is adding a unique facility that will serve as a center of excellence for fireperformance of structures ranging in size...

  1. Geocentrifuge Research Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — The geocentrifuge subjects a sample to a high-gravity field by spinning it rapidly around a central shaft. In this high-gravity field, processes, such as fluid flow,...

  2. Sandia National Laboratories: Research

    Science.gov (United States)

    Energy Stationary Power Earth Science Transportation Energy Energy Research Global Security WMD and decision-making. Materials science Leading the nation in the knowledge of materials engineering success is our foundational scientific research, which provides us with knowledge and capabilities that

  3. Iowa Central Quality Fuel Testing Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Heach, Don; Bidieman, Julaine

    2013-09-30

    The objective of this project is to finalize the creation of an independent quality fuel testing laboratory on the campus of Iowa Central Community College in Fort Dodge, Iowa that shall provide the exploding biofuels industry a timely and cost-effective centrally located laboratory to complete all state and federal fuel and related tests that are required. The recipient shall work with various state regulatory agencies, biofuel companies and state and national industry associations to ensure that training and testing needs of their members and American consumers are met. The recipient shall work with the Iowa Department of Ag and Land Stewardship on the development of an Iowa Biofuel Quality Standard along with the Development of a standard that can be used throughout industry.

  4. Korogwe Research Laboratory

    DEFF Research Database (Denmark)

    Knudsen, Jakob

    2012-01-01

    . It is a large vaccine trial programme simultaneously conducted in several countries in Africa funded by the Bill and Melinda Gates Foundation. The laboratory is an extension to a district hospital placed quite isolated and rural in the north-eastern part of Tanzania. It’s close to the equator and the climate...... and ceiling have been separated leaving a large space for natural ventilation creating a general chimney effect. To provide independent backup water supply all rainwater falling on the roof is collected and directed through a sand filter into a 100m3 subterranean water tank. All constructions, details...... and materials have been carefully selected to last a long time even in a future situation with limited maintenance. Except from the high-end lab equipment only local available materials have been used. All major spaces are reached from colonnades surrounding an inner calm and cool garden space equipped...

  5. Physical Research Laboratory

    Indian Academy of Sciences (India)

    Studies on star formation processes, active galaxies, BL Lac objects and ... photospheric and chromospheric studies and observations for the international GONG ... Research in computer science with focus on image processing and.

  6. National Renewable Energy Laboratory 2003 Research Review

    Energy Technology Data Exchange (ETDEWEB)

    2004-04-01

    In-depth articles on several NREL technologies and advances, including: production of hydrogen using renewable resources and technologies; use of carbon nanotubes for storing hydrogen; enzymatic reduction of cellulose to simple sugars as a platform for making fuel, chemicals, and materials; and the potential of electricity from wind energy to offset carbon dioxide emissions. Also covered are NREL news, awards and honors received by the Laboratory, and patents granted to NREL researchers.

  7. Great Lakes Environmental Research Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — NOAA-GLERL and its partners conduct innovative research on the dynamic environments and ecosystems of the Great Lakes and coastal regions to provide information for...

  8. Research System Integration Laboratory (SIL)

    Data.gov (United States)

    Federal Laboratory Consortium — The VEA Research SIL (VRS) is essential to the success of the TARDEC 30-Year Strategy. The vast majority of the TARDEC Capability Sets face challenging electronics...

  9. Research laboratories annual report 1991

    International Nuclear Information System (INIS)

    1992-08-01

    The 1990-1991 activities, of the Israel Atomic Energy Commission's research laboratories, are presented in this report. The main fields of interest are chemistry and material sciences, life and environmental sciences, nuclear physics and technology

  10. Chemical research at Argonne National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-04-01

    Argonne National Laboratory is a research and development laboratory located 25 miles southwest of Chicago, Illinois. It has more than 200 programs in basic and applied sciences and an Industrial Technology Development Center to help move its technologies to the industrial sector. At Argonne, basic energy research is supported by applied research in diverse areas such as biology and biomedicine, energy conservation, fossil and nuclear fuels, environmental science, and parallel computer architectures. These capabilities translate into technological expertise in energy production and use, advanced materials and manufacturing processes, and waste minimization and environmental remediation, which can be shared with the industrial sector. The Laboratory`s technologies can be applied to help companies design products, substitute materials, devise innovative industrial processes, develop advanced quality control systems and instrumentation, and address environmental concerns. The latest techniques and facilities, including those involving modeling, simulation, and high-performance computing, are available to industry and academia. At Argonne, there are opportunities for industry to carry out cooperative research, license inventions, exchange technical personnel, use unique research facilities, and attend conferences and workshops. Technology transfer is one of the Laboratory`s major missions. High priority is given to strengthening U.S. technological competitiveness through research and development partnerships with industry that capitalize on Argonne`s expertise and facilities. The Laboratory is one of three DOE superconductivity technology centers, focusing on manufacturing technology for high-temperature superconducting wires, motors, bearings, and connecting leads. Argonne National Laboratory is operated by the University of Chicago for the U.S. Department of Energy.

  11. Advanced Research Reactor Fuel Development

    Energy Technology Data Exchange (ETDEWEB)

    Kim, C. K.; Park, H. D.; Kim, K. H. (and others)

    2006-04-15

    RERTR program for non-proliferation has propelled to develop high-density U-Mo dispersion fuels, reprocessable and available as nuclear fuel for high performance research reactors in the world. As the centrifugal atomization technology, invented in KAERI, is optimum to fabricate high-density U-Mo fuel powders, it has a great possibility to be applied in commercialization if the atomized fuel shows an acceptable in-reactor performance in irradiation test for qualification. In addition, if rod-type U-Mo dispersion fuel is developed for qualification, it is a great possibility to export the HANARO technology and the U-Mo dispersion fuel to the research reactors supplied in foreign countries in future. In this project, reprocessable rod-type U-Mo test fuel was fabricated, and irradiated in HANARO. New U-Mo fuel to suppress the interaction between U-Mo and Al matrix was designed and evaluated for in-reactor irradiation test. The fabrication process of new U-Mo fuel developed, and the irradiation test fuel was fabricated. In-reactor irradiation data for practical use of U-Mo fuel was collected and evaluated. Application plan of atomized U-Mo powder to the commercialization of U-Mo fuel was investigated.

  12. Fuel tank integrity research : fuel tank analyses and test plans

    Science.gov (United States)

    2013-04-15

    The Federal Railroad Administrations Office of Research : and Development is conducting research into fuel tank : crashworthiness. Fuel tank research is being performed to : determine strategies for increasing the fuel tank impact : resistance to ...

  13. Minor Actinide Laboratory at JRC-ITU: Fuel fabrication facility

    International Nuclear Information System (INIS)

    Fernandez, A.; McGinley, J.; Somers, J.

    2008-01-01

    The Minor Actinide Laboratory (MA-lab) of the Institute for Transuranium Elements is a unique facility for the fabrication of fuels and targets containing minor actinides (MA). It is of key importance for research on Partitioning and Transmutation in Europe, as it is one of the only dedicated facilities for the fabrication of MA containing materials, either for property measurements or for the production of test pins for irradiation experiments. In this paper a detailed description of the MA-Lab facility and the fabrication processes developed to fabricate fuels and samples containing high content of minor actinides is given. In addition, experience gained and improvements are also outlined. (authors)

  14. Assembly of laboratory line for nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    Fidler, J.; Chotivka, V.

    1979-01-01

    The dismantling of a laboratory line for spent fuel reprocessing after the termination of the research programme and the procedures for hot and semi-hot cell decontamination are described. The equipment was mostly disassembled in smaller parts which were then decontaminated by wiping them with cotton wool soaked in detergent and citric acid, varnished with two-component epoxi varnish, wrapped into multiple polyethylene foils, sealed in PVC bags and thus ready for transport. (B.S.)

  15. Fuel cells for transportation program: FY1997 national laboratory annual report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    The Department of Energy (DOE) Fuel Cells for Transportation Program is structured to effectively implement the research and development (R and D) required for highly efficient, low or zero emission fuel cell power systems to be a viable replacement for the internal combustion engine in automobiles. The Program is part of the Partnership for a New Generation of Vehicles (PNGV), a government-industry initiative aimed at development of an 80 mile-per-gallon vehicle. This Annual Report summarizes the technical accomplishments of the laboratories during 1997. Participants include: Argonne National Laboratory (ANL), Brookhaven National Laboratory (BNL), Lawrence Berkeley National Laboratory (LBNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Pacific Northwest National Laboratory (PNNL), and the National Renewable Energy Laboratory (NREL). During 1997, the laboratory R and D included one project on solid oxide fuel cells; this project has since been terminated to focus Department resources on PEM fuel cells. The technical component of this report is divided into five key areas: fuel cell stack research and development; fuel processing; fuel cell modeling, testing, and evaluation; direct methanol PEM fuel cells; and solid oxide fuel cells.

  16. Caramel fuel for research reactors

    International Nuclear Information System (INIS)

    Bussy, P.

    1979-11-01

    This fuel for research reactors is made of UO 2 pellets in a zircaloy cladding to replace 93% enriched uranium. It is a cold fuel, non contaminating and non proliferating, enrichment is only 7 to 8%. Irradiation tests were performed until burn-up of 50000 MWD/t [fr

  17. Deactivation completed at historic Hanford Fuels Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Gerber, M.S.

    1994-03-01

    This report discusses deactivation work which was completed as of March 31, 1994 at the 308 Fuels Development Laboratory (FDL) at the Hanford Site near Richland, Washington. The decision to deactivate the structure, formerly known as the Plutonium Fabrication Pilot Plant (PFPP), was driven by a 1980s Department of Energy (DOE) decision that plutonium fuels should not be fabricated in areas near the Site`s boundaries, as well as by changing facility structural requirements. Inventory transfer has been followed by the cleanout and stabilization of plutonium oxide (PuO{sub 2}) and enriched uranium oxide (UO{sub 2}) residues and powders in the facility`s equipment and duct work. The Hanford Site, located in southeastern Washington state, was one of America`s primary arsenals of nuclear defense production for nearly 50 years beginning in World War II. Approximately 53 metric tons of weapons grade plutonium, over half of the national supply and about one quarter of the world`s supply, were produced at Hanford between 1944 and 1989. Today, many Site buildings are undergoing deactivation, a precursor phase to decontamination and decommissioning (D&D). The primary difference between the two activities is that equipment and structural items are not removed or torn down in deactivation. However, utilities are disconnected, and special nuclear materials (SNM) as well as hazardous and pyrophoric substances are removed from structures undergoing this process.

  18. Deactivation completed at historic Hanford Fuels Laboratory

    International Nuclear Information System (INIS)

    Gerber, M.S.

    1994-03-01

    This report discusses deactivation work which was completed as of March 31, 1994 at the 308 Fuels Development Laboratory (FDL) at the Hanford Site near Richland, Washington. The decision to deactivate the structure, formerly known as the Plutonium Fabrication Pilot Plant (PFPP), was driven by a 1980s Department of Energy (DOE) decision that plutonium fuels should not be fabricated in areas near the Site's boundaries, as well as by changing facility structural requirements. Inventory transfer has been followed by the cleanout and stabilization of plutonium oxide (PuO 2 ) and enriched uranium oxide (UO 2 ) residues and powders in the facility's equipment and duct work. The Hanford Site, located in southeastern Washington state, was one of America's primary arsenals of nuclear defense production for nearly 50 years beginning in World War II. Approximately 53 metric tons of weapons grade plutonium, over half of the national supply and about one quarter of the world's supply, were produced at Hanford between 1944 and 1989. Today, many Site buildings are undergoing deactivation, a precursor phase to decontamination and decommissioning (D ampersand D). The primary difference between the two activities is that equipment and structural items are not removed or torn down in deactivation. However, utilities are disconnected, and special nuclear materials (SNM) as well as hazardous and pyrophoric substances are removed from structures undergoing this process

  19. Small-Engine Research Laboratory (SERL)

    Data.gov (United States)

    Federal Laboratory Consortium — Description: The Small-Engine Research Laboratory (SERL) is a facility designed to conduct experimental small-scale propulsion and power generation systems research....

  20. PCR+ In Diesel Fuels and Emissions Research

    Energy Technology Data Exchange (ETDEWEB)

    McAdams, H.T.

    2002-04-15

    In past work for the U.S. Department of Energy (DOE) and Oak Ridge National Laboratory (ORNL), PCR+ was developed as an alternative methodology for building statistical models. PCR+ is an extension of Principal Components Regression (PCR), in which the eigenvectors resulting from Principal Components Analysis (PCA) are used as predictor variables in regression analysis. The work was motivated by the observation that most heavy-duty diesel (HDD) engine research was conducted with test fuels that had been ''concocted'' in the laboratory to vary selected fuel properties in isolation from each other. This approach departs markedly from the real world, where the reformulation of diesel fuels for almost any purpose leads to changes in a number of interrelated properties. In this work, we present new information regarding the problems encountered in the conventional approach to model-building and how the PCR+ method can be used to improve research on the relationship between fuel characteristics and engine emissions. We also discuss how PCR+ can be applied to a variety of other research problems related to diesel fuels.

  1. National Renewable Energy Laboratory 2005 Research Review

    Energy Technology Data Exchange (ETDEWEB)

    Brown, H.; Gwinner, D.; Miller, M.; Pitchford, P.

    2006-06-01

    Science and technology are at the heart of everything we do at the National Renewable Energy Laboratory, as we pursue innovative, robust, and sustainable ways to produce energy--and as we seek to understand and illuminate the physics, chemistry, biology, and engineering behind alternative energy technologies. This year's Research Review highlights the Lab's work in the areas of alternatives fuels and vehicles, high-performing commercial buildings, and high-efficiency inverted, semi-mismatched solar cells.

  2. Research reactor fuel - an update

    International Nuclear Information System (INIS)

    Finlay, M.R.; Ripley, M.I.

    2003-01-01

    In the two years since the last ANA conference there have been marked changes in the research reactor fuel scene. A new low-enriched uranium (LEU) fuel, 'monolithic' uranium molybdenum, has shown such promise in initial trials that it may be suitable to meet the objectives of the Joint Declaration signed by Presidents Bush and Putin to commit to converting all US and Russian research reactors to LEU by 2012. Development of more conventional aluminium dispersion UMo LEU fuel has continued in the meantime and is entering the final qualification stage of multiple full sized element irradiations. Despite this progress, the original 2005 timetable for UMo fuel qualification has slipped and research reactors, including the RRR, may not convert from silicide to UMo fuel before 2007. The operators of the Swedish R2 reactor have been forced to pursue the direct route of qualifying a UMo lead test assembly (LTA) in order to meet spent fuel disposal requirements of the Swedish law. The LTA has recently been fabricated and is expected to be loaded shortly into the R2 reactor. We present an update of our previous ANA paper and details of the qualification process for UMo fuel

  3. Laboratory directed research and development

    Energy Technology Data Exchange (ETDEWEB)

    1991-11-15

    The purposes of Argonne's Laboratory Directed Research and Development (LDRD) Program are to encourage the development of novel concepts, enhance the Laboratory's R D capabilities, and further the development of its strategic initiatives. Among the aims of the projects supported by the Program are establishment of engineering proof-of-principle''; development of an instrumental prototype, method, or system; or discovery in fundamental science. Several of these project are closely associated with major strategic thrusts of the Laboratory as described in Argonne's Five Year Institutional Plan, although the scientific implications of the achieved results extend well beyond Laboratory plans and objectives. The projects supported by the Program are distributed across the major programmatic areas at Argonne. Areas of emphasis are (1) advanced accelerator and detector technology, (2) x-ray techniques in biological and physical sciences, (3) advanced reactor technology, (4) materials science, computational science, biological sciences and environmental sciences. Individual reports summarizing the purpose, approach, and results of projects are presented.

  4. Physics Research at the Naval Research Laboratory

    Science.gov (United States)

    Coffey, Timothy

    2001-03-01

    The United States Naval Research Laboratory conducts a broad program of research into the physical properties of matter. Studies range from low temperature physics, such as that associated with superconducting systems to high temperature systems such as laser produced or astrophysical plasmas. Substantial studies are underway on surface science and nanoscience. Studies are underway on the electronic and optical properties of materials. Studies of the physical properties of the ocean and the earth’s atmosphere are of considerable importance. Studies of the earth’s sun particularly as it effects the earth’s ionosphere and magnetosphere are underway. The entire program involves a balance of laboratory experiments, field experiments and supporting theoretical and computational studies. This talk will address NRL’s funding of physics, its employment of physicists and will illustrate the nature of NRL’s physics program with several examples of recent accomplishments.

  5. Fuels for Canadian research reactors

    International Nuclear Information System (INIS)

    Feraday, M.A.

    1993-01-01

    This paper includes some statements and remarks concerning the uranium silicide fuels for which there is significant fabrication in AECL, irradiation and defect performance experience; description of two Canadian high flux research reactors which use high enrichment uranium (HEU) and the fuels currently used in these reactors; limited fabrication work done on Al-U alloys to uranium contents as high as 40 wt%. The latter concerns work aimed at AECL fast neutron program. This experience in general terms is applied to the NRX and NRU designs of fuel

  6. Fire, Fuel, and Smoke Science Program 2015 Research Accomplishments

    Science.gov (United States)

    Faith Ann Heinsch; Charles W. McHugh; Colin C. Hardy

    2016-01-01

    The Fire, Fuel, and Smoke Science Program (FFS) of the U.S. Forest Service, Rocky Mountain Research Station focuses on fundamental and applied research in wildland fire, from fire physics and fire ecology to fuels management and smoke emissions. Located at the Missoula Fire Sciences Laboratory in Montana, the scientists, engineers, technicians, and support...

  7. Fire, Fuel, and Smoke Program: 2014 Research Accomplishments

    Science.gov (United States)

    Faith Ann Heinsch; Robin J. Innes; Colin C. Hardy; Kristine M. Lee

    2015-01-01

    The Fire, Fuel, and Smoke Science Program (FFS) of the U.S. Forest Service, Rocky Mountain Research Station focuses on fundamental and applied research in wildland fire, from fire physics and fire ecology to fuels management and smoke emissions. Located at the Missoula Fire Sciences Laboratory in Montana, the scientists, engineers, technicians, and support staff in FFS...

  8. Status of biomass fuels technologies research in the US

    Energy Technology Data Exchange (ETDEWEB)

    Koontz, R.P.; Parker, S.; Glenn, B.

    1984-07-01

    Biomass is a tremendous potential source of fuel and chemical feedstocks. The US Department of Energy has sponsored a broad spectrum of research on biomass at various US government laboratories, private installations, and universities. The status of biomass fuels technologies research in the US is discussed.

  9. Fire, Fuel, and Smoke Science Program: 2013 Research accomplishments

    Science.gov (United States)

    Faith Ann Heinsch; Robin J. Innes; Colin C. Hardy; Kristine M. Lee

    2014-01-01

    The Fire, Fuel, and Smoke Science Program (FFS) of the U.S. Forest Service, Rocky Mountain Research Station, focuses on fundamental and applied research in wildland fire, from fire physics and fire ecology to fuels management and smoke emissions. Located at the Missoula Fire Sciences Laboratory in Montana, the scientists, engineers, technicians, and support staff in...

  10. NAS Human Factors Safety Research Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — This laboratory conducts an integrated program of research on the relationship of factors concerning individuals, work groups, and organizations as employees perform...

  11. Performance Evaluation of Metallic Dispersion Fuel for Advanced Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Ryu, Ho Jin; Park, Jong Man; Kim, Chang Kyu; Chae, Hee Taek; Song, Kee Chan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Kim, Yeon Soo [Argonne National Laboratory, New York (United States)

    2007-07-01

    Uranium alloys with a high uranium density has been developed for high power research reactor fuel using low-enriched uranium (LEU). U-Mo alloys have been developed as candidate fuel material because of excellent irradiation behavior. Irradiation behavior of U-Mo/Al dispersion fuel has been investigated to develop high performance research reactor fuel as RERTR international research program. While plate-type and rod-type dispersion fuel elements are used for research reactors, HANARO uses rod-type dispersion fuel elements. PLATE code is developed by Argonne National Laboratory for the performance evaluation of plate-type dispersion fuel, but there is no counterpart for rod-type dispersion fuel. Especially, thermal conductivity of fuel meat decreases during the irradiation mainly because of interaction layer formation at the interface between the U-Mo fuel particle and Al matrix. The thermal conductivity of the interaction layer is not as high as the Al matrix. The growth of interaction layer is interactively affected by the temperature of fuel because it is associated with a diffusion reaction which is a thermally activated process. It is difficult to estimate the temperature profile during irradiation test due to the interdependency of fuel temperature and thermal conductivity changed by interaction layer growth. In this study, fuel performance of rod-type U-Mo/Al dispersion fuels during irradiation tests were estimated by considering the effect of interaction layer growth on the thermal conductivity of fuel meat.

  12. Performance Evaluation of Metallic Dispersion Fuel for Advanced Research Reactors

    International Nuclear Information System (INIS)

    Ryu, Ho Jin; Park, Jong Man; Kim, Chang Kyu; Chae, Hee Taek; Song, Kee Chan; Kim, Yeon Soo

    2007-01-01

    Uranium alloys with a high uranium density has been developed for high power research reactor fuel using low-enriched uranium (LEU). U-Mo alloys have been developed as candidate fuel material because of excellent irradiation behavior. Irradiation behavior of U-Mo/Al dispersion fuel has been investigated to develop high performance research reactor fuel as RERTR international research program. While plate-type and rod-type dispersion fuel elements are used for research reactors, HANARO uses rod-type dispersion fuel elements. PLATE code is developed by Argonne National Laboratory for the performance evaluation of plate-type dispersion fuel, but there is no counterpart for rod-type dispersion fuel. Especially, thermal conductivity of fuel meat decreases during the irradiation mainly because of interaction layer formation at the interface between the U-Mo fuel particle and Al matrix. The thermal conductivity of the interaction layer is not as high as the Al matrix. The growth of interaction layer is interactively affected by the temperature of fuel because it is associated with a diffusion reaction which is a thermally activated process. It is difficult to estimate the temperature profile during irradiation test due to the interdependency of fuel temperature and thermal conductivity changed by interaction layer growth. In this study, fuel performance of rod-type U-Mo/Al dispersion fuels during irradiation tests were estimated by considering the effect of interaction layer growth on the thermal conductivity of fuel meat

  13. Fuels Combustion Research: Supercritical Fuel Pyrolysis

    National Research Council Canada - National Science Library

    Glassman, Irvin

    2001-01-01

    .... The focus during the subject period was directed to understanding the pyrolysis and combustion of endothermic fuels under subcritical conditions and the pyrolysis of these fuels under supercritical conditions...

  14. Fuels Combustion Research: Supercritical Fuel Pyrolysis

    National Research Council Canada - National Science Library

    Glassman, Irvin

    2000-01-01

    .... The focus during the subject period was directed to understanding the pyrolysis and combustion of endothermic fuels under subcritical conditions and the pyrolysis of these fuels under supercritical conditions...

  15. NDE Acoustic Microscopy Research Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — The purpose is to develop advanced, more effective high-resolution micro-NDE materials characterization methods using scanning acoustic microscopy. The laboratory's...

  16. Fuels Performance | Transportation Research | NREL

    Science.gov (United States)

    Biodiesel Performance in Modern Engines NREL is working cooperatively with the National Biodiesel Board on research that assesses several aspects of biodiesel compatibility with engines, vehicles, and fuel-handling infrastructure. Several cooperative studies were recently conducted that examined how biodiesel performs with new

  17. U.S. Army Research Laboratory Annual Review 2011

    Science.gov (United States)

    2011-12-01

    bioremediation of wastewater. The researchers created a functional atomic circuit with stationary barrier. This “atom circuit” is composed of ultra...high energy content approaching jet propellant (JP)-8/ diesel fuel, are a means to address these demands. The Army Research Laboratory has

  18. Institute of Laboratory Animal Research

    National Research Council Canada - National Science Library

    Dell, Ralph

    2000-01-01

    ...; and reports on specific issues of humane care and use of laboratory animals. ILAR's mission is to help improve the availability, quality, care, and humane and scientifically valid use of laboratory animals...

  19. Reducing enrichment of fuel for research reactors

    International Nuclear Information System (INIS)

    Kanda, Keiji; Matsuura, Shojiro.

    1980-01-01

    In research reactors, highly enriched uranium (HEU) is used as fuel for their purposes of operation. However, the United States strongly required in 1977 that these HEU should be replaced by low enrichment uranium (LEU) of 20% or less, or even in unavoidable cases, it should be replaced by medium enrichment uranium (MEU). INFCE (International Nuclear Fuel Cycle Evaluation) which started its activity just at that time decided to discuss this problem in the research reactor group of No. 8 sectional committee. Japan has been able to forward the work, taking a leading part in the international opinion because she has taken the countermeasures quickly. INFCE investigated the problem along the lines of policy that the possibility of reducing the degree of enrichment should be limited to the degree in which the core structures and equipments of research reactors will be modified as little as possible, and the change of fuel element geometry will be done within the permissible thermohydrodynamic capacity, and concluded that it might be possible in near future to reduce the degree of enrichment to about 45% MEU, while the reduction to 20% LEU might require considerable research, development and verification. On the other hand, the joint researches by Kyoto University and ANL (Argonne National Laboratory) and by Japan Atomic Energy Research Institute and ANL are being continued. IAEA has edited the guidebook (IAEA-TECDOC-233) for reducing the degree of enrichment for developing countries. (Wakatsuki, Y.)

  20. Advanced research reactor fuel development

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Chang Kyu; Pak, H. D.; Kim, K. H. [and others

    2000-05-01

    The fabrication technology of the U{sub 3}Si fuel dispersed in aluminum for the localization of HANARO driver fuel has been launches. The increase of production yield of LEU metal, the establishment of measurement method of homogeneity, and electron beam welding process were performed. Irradiation test under normal operation condition, had been carried out and any clues of the fuel assembly breakdown was not detected. The 2nd test fuel assembly has been irradiated at HANARO reactor since 17th June 1999. The quality assurance system has been re-established and the eddy current test technique has been developed. The irradiation test for U{sub 3}Si{sub 2} dispersed fuels at HANARO reactor has been carried out in order to compare the in-pile performance of between the two types of U{sub 3}Si{sub 2} fuels, prepared by both the atomization and comminution processes. KAERI has also conducted all safety-related works such as the design and the fabrication of irradiation rig, the analysis of irradiation behavior, thermal hydraulic characteristics, stress analysis for irradiation rig, and thermal analysis fuel plate, for the mini-plate prepared by international research cooperation being irradiated safely at HANARO. Pressure drop test, vibration test and endurance test were performed. The characterization on powders of U-(5.4 {approx} 10 wt%) Mo alloy depending on Mo content prepared by rotating disk centrifugal atomization process was carried out in order to investigate the phase stability of the atomized U-Mo alloy system. The {gamma}-U phase stability and the thermal compatibility of atomized U-16at.%Mo and U-14at.%Mo-2at.%X(: Ru, Os) dispersion fuel meats at an elevated temperature have been investigated. The volume increases of U-Mo compatibility specimens were almost the same as or smaller than those of U{sub 3}Si{sub 2}. However the atomized alloy fuel exhibited a better irradiation performance than the comminuted alloy. The RERTR-3 irradiation test of nano

  1. Developments of Spent Nuclear Fuel Pyroprocessing Technology at Idaho National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Michael F. Simpson

    2012-03-01

    This paper summarizes research in used fuel pyroprocessing that has been published by Idaho National Laboratory over the last decade. It includes work done both on treatment of Experimental Breeder Reactor-II and development of advanced technology for potential scale-up and commercialization. Collaborations with universities and other laboratories is included in the cited work.

  2. Air Force Research Laboratory Integrated Omics Research

    Science.gov (United States)

    2015-10-01

    fuel exposures and cognitive fatigue. 15. SUBJECT TERMS biomonitoring, omics, metabonomics, proteomics, genomics, epigenetics, biomarker, toxin...biomarker discovery in a number of toxicology and human performance projects, including jet fuel exposures and cognitive fatigue. INTRODUCTION One of...chemical exposure for U.S. and NATO military personnel46; inhalation and dermal have been shown to represent the primary routes of exposure47 This

  3. National Bio-fuel Energy Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Jezierski, Kelly [NextEnergy Center, Detroit, MI (United States)

    2010-12-27

    The National Biofuel Energy Laboratory or NBEL was a consortia consisting of non-profits, universities, industry, and OEM’s. NextEnergy Center (NEC) in Detroit, Michigan was the prime with Wayne State University as the primary subcontractor. Other partners included: Art Van Furniture; Biodiesel Industries Inc. (BDI); Bosch; Clean Emission Fluids (CEF); Delphi; Oakland University; U.S. TARDEC (The Army); and later Cummins Bridgeway. The program was awarded to NextEnergy by U.S. DOE-NREL on July 1, 2005. The period of performance was about five (5) years, ending June 30, 2010. This program was executed in two phases: 1.Phase I focused on bench-scale R&D and performance-property-relationships. 2.Phase II expanded those efforts into further engine testing, emissions testing, and on-road fleet testing of biodiesel using additional types of feedstock (i.e., corn, and choice white grease based). NextEnergy – a non-profit 501(c)(3) organization based in Detroit was originally awarded a $1.9 million grant from the U.S. Dept. of Energy for Phase I of the NBEL program. A few years later, NextEnergy and its partners received an additional $1.9MM in DOE funding to complete Phase II. The NBEL funding was completely exhausted by the program end date of June 30, 2010 and the cost share commitment of 20% minimum has been exceeded nearly two times over. As a result of the work performed by the NBEL consortia, the following successes were realized: 1.Over one hundred publications and presentations have been delivered by the NBEL consortia, including but not limited to: R&D efforts on algae-based biodiesel, novel heterogeneous catalysis, biodiesel properties from a vast array of feedstock blends, cold flow properties, engine testing results (several Society of Automotive Engineers [SAE] papers have been published on this research), emissions testing results, and market quality survey results. 2.One new spinoff company (NextCAT) was formed by two WSU Chemical Engineering professors

  4. Biometrics Research and Engineering Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — As the Department of Defense moves forward in its pursuit of integrating biometrics technology into facility access control, the Global War on Terrorism and weapon...

  5. Subsonic Aerodynamic Research Laboratory (SARL)

    Data.gov (United States)

    Federal Laboratory Consortium — Description: The SARL is a unique high contraction, open circuit subsonic wind tunnel providing a test velocity up to 436 mph (0.5 Mach number) and a high quality,...

  6. Research and development of thorium fuel cycle

    International Nuclear Information System (INIS)

    Oishi, Jun.

    1994-01-01

    Nuclear properties of thorium are summarized and present status of research and development of the use of thorium as nuclear fuel is reviewed. Thorium may be used for nuclear fuel in forms of metal, oxide, carbide and nitride independently, alloy with uranium or plutonium or mixture of the compound. Their use in reactors is described. The reprocessing of the spent oxide fuel in thorium fuel cycle is called the thorex process and similar to the purex process. A concept of a molten salt fuel reactor and chemical processing of the molten salt fuel are explained. The required future research on thorium fuel cycle is commented briefly. (T.H.)

  7. Composite Solid Fuel: Research of Formation Parameters

    Directory of Open Access Journals (Sweden)

    Tabakaev Roman

    2016-01-01

    Full Text Available Involving of local low-grade fuels resources in fuel and energy balance is actual question of research in the present. In this paper the possibility of processing low-grade fuel in the solid fuel composite was considered. The aim of the work is to define the optimal parameters for formation of the solid composite fuel. A result of researches determined that dextrin content in the binder allows to obtain solid composite fuel having the highest strength. The drying temperature for the various fuels was determined: for pellets production was 20-80 °C, for briquettes – 20-40 °C.

  8. Techniques in cancer research: a laboratory manual

    International Nuclear Information System (INIS)

    Deo, M.G.; Seshadri, R.; Mulherkar, R.; Mukhopadhyaya, R.

    1995-01-01

    Cancer Research Institute (CRI) works on all facets of cancer using the latest biomedical tools. For this purpose, it has established modern laboratories in different branches of cancer biology such as cell and molecular biology, biochemistry, immunology, chemical and viral oncogenesis, genetics of cancer including genetic engineering, tissue culture, cancer chemotherapy, neurooncology and comparative oncology. This manual describes the protocols used in these laboratories. There is also a chapter on handling and care of laboratory animals, an essential component of any modern cancer biology laboratory. It is hoped that the manual will be useful to biomedical laboratories, specially those interested in cancer research. refs., tabs., figs

  9. The integral fast reactor fuels reprocessing laboratory at Argonne National Laboratory, Illinois

    International Nuclear Information System (INIS)

    Wolson, R.D.; Tomczuk, Z.; Fischer, D.F.; Slawecki, M.A.; Miller, W.E.

    1986-09-01

    The processing of Integral Fast Reactor (IFR) metal fuel utilizes pyrochemical fuel reprocessing steps. These steps include separation of the fission products from uranium and plutonium by electrorefining in a fused salt, subsequent concentration of uranium and plutonium for reuse, removal, concentration, and packaging of the waste material. Approximately two years ago a facility became operational at Argonne National Laboratory-Illinois to establish the chemical feasibility of proposed reprocessing and consolidation processes. Sensitivity of the pyroprocessing melts to air oxidation necessitated operation in atmosphere-controlled enclosures. The Integral Fast Reactor Fuels Reprocessing Laboratory is described

  10. Logistics of the research reactor fuel cycle: AREVA solutions

    International Nuclear Information System (INIS)

    Ohayon, David; Halle, Laurent; Naigeon, Philippe; Falgoux, Jean-Louis; Franck Obadia, Franck; Auziere, Philippe

    2005-01-01

    The AREVA Group Companies offer comprehensive solutions for the entire fuel cycle of Research Reactors comply with IAEA standards. CERCA and Cogema Logistics have developed a full partnership in the front end cycle. In the field of uranium CERCA and Cogema Logistics have the long term experience of the shipment from Russia, USA to the CERCA plant.. Since 1960, CERCA has manufactured over 300,000 fuel plates and 15,000 fuel elements of more than 70 designs. These fuel elements have been delivered to 40 research reactors in 20 countries. For the Back-End stage, Cogema and Cogema Logistics propose customised solutions and services for international shipments. Cogema Logistics has developed a new generation of packaging to meet the various needs and requirements of the Laboratories and Research Reactors all over the world, and complex regulatory framework. Comprehensive assistance dedicated, services, technical studies, packaging and transport systems are provided by AREVA for every step of research reactor fuel cycle. (author)

  11. Naval Research Laboratory Arctic Initiatives

    Science.gov (United States)

    2011-06-01

    Campaign Code 7420 Arctic Modeling Code 7320/7500/7600 In-situ NRL, CRREL NRL boreholes Strategy Remote Sensing Synergism −Collect in-situ...Navy and Marine Corps Corporate Laboratory An array of BMFCs being prepared for deployment. Each BMFC consists of a weighted anode laid flat onto...Gas CH4 E C D CO2 BGHS Free Methane Gas Hydrates HCO3- HCO3- Seismic and geochemical data to predict deep sediment hydrates Estimate spatial

  12. Fuel elements of research reactors in China

    International Nuclear Information System (INIS)

    Zhou Yongmao; Chen Dianshan; Tan Jiaqiu

    1987-01-01

    This paper describes the current status of design, fabrication of fuel elements for research reactors in China, emphasis is placed on the technology of fuel elements for the High Flux Engineering Test Reactor (HFETR). (author)

  13. Proceedings of fuel safety research specialists' meeting

    International Nuclear Information System (INIS)

    Suzuki, Motoe

    2002-08-01

    Fuel Safety Research Specialists' Meeting, which was organized by Japan Atomic Energy Research Institute, was held on March 4-5, 2002 at JAERI in Tokai Establishment. Purposes of the Meeting are to exchange information and views on LWR fuel safety topics among the specialist participants from domestic and foreign organizations, and to discuss the recent and future fuel research activities in JAERI. In the Meeting, presentations were given and discussions were made on general report of fuel safety research activities, fuel behaviors in normal operation and accident conditions, FP release behaviors in severe accident conditions, and JAERI's ''Advanced LWR Fuel Performance and Safety Research Program''. A poster exhibition was also carried out. The Meeting significantly contributed to planning future program and cooperation in fuel research. This proceeding integrates all the pictures and papers presented in the Meeting. The 10 of the presented papers are indexed individually. (J.P.N.)

  14. Laboratory Animal Technician | Center for Cancer Research

    Science.gov (United States)

    PROGRAM DESCRIPTION The Laboratory Animal Sciences Program (LASP) provides exceptional quality animal care and technical support services for animal research performed at the National Cancer Institute at the Frederick National Laboratory for Cancer Research. LASP executes this mission by providing a broad spectrum of state-of-the-art technologies and services that are focused

  15. Argonne Research Library | Argonne National Laboratory

    Science.gov (United States)

    Argonne Argonne Research Library The Argonne Research Library supports the scientific and technical research needs of Argonne National Laboratory employees. Our library catalog is available via the Research questions or concerns, please contact us at librarians@anl.gov. Contact the Library Argonne Research Library

  16. Sandia National Laboratories: Research: Biodefense

    Science.gov (United States)

    Energy Stationary Power Earth Science Transportation Energy Energy Research Global Security WMD knowledge to counter disease Sandia conducts research into how pathogens interact and subvert a host's immune response to develop the knowledge base needed to create new novel environmental detectors, medical

  17. United States Domestic Research Reactor Infrastructure TRIGA Reactor Fuel Support

    International Nuclear Information System (INIS)

    Morrell, Douglas

    2011-01-01

    The United State Domestic Research Reactor Infrastructure Program at the Idaho National Laboratory manages and provides project management, technical, quality engineering, quality inspection and nuclear material support for the United States Department of Energy sponsored University Reactor Fuels Program. This program provides fresh, unirradiated nuclear fuel to Domestic University Research Reactor Facilities and is responsible for the return of the DOE-owned, irradiated nuclear fuel over the life of the program. This presentation will introduce the program management team, the universities supported by the program, the status of the program and focus on the return process of irradiated nuclear fuel for long term storage at DOE managed receipt facilities. It will include lessons learned from research reactor facilities that have successfully shipped spent fuel elements to DOE receipt facilities.

  18. Summary of fuel safety research meeting 2004

    International Nuclear Information System (INIS)

    Fuketa, Toyoshi; Hidaka, Akihide; Nakamura, Jinichi; Suzuki, Motoe; Nagase, Fumihisa; Sasajima, Hideo; Fujita, Misao; Otomo, Takashi; Kudo, Tamotsu; Amaya, Masaki; Sugiyama, Tomoyuki; Ikehata, Hisashi; Iwasaki, Ryo; Ozawa, Masaaki; Kida, Mitsuko

    2004-10-01

    Fuel Safety Research Meeting 2004, which was organized by the Japan Atomic Energy Research Institute, was held on March 1-2, 2004 at Toranomon Pastoral, Tokyo. The purposes of the meeting are to present and discuss the results of experiments and analyses on reactor fuel safety and to exchange views and experiences among the participants. The technical topics of the meeting covered the status of fuel safety research activities, fuel behavior under RIA and LOCA conditions, high burnup fuel behavior, and radionuclides release under severe accident conditions. This summary contains all the abstracts and OHP sheets presented in the meeting. (author)

  19. Research and Progress on Virtual Cloud Laboratory

    Directory of Open Access Journals (Sweden)

    Zhang Jian Wei

    2016-01-01

    Full Text Available In recent years, cloud computing technology has experienced continuous development and improvement, and has gradually expanded to the education sector. First, this paper will introduce the background knowledge of the current virtual cloud laboratory; by comparing the advantages and disadvantages between traditional laboratory and virtual cloud laboratory, and comparing the application, advantages and disadvantages, and development trend of OpenStack technology and VMWare technology in safety, performance, design, function, use case, and value of virtual cloud laboratory, this paper concludes that application based on OpenStack virtual cloud laboratory in universities and research institutes and other departments is essential.

  20. Fuels Performance | Transportation Research | NREL

    Science.gov (United States)

    chemistry, combustion, and emissions to answer two primary questions: How can improved fuel chemistry lead initiative Combustion and engines Fuel chemistry Emissions and fuel economy Find out about related NREL Chemistry. (2014) Saturated Monoglyceride Effects on Low-Temperature Performance of Biodiesel Blends. G.M

  1. Research laboratories annual report 1994

    International Nuclear Information System (INIS)

    1996-01-01

    The publication is the 1994 annual report of the Israel atomic energy commission in a new format. The report includes three invited papers and a bibliographic list of publications by the commission scientific researches

  2. Research laboratories annual report 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    The publication is the 1994 annual report of the Israel atomic energy commission in a new format. The report includes three invited papers and a bibliographic list of publications by the commission scientific researches.

  3. Human-machine interfaces for teleoperators: an overview of research and development at the Oak Ridge National Laboratory. Consolidated Fuel Reprocessing Program

    International Nuclear Information System (INIS)

    Draper, J.V.; Feldman, M.J.

    1985-01-01

    This paper surveys the contributions of human factors to the mission of the Remote Control Engineering (RCE) task over the last six years. These contributions can be divided into two areas, research efforts and design efforts. Some of the topics covered in human factors research are manipulator comparisons, investigation of viewing system characteristics, research into the effects of force reflection, and studies of crew size and task allocation. In the area of component design the human factors group was primarily responsible for the conceptual design of the Advanced Integrated Maintenance System (AIMS) control room, including all operator work stations and overall control room architecture. The human factors group also contributed to the design of the AIMS master controller handle. Recent research at the RCE task has centered on comparison of manipulator systems. This research was planned and conducted by the human factors group and other ORNL personnel. The research is aimed at evaluating three important characteristics of manipulator systems: system dynamics, force feedback, and human-machine interface

  4. Trends in fuel reprocessing safety research

    International Nuclear Information System (INIS)

    Tsujino, Takeshi

    1981-01-01

    With the operation of a fuel reprocessing plant in the Power Reactor and Nuclear Fuel Development Corporation (PNC) and the plan for a second fuel reprocessing plant, the research on fuel reprocessing safety, along with the reprocessing technology itself, has become increasingly important. As compared with the case of LWR power plants, the safety research in this field still lags behind. In the safety of fuel reprocessing, there are the aspects of keeping radiation exposure as low as possible in both personnel and local people, the high reliability of the plant operation and the securing of public safety in accidents. Safety research is then required to establish the safety standards and to raise the rate of plant operation associated with safety. The following matters are described: basic ideas for the safety design, safety features in fuel reprocessing, safety guideline and standards, and safety research for fuel reprocessing. (J.P.N.)

  5. Naval Research Laboratory 1986 Review

    Science.gov (United States)

    1986-01-01

    probabil- infinitesimal impedance elements cannot be dep- ity density, icted .) If PR (r. 1 is the joint probability den- sity function for r and 1, a...Dynamics. 1-5 Sept. 1986, finse Research. Medellin , Colombia. % Rosenblum, L.J., Chairperson, IEEE Computer Saks, N.S., Coorganizer and lecturer, IEEE

  6. Research laboratories annual report 1992

    International Nuclear Information System (INIS)

    1993-07-01

    The report book presents the various research activities within the Israel Atomic Energy Commission, during 1992 calendar year. The discipline reported here are (by chapters): theoretical physics and theoretical chemistry, optics and lasers, solid states and nuclear physics, material sciences, chemistry, radiopharmaceuticals, labelled compounds and environmental studies, radiation effects, dosimetry and protection, instrumentation and techniques

  7. Dispersion fuel for nuclear research facilities

    International Nuclear Information System (INIS)

    Kushtym, A.V.; Belash, M.M.; Zigunov, V.V.; Slabospitska, O.O.; Zuyok, V.A.

    2017-01-01

    Designs and process flow sheets for production of nuclear fuel rod elements and assemblies TVS-XD with dispersion composition UO_2+Al are presented. The results of fuel rod thermal calculation applied to Kharkiv subcritical assembly and Kyiv research reactor VVR-M, comparative characteristics of these fuel elements, the results of metallographic analyses and corrosion tests of fuel pellets are given in this paper

  8. Sandia National Laboratories: Research: Research Foundations: Nanodevices

    Science.gov (United States)

    Technology Partnerships Business, Industry, & Non-Profits Government Universities Center for Mexico Small Business Assistance Program Sandia Science & Technology Park Careers Community support for research; technology advancement and maturation; and small-lot, fast-turn prototyping Our

  9. Research laboratories annual report 1993

    International Nuclear Information System (INIS)

    1994-08-01

    The 1993 annual report of the Israel Atomic Energy Commission presents, in brief and concise form, recent results and achievements of the well established program of the basic and applied research carried out by the scientists and engineers of the Israel Atomic Energy Commission in collaboration with colleagues at the other institutions in Israel and abroad. In terms of contents, the report presents the usual combination of topical basic applied research. Much of the work has been published or submitted for publication in the international scientific or technical literature. The main headings in the report are: theoretical physics and theoretical chemistry; optics and lasers; solid states and nuclear physics; materials sciences; chemistry; environmental studies and radiopharmaceuticals; radiation effects, dosimetry and radioprotection; and instrumentation and techniques

  10. Design study of underground facility of the Underground Research Laboratory

    International Nuclear Information System (INIS)

    Hibiya, Keisuke; Akiyoshi, Kenji; Ishizuka, Mineo; Anezaki, Susumu

    1998-03-01

    Geoscientific research program to study deep geological environment has been performed by Power Reactor and Nuclear Fuel Development Corporation (PNC). This research is supported by 'Long-Term Program for Research, Development and Utilization of Nuclear Energy'. An Underground Research Laboratory is planned to be constructed at Shoma-sama Hora in the research area belonging to PNC. A wide range of geoscientific research and development activities which have been previously studied at the Tono Area is planned in the laboratory. The Underground Research Laboratory is consisted of Surface Laboratory and Underground Research Facility located from the surface down to depth between several hundreds and 1,000 meters. Based on the results of design study in last year, the design study performed in this year is to investigate the followings in advance of studies for basic design and practical design: concept, design procedure, design flow and total layout. As a study for the concept of the underground facility, items required for the facility are investigated and factors to design the primary form of the underground facility are extracted. Continuously, design methods for the vault and the underground facility are summarized. Furthermore, design procedures of the extracted factors are summarized and total layout is studied considering the results to be obtained from the laboratory. (author)

  11. Research laboratories annual report 1987

    International Nuclear Information System (INIS)

    1988-08-01

    The 1987 report reflects a continuation of trends and patterns established in previous years. It does not reveal novel revolutionary developments and does not open new horizons and vistas. Rather, the report represents what we believe is a sound and mature program striving to achieve a proper balance between innovative basic research and economically viable practical applications. In the field of nuclear power, six entries are devoted to an analysis of the economics, safety and vulnerability of HTGR's. Theoretical work on more advanced concepts of hybrid and fusion reactors, is also a part of our research program. In plasma physics, the highly innovative applied topic of electrothermal propulsion was added to the more familiar research on laser induced plasmas and use of cool, low density plasmas to produce coatings and other thin layers of refractory materials. Results from the airborne radiometric survey carried out in collaboration with the Geological Survey of Israel and some of the techniques developed for this purpose are shown here for the first time. Of particular interest are the anomalies found in the Gevanim Valley in the Machtesh Ramon area and their interpretation. Noteworthy achievements in radiopharmaceutics include the development of a new improved 99 Mo/ 99m Tc generator and successful clinical tests of the innovative generator of ultrashort-lived 191m Ir. The food irradiation program has reached the stage of true commercial implementation: over 50 tons of spices and condiments were treated for the food industry in 1987. In the field of non-nuclear applications, important achievements were attained in the development of surgical holmium solid state lasers and their application to gastroenterology, cardiac and vascular surgery, urology, neurosurgery and other disciplines

  12. Laboratory research in homeopathy: pro.

    Science.gov (United States)

    Khuda-Bukhsh, Anisur R

    2006-12-01

    Homeopathy is a holistic method of treatment that uses ultralow doses of highly diluted natural substances originating from plants, minerals, or animals and is based on the principle of "like cures like." Despite being occasionally challenged for its scientific validity and mechanism of action, homeopathy continues to enjoy the confidence of millions of patients around the world who opt for this mode of treatment. Contrary to skeptics' views, research on home-opathy using modern tools mostly tends to support its efficacy and advocates new ideas toward understanding its mechanism of action. As part of a Point-Counterpoint feature, this review and its companion piece in this issue by Moffett et al (Integr Cancer Ther. 2006;5:333-342) are composed of a thesis section, a response section in reaction to the companion thesis, and a rebuttal section to address issues raised in the companion response.

  13. Controlled drill ampersand blast excavation at AECL's Underground Research Laboratory

    International Nuclear Information System (INIS)

    Kuzyk, G.W.; Onagi, D.P.; Thompson, P.M.

    1996-01-01

    A controlled drill and blast method has been developed and used to excavate the Underground Research Laboratory, a geotechnical facility constructed by Atomic Energy of Canada Limited (AECL) in crystalline rock. It has been demonstrated that the method can effectively reduce the excavation disturbed zone (EDZ) and is suitable for the construction of a used fuel disposal vault in the plutonic rock of the Canadian Shield

  14. The Plutonium Fuel Laboratory at Studsvik and Its Activities

    Energy Technology Data Exchange (ETDEWEB)

    Hultgren, A.; Berggren, G.; Brown, A.; Eng, H. U.; Forsyth, R. S. [AB Atomenergi, Studsvik (Sweden)

    1967-09-15

    The plutonium fuel laboratory at Studsvik is engaged in development work on plutonium-enriched fuel. At present, low enriched fuel for thermal reactors is being studied: work on fuel with a higher plutonium content for fast reactors is foreseen at a later date. So far only the pellet technique is under consideration, and a number of pellet rod specimens will be produced and irradiated in the reactor R2. These specimens include pellets from both co-precipitated uranium-plutonium salts and from physically mixed oxides. Comparison of these two materials will be extended to different density levels and different heat ratings. The methods and techniques used and studied include wet chemical work for powder preparation (continuous precipitation of Pu(IV)-oxalate with oxalic acid, continuous co-precipitation of plutonium and uranium with ammonia, optimization of.precipitation conditions using U(IV) and U(VI) respectively) ; powder preparation (drying, calcination, reduction, mixing, milling, binder addition, granulation); pellet preparation (pressing, debonding, sintering, inspection): encapsulation (charging, welding of end plug, helium filling, end sealing by welding, leak detection, decontamination); metallography (specimen preparation (moulding, polishing), etching, microscopy); structure investigations (thermal analysis (TG, DTA), X-ray diffraction, neutron diffraction, data handling by computer analysis); radiometric methods (direct plutonium determination by gamma spectrometry, non-destructive burn-up analysis by high resolution gamma spectrometry, using a Ge(Li) detector) ; rework of waste (recovery of plutonium from fuel waste by extraction with trilauryl amine and anion exchange). The plutonium fuel laboratory forms part of the Active Central Laboratory. The equipment is contained in four adjacent 10 x 15 m rooms; .for diffraction work and inactive uranium work additional space is available. All the forty glove boxes in operation except two are of AB Atomenergi

  15. Laboratory Directed Research ampersand Development Program

    International Nuclear Information System (INIS)

    Ogeka, G.J.; Romano, A.J.

    1993-12-01

    At Brookhaven National Laboratory the Laboratory Directed Research and Development (LDRD) Program is a discretionary research and development tool critical in maintaining the scientific excellence and vitality of the laboratory. It is also a means to stimulate the scientific community, fostering new science and technology ideas, which is the major factor in achieving and maintaining staff excellence, and a means to address national needs, within the overall mission of the Department of Energy and Brookhaven National Laboratory. This report summarizes research which was funded by this program during fiscal year 1993. The research fell in a number of broad technical and scientific categories: new directions for energy technologies; global change; radiation therapies and imaging; genetic studies; new directions for the development and utilization of BNL facilities; miscellaneous projects. Two million dollars in funding supported 28 projects which were spread throughout all BNL scientific departments

  16. Cyber Defense Research and Monitoring Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — This facility acts as a fusion point for bridging ARL's research in tactical and operational Information Assurance (IA) areas and the development and assessment of...

  17. Location | Frederick National Laboratory for Cancer Research

    Science.gov (United States)

    The Frederick National Laboratory for Cancer Research campus is located 50 miles northwest of Washington, D.C., and 50 miles west of Baltimore, Maryland, in Frederick, Maryland. Satellite locations include leased and government facilities extending s

  18. Nuclear Fusion Fuel Cycle Research Perspectives

    International Nuclear Information System (INIS)

    Chung, Hongsuk; Koo, Daeseo; Park, Jongcheol; Kim, Yeanjin; Yun, Sei-Hun

    2015-01-01

    As a part of the International Thermonuclear Experimental Reactor (ITER) Project, we at the Korea Atomic Energy Research Institute (KAERI) and our National Fusion Research Institute (NFRI) colleagues are investigating nuclear fusion fuel cycle hardware including a nuclear fusion fuel Storage and Delivery System (SDS). To have a better knowledge of the nuclear fusion fuel cycle, we present our research efforts not only on SDS but also on the Fuel Supply System (FS), Tokamak Exhaust Processing System (TEP), Isotope Separation System (ISS), and Detritiation System (DS). To have better knowledge of the nuclear fusion fuel cycle, we presented our research efforts not only on SDS but also on the Fuel Supply System (FS), Tokamak Exhaust Processing System (TEP), Isotope Separation System (ISS), and Detritiation System (DS). Our efforts to enhance the tritium confinement will be continued for the development of cleaner nuclear fusion power plants

  19. Safe handling of plutonium in research laboratories

    International Nuclear Information System (INIS)

    1976-01-01

    The training film illustrates the main basic requirements for the safe handling of small amounts of plutonium. The film is intended not only for people setting up plutonium research laboratories but also for all those who work in existing plutonium research laboratories. It was awarded the first prize in the category ''Protection of Workers'' at the international film festival organized by the 4th World Congress of the International Radiation Protection Association (IRPA) in Paris in April 1977

  20. Safe handling of plutonium in research laboratories

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1977-12-31

    The training film illustrates the main basic requirements for the safe handling of small amounts of plutonium. The film is intended not only for people setting up plutonium research laboratories but also for all those who work in existing plutonium research laboratories. It was awarded the first prize in the category ``Protection of Workers`` at the international film festival organized by the 4th World Congress of the International Radiation Protection Association (IRPA) in Paris in April 1977

  1. Pellet fueling development at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Foster, C.A.; Milora, S.L.; Schuresko, D.D.; Combs, S.K.; Lunsford, R.V.

    1982-01-01

    A pellet injector development program has been under way at the Oak Ridge National Laboratory (ORNL) since 1976 with the goals of developing D 2 , T 2 pellet fuel injectors capable of reliable repetitive fueling of reactors and of continued experimentation on contemporary plasma devices. The development has focused primarily on two types of injectors that show promise. One of these injectors is the centrifuge-type injector, which accelerates pellets in a high speed rotating track. The other is the gas or pneumatic gun, which accelerates pellets in a gun barrel using compressed helium of H 2 gas

  2. The Canadian research reactor spent fuel situation

    International Nuclear Information System (INIS)

    Ernst, P.C.

    1996-01-01

    This paper summarizes the present research reactor spent fuel situation in Canada. The research reactors currently operating are listed along with the types of fuel that they utilize. Other shut down research reactors contributing to the storage volume are included for completeness. The spent fuel storage facilities associated with these reactors and the methods used to determine criticality safety are described. Finally the current inventory of spent fuel and where it is stored is presented along with concerns for future storage. (author). 3 figs

  3. Unification of fuel elements for research reactors

    International Nuclear Information System (INIS)

    Vatulyn, A.V.; Stetskyi, Y.A.; Dobrikova, I.V.

    1997-01-01

    To the purpose of fuel elements unification the possibility of rod fuel assembly (FA) using in the cores of research reactors have been considered in this paper. The calculation results of geometric, hydraulic and thermotechnical parameters of rod assembly are submitted. Several designs of finned square fuel element and fuel assembly are proposed on base of analysis of rod FA characteristics in compare of tube ones. The fuel elements specimens and the model assembly are manufactured. The developed designs are the basis for further optimization after neutron-physical calculations of cores. (author)

  4. Shaft extension design at the Underground Research Laboratory, Pinawa, Manitoba

    International Nuclear Information System (INIS)

    Kuzyk, G.W.; Ball, A.E.

    1991-01-01

    AECL Research has constructed an underground laboratory for the research and development required for the Canadian Nuclear Fuel Waste Management Program. The experimental program in the laboratory will contribute to the assessment of the feasibility and safety of nuclear fuel waste disposal deep in stable plutonic rock. In 1988, AECL extended the shaft of the Underground Research Laboratory (URL) from the existing 255 m depth to a depth of 443 m in cooperation with the United States Department of Energy. The project, which involved carrying out research activities while excavation and construction work was in progress, required careful planning. To accommodate the research programs, full-face blasting with a burn cut was used to advance the shaft. Existing facilities at the URL had to be modified to accommodate an expanded underground facility at a new depth. This paper discusses the design criteria, shaft-sinking methods and approaches used to accommodate the research work during this shaft extension project. (11 refs., 11 figs.)

  5. Decommissioning of fuel PIE caves at Berkeley Nuclear Laboratories

    International Nuclear Information System (INIS)

    Brant, A.W.

    1990-01-01

    This paper describes the first major contract awarded to private industry to carry out decommissioning of a facility with significant radiation levels. The work required operatives to work in pressurised suits, entry times were significantly affected by sources of radiation in the Caves, being as low as thirty minutes per day initially. The Caves at Berkeley Nuclear Laboratories carry out post irradiation examination of fuel elements support units and reactor core components from CEGB power stations. The decommissioning work is part of an overall refurbishment of the facility to allow the receipt of AGR Fuel Stringer Component direct from power stations. The paper describes the decommissioning and decontamination of the facility from the remote removal and clean up work carried out by the client to the hands-on work. It includes reference to entry times, work patterns, interfaces with the client and the operations of the laboratory. Details of a specially adapted size reduction method are given. (Author)

  6. Update on Engine Combustion Research at Sandia National Laboratories

    International Nuclear Information System (INIS)

    Jay Keller; Gurpreet Singh

    2001-01-01

    The objectives of this paper are to describe the research efforts in diesel engine combustion at Sandia National Laboratories' Combustion Research Facility and to provide recent experimental results. We have four diesel engine experiments supported by the Department of Energy, Office of Heavy Vehicle Technologies: a one-cylinder version of a Cummins heavy-duty engine, a diesel simulation facility, a one-cylinder Caterpillar engine to evaluate combustion of alternative fuels, and a homogeneous-charge, compression ignition (HCCI) engine. Recent experimental results of diesel combustion research will be discussed and a description will be given of our HCCI experimental program and of our HCCI modeling work

  7. Safety analysis of IFR fuel processing in the Argonne National Laboratory Fuel Cycle Facility

    International Nuclear Information System (INIS)

    Charak, I; Pedersen, D.R.; Forrester, R.J.; Phipps, R.D.

    1993-01-01

    The Integral Fast Reactor (IFR) concept developed by Argonne National Laboratory (ANL) includes on-site processing and recycling of discharged core and blanket fuel materials. The process is being demonstrated in the Fuel Cycle Facility (FCF) at ANL's Idaho site. This paper describes the safety analyses that were performed in support of the FCF program; the resulting safety analysis report was the vehicle used to secure authorization to operate the facility and carry out the program, which is now under way. This work also provided some insights into safety-related issues of a commercial IFR fuel processing facility. These are also discussed

  8. NASA Ames Fluid Mechanics Laboratory research briefs

    Science.gov (United States)

    Davis, Sanford (Editor)

    1994-01-01

    The Ames Fluid Mechanics Laboratory research program is presented in a series of research briefs. Nineteen projects covering aeronautical fluid mechanics and related areas are discussed and augmented with the publication and presentation output of the Branch for the period 1990-1993.

  9. Corrosion of research reactor aluminium clad spent fuel in water

    International Nuclear Information System (INIS)

    2009-12-01

    reactor aluminium clad spent fuel. These corrosion activities were quite similar to those carried out in the CRP. Eight Member States participated in Phase-II of the CRP and five Member States in the Regional Project RLA/4/018. Two of the countries participating in the regional project were also participants in the CRP. This report documents the work performed in the IAEA Coordinated Research Project (CRP) on Corrosion of Research Reactor Aluminium Clad Spent Fuel in Water (Phase II) and in the IAEA's Technical Cooperation Regional Project for Latin America (RLA/4/018) entitled Management of Spent Fuel from Research Reactors. The key activity of both, the CRP and the Regional Project, consisted of the exposure of standard racks of corrosion coupons in the spent fuel pools of the participating research reactor laboratories and the evaluation of the coupons after predetermined exposure times, along with periodic monitoring of the storage water and evaluation of sediments settling in the spent fuel pools. The report includes: a description of the standard corrosion racks, experimental protocols, test procedures and water quality monitoring; the specific contributions by each of the participating laboratories; a compilation of all experimental results obtained and the analysis and discussion of the results, along with conclusions

  10. Fuels Inventories in the Los Alamos National Laboratory Region: 1997

    International Nuclear Information System (INIS)

    Balice, R.G.; Oswald, B.P.; Martin, C.

    1999-01-01

    Fifty-four sites were surveyed for fuel levels, vegetational structures, and topographic characteristics. Most of the surveyed sites were on Los Alamos National Laboratory property, however, some surveys were also conducted on U.S. Forest Service property. The overall vegetation of these sites ranged from pinon-juniper woodlands to ponderosa pine forests to mixed conifer forests, and the topographic positions included canyons, mesas, and mountains. The results of these surveys indicate that the understory fuels are the greatest in mixed conifer forests and that overstory fuels are greatest in both mixed conifer forests and ponderosa pine forests on mesas. The geographic distribution of these fuels would suggest a most credible wildfire scenario for the Los Alamos region. Three major fires have occurred since 1954 and these fires behaved in a manner that is consistent with this scenario. The most credible wildfire scenario was also supported by the results of BEHAVE modeling that used the fuels inventory data as inputs. Output from the BEHAVE model suggested that catastrophic wildfires would continue to occur during any season with sufficiently dry, windy weather

  11. Fuel cell research: Towards efficient energy

    CSIR Research Space (South Africa)

    Rohwer, MB

    2008-11-01

    Full Text Available fuel cells by optimising the loading of catalyst (being expensive noble metals) and ionomer; 2) Improving conventional acidic direct alcohol fuel cells by developing more efficient catalysts and by investigating other fuels than methanol; 3... these components add significantly to the overall cost of a PEMFC. 1 We focused our research activities on: 1) The effect of the loading of catalytic ink on cell performance; 2) The effect of the ionomer content in the catalytic ink; 3) Testing...

  12. Fuel quality control: Five years of activity in laboratories

    International Nuclear Information System (INIS)

    Bettinelli, M.; Cimini, G.; Durello, G.; Lucchesi, P.L.

    1991-01-01

    A description of how ENEL (Italian National Electricity Board) carries out the activity of fuel quality control is given, and the results of the Round Robin circuit which has been operating for five years in laboratories regulary performing the control analyses of these products are reported. The laboratories taking part in the Round Robin circuit are 41 (out of which 35 are ENEL laboratories and 6 are owned by external companies) and they are situated throughout Italy; the controlled parameters are the following: heat of combustion (PCS), sulphur (S), vanadium (V) and asphaltenes (ASF); the adopted methods are the official ASTM or IP ones. The statistical analysis of the results has permitted, for every parameter, the calculation of the repeatability and the reproducibility which, in most cases, have turned out to be in keeping with the values provided for in the regulations. Among the collateral initiatives promoted in the framework of this Round Robin, the following are reported: preparation of standards of fuel oil with a known content of a sulphur and vanadium; expediting visits to all the ENEL laboratories participating in the RRT; publication of a handbook of the adopted analysis methods (in Italian); definition of guide-lines on the right selection of new automatic equipment

  13. Research on CDA for advanced fuel FBR

    International Nuclear Information System (INIS)

    Hirano, Go; Hirakawa, Naohiro; Kawada, Ken-ichi; Niwa, Hazime.

    1997-03-01

    For the purpose of evaluating possibility of the re-criticality of a metallic fueled reactor, Tohoku university and Power Reactor and Nuclear Fuel Development Corporation have made a joint research entitled 'Research on CDA for advanced fuel FBR'. The results of this year are the following. The accident initiator considered is a loss-of-flow accident with ATWS. The LOF analysis was performed for the metallic fueled 600 MWe homogeneous two region reactors, both for a metallic fuel only and for a metallic fuel core with ZrH pin. The SAS3D CDA initiation phase analysis code was used to investigate the re-criticality potential at the severe accident. The change mainly in the constants was necessary to apply the code for the analysis of a metallic fueled reactor. These changes were made by assuming appropriate models. LOF with flow decay half time of t 1/2 =0.5(s) (all blackout case) and 5.5(s) (ordinary LOF case) were analyzed. Independent of the conditions of the analysis, the results show all the cases could avoid to become prompt-critical. Depending on the analysis condition, it becomes necessary to transfer to the transient phase, it is also shown there is a possibility to avoid re-criticality due to the motion of molten fuel both for the metallic fuel and for the metallic fuel with ZrH moderator. However, because of the constants used for the material property the results might overestimate the fuel motion. It is shown that the moderator is effective to terminate the accident at an early stage. The behavior of metallic fueled reactors at CDA was analyzed with SAS3D code by modifying the constants of material properties to be applied to the reactor. It is shown that a metallic fueled reactor has a possibility to avoid re-criticality at CDA. (J.P.N.)

  14. Fuel Fabrication Capability Research and Development Plan

    Energy Technology Data Exchange (ETDEWEB)

    Senor, David J.; Burkes, Douglas

    2013-06-28

    The purpose of this document is to provide a comprehensive review of the mission of the Fuel Fabrication Capability (FFC) within the Global Threat Reduction Initiative (GTRI) Convert Program, along with research and development (R&D) needs that have been identified as necessary to ensuring mission success. The design and fabrication of successful nuclear fuels must be closely linked endeavors.

  15. Research reactor spent fuel in Ukraine

    International Nuclear Information System (INIS)

    Trofimenko, A.P.

    1996-01-01

    This paper describes the research reactors in Ukraine, their spent fuel facilities and spent fuel management problems. Nuclear sciences, technology and industry are highly developed in Ukraine. There are 5 NPPs in the country with 14 operating reactors which have total power capacity of 12,800 MW

  16. Advanced fuel in the Budapest research reactor

    International Nuclear Information System (INIS)

    Hargitai, T.; Vidovsky, I.

    1997-01-01

    The Budapest Research Reactor, the first nuclear facility of Hungary, started to operate in 1959. The main goal of the reactor is to serve neutron research, but applications as neutron radiography, radioisotope production, pressure vessel surveillance test, etc. are important as well. The Budapest Research Reactor is a tank type reactor, moderated and cooled by light water. After a reconstruction and upgrading in 1967 the VVR-SM type fuel elements were used in it. These fuel elements provided a thermal power of 5 MW in the period 1967-1986 and 10 MW after the reconstruction from 1992. In the late eighties the Russian vendor changed the fuel elements slightly, i.e. the main parameters of the fuel remained unchanged, however a higher uranium content was reached. This new fuel is called VVR-M2. The geometry of VVR-SM and VVR-M2 are identical, allowing the use to load old and new fuel assemblies together to the active core. The first new type fuel assemblies were loaded to the Budapest Research Reactor in 1996. The present paper describes the operational experience with the new type of fuel elements in Hungary. (author)

  17. Research reactor de-fueling and fuel shipment

    International Nuclear Information System (INIS)

    Ice, R.D.; Jawdeh, E.; Strydom, J.

    1998-01-01

    Planning for the Georgia Institute of Technology Research Reactor operations during the 1996 Summer Olympic Games began in early 1995. Before any details could be outlined, several preliminary administrative decisions had to be agreed upon by state, city, and university officials. The two major administrative decisions involving the reactor were (1) the security level and requirements and (2) the fuel status of the reactor. The Georgia Tech Research Reactor (GTRR) was a heavy-water moderated and cooled reactor, fueled with high-enriched uranium. The reactor was first licensed in 1964 with an engineered lifetime of thirty years. The reactor was intended for use in research applications and as a teaching facility for nuclear engineering students and reactor operators. Approximately one year prior to the olympics, the Georgia Tech administration decided that the GTRR fuel would be removed. In addition, a heightened, beyond regulatory requirements, security system was to be implemented. This report describes the scheduling, operations, and procedures

  18. Savannah River Laboratory monthly report: 238Pu fuel form processes

    International Nuclear Information System (INIS)

    1976-01-01

    Progress in the Savannah River 238 Pu Fuel Form Program is discussed. Goals of the Savannah River Laboratory (SRL) program are to provide technical support for the transfer of the 238 Pu fuel form fabrication operations from Mound Laboratory to new facilities being built at the Savannah River Plant (SRP), to provide the technical basis for 238 Pu scrap recovery at SRP, and to assist in sustaining plant operations. During the period it was found that the density of hot-pressed 238 PuO 2 pellets decreased as the particle size of ball-milled powder decreased;the surface area of calcined 238 PuO 2 powder increased with increasing precipitation temperature and may be related to the variation in ball-milling response observed among different H Area B-Line batches; calcined PuO 2 produced by Pu(III) reverse-strike precipitation was directly fabricated into a pellet without ball milling, slugging, or sharding. The pellet had good appearance with acceptable density and dimensional stability, and heat transfer measurements and calculations showed that the use of hollow aluminum sleeves in the plutonium fuel fabrication (PuFF) storage vault reduced the temperature of shipping cans to 170 0 C and will reduce the temperature at the center of pure plutonium oxide (PPO) spheres to 580 0 C

  19. Alternative Fuels DISI Engine Research ? Autoignition Metrics.

    Energy Technology Data Exchange (ETDEWEB)

    Sjoberg, Carl Magnus Goran [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Vuilleumier, David [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2018-02-01

    Improved engine efficiency is required to comply with future fuel economy standards. Alternative fuels have the potential to enable more efficient engines while addressing concerns about energy security. This project contributes to the science base needed by industry to develop highly efficient direct injection spark igniton (DISI) engines that also beneficially exploit the different properties of alternative fuels. Here, the emphasis is on quantifying autoignition behavior for a range of spark-ignited engine conditions, including directly injected boosted conditions. The efficiency of stoichiometrically operated spark ignition engines is often limited by fuel-oxidizer end-gas autoignition, which can result in engine knock. A fuel’s knock resistance is assessed empirically by the Research Octane Number (RON) and Motor Octane Number (MON) tests. By clarifying how these two tests relate to the autoignition behavior of conventional and alternative fuel formulations, fuel design guidelines for enhanced engine efficiency can be developed.

  20. Spent fuel storage cask testing and operational experience at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Eslinger, L.E.; Schmitt, R.C.

    1989-01-01

    Spent-fuel storage cask research, development, and demonstration activities are being performed for the U.S. Department of Energy's (DOE's) Office of Civilian Radioactive Waste Management (OCRWM) as a part of the storage cask testing program. The cask testing program at federal sites and other locations supports the Nuclear Waste Policy Act (NWPA) and DOE objectives for cooperative demonstrations with the cask vendors and utilities for development of at-reactor dry cask storage capabilities for spent nuclear fuel assemblies. One research and development program for the storage cask performance testing of metal storage cask was initiated through a cooperative agreement between Virginia Power and DOE in 1984. The performance testing was conducted for the DOE and the Electric Power Research Institute by the Pacific Northwest laboratory, operated for DOE by Battelle Memorial Institute, and the Idaho National Engineering Laboratory (INEL), operated for DOE by EG ampersand G Idaho, Inc. In 1988 a cooperative agreement was entered into by DOE with Pacific Sierra Nuclear Associates (PSN) for performance testing of the PSN concrete Ventilated Storage Cask. Another closely related activity involving INEL is a transportable storage cask project identified as the Nuclear Fuel Services Spent-Fuel Shipping/Storage Cask Demonstration Project. The purpose of this project is to demonstrate the feasibility of packing, transporting, and storing commercial spent fuel in dual-purpose transport/storage casks

  1. Idaho National Laboratory Research & Development Impacts

    Energy Technology Data Exchange (ETDEWEB)

    Stricker, Nicole [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-01-01

    Technological advances that drive economic growth require both public and private investment. The U.S. Department of Energy’s national laboratories play a crucial role by conducting the type of research, testing and evaluation that is beyond the scope of regulators, academia or industry. Examples of such work from the past year can be found in these pages. Idaho National Laboratory’s engineering and applied science expertise helps deploy new technologies for nuclear energy, national security and new energy resources. Unique infrastructure, nuclear material inventory and vast expertise converge at INL, the nation’s nuclear energy laboratory. Productive partnerships with academia, industry and government agencies deliver high-impact outcomes. This edition of INL’s Impacts magazine highlights national and regional leadership efforts, growing capabilities, notable collaborations, and technology innovations. Please take a few minutes to learn more about the critical resources and transformative research at one of the nation’s premier applied science laboratories.

  2. 1999 LDRD Laboratory Directed Research and Development

    Energy Technology Data Exchange (ETDEWEB)

    Rita Spencer; Kyle Wheeler

    2000-06-01

    This is the FY 1999 Progress Report for the Laboratory Directed Research and Development (LDRD) Program at Los Alamos National Laboratory. It gives an overview of the LDRD Program, summarizes work done on individual research projects, relates the projects to major Laboratory program sponsors, and provides an index to the principal investigators. Project summaries are grouped by their LDRD component: Competency Development, Program Development, and Individual Projects. Within each component, they are further grouped into nine technical categories: (1) materials science, (2) chemistry, (3) mathematics and computational science, (4) atomic, molecular, optical, and plasma physics, fluids, and particle beams, (5) engineering science, (6) instrumentation and diagnostics, (7) geoscience, space science, and astrophysics, (8) nuclear and particle physics, and (9) bioscience.

  3. Summary of fuel safety research meeting 2005

    International Nuclear Information System (INIS)

    Fuketa, Toyoshi; Nakamura, Takehiko; Nagase, Fumihisa; Nakamura, Jinichi; Suzuki, Motoe; Sasajima, Hideo; Sugiyama, Tomoyuki; Amaya, Masaki; Kudo, Tamotsu; Chuto, Toshinori; Tomiyasu, Kunihiko; Udagawa, Yutaka; Ikehata, Hisashi; Kida, Mitsuko; Ikatsu, Nobuhiko; Hosoyamada, Ryuji; Hamanishi, Eizou; Iwasaki, Ryo; Ozawa, Masaaki

    2006-03-01

    Fuel Safety Research Meeting 2005, which was organized by the Japan Atomic Energy Agency (Establishment of the new organization in Oct. 1, 2005 integrated of JAERI and JNC) was held on March 2-3, 2005 at Toshi Center Hotel, Tokyo. The purposes of the meeting are to present and discuss the results of experiments and analyses on reactor fuel safety and to exchange views and experiences among the participants. The technical topics of the meting covered the status of fuel safety research activities, fuel behavior under Reactivity Initiated Accident (RIA) and Loss of coolant accident (LOCA) conditions, high fuel behavior, and radionuclide release under severe accident conditions. This summary contains all the abstracts and sheets of viewgraph presented in the meeting. (author)

  4. Fuels for Canadian research reactors

    International Nuclear Information System (INIS)

    Feraday, M.A.

    1993-01-01

    For a period of about 10 years AECL had a significant program looking into the possibility of developing U 3 Si as a high density replacement for the UO 2 pellet fuel in use in CANDU power reactors. The element design consisted of a Zircaloy-clad U 3 Si rod containing suitable voidage to accommodate swelling. We found that the binary U 3 Si could not meet the defect criterion for our power reactors, i.e., one month in 300 degree C water with a defect in the sheath and no significant damage to the element. Since U 3 Si could not do the job, a new corrosion resistant ternary U-Si-Al alloy was developed and patented. Fuel elements containing this alloy came close to meeting the defect criterion and showed slightly better irradiation stability than U 3 Si. Shortly after this, the program was terminated for other reasons. We have made much of this experience available to the Low Enrichment Fuel Development Program and will be glad to supply further data to assist this program

  5. Geoscience research for the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Whitaker, S.H.

    1987-01-01

    The Canadian Nuclear Fuel Waste Management Program is assessing the concept of deep disposal of nuclear fuel waste in plutonic rock. As part of that assessment, a broad program of geoscience and geotechnical work has been undertaken to develop methods for characterizing sites, incorporating geotechnical data into disposal facility design, and incorporating geotechnical data into environmental and safety assessment of the disposal system. General field investigations are conducted throughout the Precambrian Shield, subsurface investigations are conducted at designated field research areas, and in situ rock mass experiments are being conducted in an Underground Research Laboratory. Samples from the field research areas and elsewhere are subjected to a wide range of tests and experiments in the laboratory to develop an understanding of the physical and chemical processes involved in ground-water-rock-waste interactions. Mathematical models to simulate these processes are developed, verified and validated. 114 refs.; 13 figs

  6. Laboratory and cyclotron requirements for PET research

    International Nuclear Information System (INIS)

    Schlyer, D.J.

    1993-01-01

    The requirements for carrying out PET research can vary widely depending on the type of basic research being carried out and the extent of a clinical program at a particular center. The type of accelerator and laboratory facilities will, of course, depend on the exact mix. These centers have been divided into four categories. 1. Clinical PET with no radionuclide production facilities, 2. clinical PET with some radionuclide production facilities, 3. clinical PET with research support, and 4. a PET research facility developing new tracers and exploring clinical applications. Guidelines for the choice of an accelerator based on these categories and the practical yields of the common nuclear reactions for production of PET isotopes have been developed and are detailed. Guidelines as to the size and physical layout of the laboratory space necessary for the synthesis of various radiopharmaceuticals have also been developed and are presented. Important utility and air flow considerations are explored

  7. Occupational radiation exposures in research laboratories

    International Nuclear Information System (INIS)

    Vaccari, S.; Papotti, E.; Pedrazzi, G.

    2006-01-01

    Radioactive sources are widely used in many research activities at University centers. In particular, the activities concerning use of sealed form ( 57 Co in Moessbauer application) and unsealed form ( 3 H, 14 C, 32 P in radioisotope laboratories) are analyzed. The radiological impact of these materials and potential effective doses to researchers and members of the public were evaluated to show compliance with regulatory limits. A review of the procedures performed by researchers and technicians in the research laboratories with the relative dose evaluations is presented in different situations, including normal operations and emergency situations, for example the fire. A study of the possible exposure to radiation by workers, restricted groups of people, and public in general, as well as environmental releases, is presented. (authors)

  8. Occupational radiation exposures in research laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Vaccari, S.; Papotti, E. [Parma Univ., Health Physics (Italy); Pedrazzi, G. [Parma Univ., Dept. of Public Health (Italy)

    2006-07-01

    Radioactive sources are widely used in many research activities at University centers. In particular, the activities concerning use of sealed form ({sup 57}Co in Moessbauer application) and unsealed form ({sup 3}H, {sup 14}C, {sup 32}P in radioisotope laboratories) are analyzed. The radiological impact of these materials and potential effective doses to researchers and members of the public were evaluated to show compliance with regulatory limits. A review of the procedures performed by researchers and technicians in the research laboratories with the relative dose evaluations is presented in different situations, including normal operations and emergency situations, for example the fire. A study of the possible exposure to radiation by workers, restricted groups of people, and public in general, as well as environmental releases, is presented. (authors)

  9. National Renewable Energy Laboratory 2004 Research Review

    Energy Technology Data Exchange (ETDEWEB)

    2005-03-01

    In-depth articles on several NREL technologies and advances, including: aligning quantum dots and related nanoscience and nanotechnology research; using NREL's Advanced Automotive Manikin (ADAM) to help test and design ancillary automotive systems; and harvesting ocean wind to generate electricity with deep-water wind turbines. Also covered are NREL news, research updates, and awards and honors received by the Laboratory.

  10. Mobile robotics research at Sandia National Laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Morse, W.D.

    1998-09-01

    Sandia is a National Security Laboratory providing scientific and engineering solutions to meet national needs for both government and industry. As part of this mission, the Intelligent Systems and Robotics Center conducts research and development in robotics and intelligent machine technologies. An overview of Sandia`s mobile robotics research is provided. Recent achievements and future directions in the areas of coordinated mobile manipulation, small smart machines, world modeling, and special application robots are presented.

  11. Research laboratories annual report. 1973 and 1974

    International Nuclear Information System (INIS)

    1975-02-01

    This report presents brief summaries of the research carried out at the Israel A.E.C. laboratories during the two years 1973 and 1974 in the following fields: theoretical physics and chemistry, neutron and reactor physics, solid state physics and metallurgy, laser-induced plasma research, nuclear physics and chemistry, radiation chemistry and applications of radiation and radioisotopes, physical and inorganic chemistry, analytical chemistry, health physics, environmental studies, instrumentation and techniques. (B.G.)

  12. Radionuclide release from research reactor spent fuel

    Energy Technology Data Exchange (ETDEWEB)

    Curtius, H., E-mail: h.curtius@fz-juelich.de [Forschungszentrum Juelich, Institut fuer Energieforschung, IEF-6 Sicherheitsforschung und Reaktortechnik, Geb. 05.3, D-52425 Juelich (Germany); Kaiser, G.; Mueller, E.; Bosbach, D. [Forschungszentrum Juelich, Institut fuer Energieforschung, IEF-6 Sicherheitsforschung und Reaktortechnik, Geb. 05.3, D-52425 Juelich (Germany)

    2011-09-01

    Numerous investigations with respect to LWR fuel under non oxidizing repository relevant conditions were performed. The results obtained indicate slow corrosion rates for the UO{sub 2} fuel matrix. Special fuel-types (mostly dispersed fuels, high enriched in {sup 235}U, cladded with aluminium) are used in German research reactors, whereas in German nuclear power plants, UO{sub 2}-fuel (LWR fuel, enrichment in {sup 235}U up to 5%, zircaloy as cladding) is used. Irradiated research reactor fuels contribute less than 1% to the total waste volume. In Germany, the state is responsible for fuel operation and for fuel back-end options. The institute for energy research (IEF-6) at the Research Center Juelich performs investigation with irradiated research reactor spent fuels under repository relevant conditions. In the study, the corrosion of research reactor spent fuel has been investigated in MgCl{sub 2}-rich salt brine and the radionuclide release fractions have been determined. Leaching experiments in brine with two different research reactor fuel-types were performed in a hot cell facility in order to determine the corrosion behaviour and the radionuclide release fractions. The corrosion of two dispersed research reactor fuel-types (UAl{sub x}-Al and U{sub 3}Si{sub 2}-Al) was studied in 400 mL MgCl{sub 2}-rich salt brine in the presence of Fe{sup 2+} under static and initially anoxic conditions. Within these experimental parameters, both fuel types corroded in the experimental time period of 3.5 years completely, and secondary alteration phases were formed. After complete corrosion of the used research reactor fuel samples, the inventories of Cs and Sr were quantitatively detected in solution. Solution concentrations of Am and Eu were lower than the solubility of Am(OH){sub 3}(s) and Eu(OH){sub 3}(s) solid phases respectively, and may be controlled by sorption processes. Pu concentrations may be controlled by Pu(IV) polymer species, but the presence of Pu(V) and Pu

  13. Virtual laboratory for fusion research in Japan

    International Nuclear Information System (INIS)

    Tsuda, K.; Nagayama, Y.; Yamamoto, T.; Horiuchi, R.; Ishiguro, S.; Takami, S.

    2008-01-01

    A virtual laboratory system for nuclear fusion research in Japan has been developed using SuperSINET, which is a super high-speed network operated by National Institute of Informatics. Sixteen sites including major Japanese universities, Japan Atomic Energy Agency and National Institute for Fusion Science (NIFS) are mutually connected to SuperSINET with the speed of 1 Gbps by the end of 2006 fiscal year. Collaboration categories in this virtual laboratory are as follows: the large helical device (LHD) remote participation; the remote use of supercomputer system; and the all Japan ST (Spherical Tokamak) research program. This virtual laboratory is a closed network system, and is connected to the Internet through the NIFS firewall in order to keep higher security. Collaborators in a remote station can control their diagnostic devices at LHD and analyze the LHD data as they were at the LHD control room. Researchers in a remote station can use the supercomputer of NIFS in the same environment as NIFS. In this paper, we will describe detail of technologies and the present status of the virtual laboratory. Furthermore, the items that should be developed in the near future are also described

  14. Laboratory Directed Research and Development Program

    Energy Technology Data Exchange (ETDEWEB)

    Ogeka, G.J.

    1991-12-01

    Today, new ideas and opportunities, fostering the advancement of technology, are occurring at an ever-increasing rate. It, therefore, seems appropriate that a vehicle be available which fosters the development of these new ideas and technologies, promotes the early exploration and exploitation of creative and innovative concepts, and which develops new fundable'' R D projects and programs. At Brookhaven National Laboratory (BNL), one such method is through its Laboratory Directed Research and Development (LDRD) Program. This discretionary research and development tool is critical in maintaining the scientific excellence and vitality of the Laboratory. Additionally, it is a means to stimulate the scientific community, fostering new science and technology ideas, which is the major factor achieving and maintaining staff excellence, and a means to address national needs, with the overall mission of the Department of Energy (DOE) and the Brookhaven National Laboratory. The Project Summaries with their accomplishments described in this report reflect the above. Aside from leading to new fundable or promising programs and producing especially noteworthy research, they have resulted in numerous publications in various professional and scientific journals, and presentations at meetings and forums.

  15. Laboratory research irradiators with enhanced security features

    International Nuclear Information System (INIS)

    Srivastava, Piyush

    2016-01-01

    Over the years BRIT has developed state of art technology for laboratory research irradiators which are suited most for carrying out research and development works in the fields of radiation processing. These equipment which house radioactive sources up to 14 kCi are having a number of features to meet users requirements. They are manufactured as per the national and International standards of safety codes. The paper deals with design, development and application aspects of laboratory research irradiator called Gamma Chamber and also the new security features planned for incorporation in the equipment. Equipment are being regularly manufactured, supplied and installed by BRIT in India and Abroad. There is a number of such equipment in use at different institutions and are found to be very useful. (author)

  16. Laboratory research irradiators with enhanced security features

    International Nuclear Information System (INIS)

    Srivastava, Piyush

    2014-01-01

    Over the years BRIT has developed state of art technology for laboratory research irradiators which are suited most for carrying out research and development works in the fields of radiation processing. These equipment which house radioactive sources up to 14 kCi are having a number of features to meet users requirements. They are manufactured as per the national and International standards of safety codes. The paper deals with design, development and application aspects of laboratory research irradiator called Gamma Chamber and also the new security features planned for incorporation in the equipment. Equipment are being regularly manufactured, supplied and installed by BRIT in India and Abroad. There are a number of such equipment in use at different institutions and are found to be very useful. (author)

  17. Report on operation utilization and technical development of research reactors and hot laboratory

    International Nuclear Information System (INIS)

    1982-03-01

    Activities of the Division of Research Reactor Operation in fiscal 1980 are described. The division is responsible for operation and maintenance of JRR-2, JRR-3, JRR-4 and Hot Laboratory. In the above connection, various other works are performed, including technical management of fuel and coolant, radiation control, irradiation technique, etc. In Hot Laboratory, postirradiation examinations of fuels and materials are made, and also development of examination methods. (author)

  18. Report on operation, utilization and technical development of research reactors and hot laboratory

    International Nuclear Information System (INIS)

    1980-03-01

    Activities of the Division of Research Reactor Operation in fiscal 1978 are described. The division is responsible for operation and maintenance of JRR-2, JRR-3, JRR-4 and Hot Laboratory. In the above connection, various other works are performed, including technical management of fuel and coolant, radiation control, irradiation technique, etc. In Hot Laboratory, postirradiation examinations of fuels and materials are made, and also development of examination methods. (author)

  19. Report on operation, utilization and technical development of Research Reactors and Hot Laboratory

    International Nuclear Information System (INIS)

    1984-10-01

    Activities of the Division of Research Reactor Operation in fiscal 1981 are described. The division is responsible for operation and maintenance of JRR-2, JRR-3, JRR-4 and Hot Laboratory. In the above connection, various other works are performed, including technical management of fuel and coolant, radiation control, irradiation technique, etc. In Hot Laboratory, postirradiation examinations of fuels and materials are made, and also development of examination methods. (author)

  20. Global nuclear energy partnership fuels transient testing at the Sandia National Laboratories nuclear facilities : planning and facility infrastructure options

    International Nuclear Information System (INIS)

    Kelly, John E.; Wright, Steven Alan; Tikare, Veena; MacLean, Heather J.; Parma, Edward J.Jr; Peters, Curtis D.; Vernon, Milton E.; Pickard, Paul S.

    2007-01-01

    The Global Nuclear Energy Partnership fuels development program is currently developing metallic, oxide, and nitride fuel forms as candidate fuels for an Advanced Burner Reactor. The Advance Burner Reactor is being designed to fission actinides efficiently, thereby reducing the long-term storage requirements for spent fuel repositories. Small fuel samples are being fabricated and evaluated with different transuranic loadings and with extensive burnup using the Advanced Test Reactor. During the next several years, numerous fuel samples will be fabricated, evaluated, and tested, with the eventual goal of developing a transmuter fuel database that supports the down selection to the most suitable fuel type. To provide a comparative database of safety margins for the range of potential transmuter fuels, this report describes a plan to conduct a set of early transient tests in the Annular Core Research Reactor at Sandia National Laboratories. The Annular Core Research Reactor is uniquely qualified to perform these types of tests because of its wide range of operating capabilities and large dry central cavity which extents through the center of the core. The goal of the fuels testing program is to demonstrate that the design and fabrication processes are of sufficient quality that the fuel will not fail at its design limit--up to a specified burnup, power density, and operating temperature. Transient testing is required to determine the fuel pin failure thresholds and to demonstrate that adequate fuel failure margins exist during the postulated design basis accidents

  1. Global nuclear energy partnership fuels transient testing at the Sandia National Laboratories nuclear facilities : planning and facility infrastructure options.

    Energy Technology Data Exchange (ETDEWEB)

    Kelly, John E.; Wright, Steven Alan; Tikare, Veena; MacLean, Heather J. (Idaho National Laboratory, Idaho Falls, ID); Parma, Edward J., Jr.; Peters, Curtis D.; Vernon, Milton E.; Pickard, Paul S.

    2007-10-01

    The Global Nuclear Energy Partnership fuels development program is currently developing metallic, oxide, and nitride fuel forms as candidate fuels for an Advanced Burner Reactor. The Advance Burner Reactor is being designed to fission actinides efficiently, thereby reducing the long-term storage requirements for spent fuel repositories. Small fuel samples are being fabricated and evaluated with different transuranic loadings and with extensive burnup using the Advanced Test Reactor. During the next several years, numerous fuel samples will be fabricated, evaluated, and tested, with the eventual goal of developing a transmuter fuel database that supports the down selection to the most suitable fuel type. To provide a comparative database of safety margins for the range of potential transmuter fuels, this report describes a plan to conduct a set of early transient tests in the Annular Core Research Reactor at Sandia National Laboratories. The Annular Core Research Reactor is uniquely qualified to perform these types of tests because of its wide range of operating capabilities and large dry central cavity which extents through the center of the core. The goal of the fuels testing program is to demonstrate that the design and fabrication processes are of sufficient quality that the fuel will not fail at its design limit--up to a specified burnup, power density, and operating temperature. Transient testing is required to determine the fuel pin failure thresholds and to demonstrate that adequate fuel failure margins exist during the postulated design basis accidents.

  2. Laboratory Directed Research and Development FY 2000

    International Nuclear Information System (INIS)

    Hansen, Todd; Levy, Karin

    2001-01-01

    The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab or LBNL) is a multi-program national research facility operated by the University of California for the Department of Energy (DOE). As an integral element of DOE's National Laboratory System, Berkeley Lab supports DOE's missions in fundamental science, energy resources, and environmental quality. Berkeley Lab programs advance four distinct goals for DOE and the nation: (1) To perform leading multidisciplinary research in the computing sciences, physical sciences, energy sciences, biosciences, and general sciences in a manner that ensures employee and public safety and protection of the environment. (2) To develop and operate unique national experimental facilities for qualified investigators. (3) To educate and train future generations of scientists and engineers to promote national science and education goals. (4) To transfer knowledge and technological innovations and to foster productive relationships among Berkeley Lab's research programs, universities, and industry in order to promote national economic competitiveness. Annual report on Laboratory Directed Research and Development for FY2000

  3. Laboratory Directed Research and Development FY 2000

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, Todd; Levy, Karin

    2001-02-27

    The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab or LBNL) is a multi-program national research facility operated by the University of California for the Department of Energy (DOE). As an integral element of DOE's National Laboratory System, Berkeley Lab supports DOE's missions in fundamental science, energy resources, and environmental quality. Berkeley Lab programs advance four distinct goals for DOE and the nation: (1) To perform leading multidisciplinary research in the computing sciences, physical sciences, energy sciences, biosciences, and general sciences in a manner that ensures employee and public safety and protection of the environment. (2) To develop and operate unique national experimental facilities for qualified investigators. (3) To educate and train future generations of scientists and engineers to promote national science and education goals. (4) To transfer knowledge and technological innovations and to foster productive relationships among Berkeley Lab's research programs, universities, and industry in order to promote national economic competitiveness. Annual report on Laboratory Directed Research and Development for FY2000.

  4. Fuel element gamma scanning at the Oak Ridge Research Reactor

    International Nuclear Information System (INIS)

    Hobbs, R.W.

    1987-01-01

    In January 1986, a demonstration program was begun at the Oak Ridge Research Reactor (ORR) to convert operations from high-enrichment uranium fuel to the newly developed U 3 Si 2 low-enrichment fuel. A primary program objective is to validate neutronics calculations conducted by the Reduced Enrichment in Research and Test Reactors Program at Argonne National Laboratory. Accordingly, a new method for determining core-power distribution has been developed. The method is based on gamma-ray spectroscopy measurements to determine the relative levels of 140 La in the fuel elements after each operating cycle. The measurement and data analyses are described and a comparison of measured and diffusion theory calculated values of the core-power distribution is presented in this paper

  5. Research on nondestructive examination methods for CANDU fuel channel inspection

    International Nuclear Information System (INIS)

    Soare, M.; Petriu, F.; Toma, V.; Revenco, V.; Calinescu, A.; Ciocan, R.; Iordache, C.; Popescu, L.; Mihalache, M.; Murgescu, C.

    1995-01-01

    The requirements of the 1994 edition of CAN/CSA-N285.4 Periodic Inspection Standard, which address all known and postulated degradation mechanisms and introduce material surveillance demands, involve a growing need for improved nondestructive examination (NDE) methods and technologies. In order to have a proper technical support in its decisions concerning fuel channel inspections at Cernavoda NPP, the Romanian Power Authority (RENEL) initiated a Research Program regarding the nondestructive characterization of the fuel channels structural integrity. The paper presents the most significant results obtained on this Research Program: the ENDUS experimental system for Laboratory simulation of the fuel channel inspection, ultrasonic Rayleigh-Lamb waves technique for pressure tubes examination, phase analysis technique for near-surface flaws, influence of the metallurgical state of the pressure tube material on the eddy current defectoscopic signals, characterization of plastic deformation and fracture of zirconium alloys by acoustic emission. (author)

  6. MANAGING SPENT NUCLEAR FUEL WASTES AT THE IDAHO NATIONAL LABORATORY

    Energy Technology Data Exchange (ETDEWEB)

    Hill, Thomas J

    2005-09-01

    The Idaho National Engineering Laboratory (INL) has a large inventory of diverse types of spent nuclear fuel (SNF). This legacy is in part due to the history of the INL as the National Reactor Testing Station, in part to its mission to recover highly enriched uranium from SNF and in part to it’s mission to test and examine SNF after irradiation. The INL also has a large diversity of SNF storage facility, some dating back 50 years in the site history. The success of the INL SNF program is measured by its ability to: 1) achieve safe existing storage, 2) continue to receive SNF from other locations, both foreign and domestic, 3) repackage SNF from wet storage to interim dry storage, and 4) prepare the SNF for dispositioning in a federal repository. Because of the diversity in the SNF and the facilities at the INL, the INL is addressing almost very condition that may exist in the SNF world. Many of solutions developed by the INL are applicable to other SNF storage sites as they develop their management strategy. The SNF being managed by the INL are in a variety of conditions, from intact assemblies to individual rods or plates to powders, rubble, and metallurgical mounts. Some of the fuel has been in wet storage for over forty years. The fuel is stored bare, or in metal cans and either wet under water or dry in vaults, caissons or casks. Inspections have shown varying degrees of corrosion and degradation of the fuel and the storage cans. Some of the fuel has been recanned under water, and the conditions of the fuel inside the second or third can are unknown. The fuel has been stored in one of 10 different facilities: five wet pools and one casks storage pad, one vault, two generations of caisson facilities, and one modular Independent Spent Fuel Storage Installation (ISFSI). The wet pools range from forty years old to the most modern pool in the US Department of Energy (DOE) complex. The near-term objective is moving the fuel in the older wet storage facilities to

  7. About fuel assemblies optimization in research reactor

    International Nuclear Information System (INIS)

    Malers, Yu.P.

    1992-01-01

    Ealier was considered an algorithm for optimization of fuel assembly arrangement in a research reator. The alggorithm was based on an analytical relation between distributions of energy release and fuel concentration and on the method of succesive linearization and partially integral-number programming. In the paper are solved the problems, appeared as a result of realization of the used approach and required more correct formulation of the algorithm and introduction in it some variations

  8. Laboratory Directed Research and Development Program

    International Nuclear Information System (INIS)

    1994-02-01

    This report is compiled from annual reports submitted by principal investigators following the close of fiscal year 1993. This report describes the projects supported and summarizes their accomplishments. The program advances the Laboratory's core competencies, foundations, scientific capability, and permits exploration of exciting new opportunities. Reports are given from the following divisions: Accelerator and Fusion Research, Chemical Sciences, Earth Sciences, Energy and Environment, Engineering, Environment -- Health and Safety, Information and Computing Sciences, Life Sciences, Materials Sciences, Nuclear Science, Physics, and Structural Biology

  9. Laboratory directed research and development FY91

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, S.E.; Hedman, I.; Kirvel, R.D.; McGregor, C.K. (eds.)

    1991-01-01

    This review of research programs at Lawrence Livermore National Laboratory is composed of individual papers on various subjects. Broad topics of interest are: chemistry and materials science, computation, earth sciences, engineering, nuclear physics, and physics, and biology. Director's initiatives include the development of a transgenic mouse, accelerator mass spectrometry, high-energy physics detectors, massive parallel computing, astronomical telescopes, the Kuwaiti oil fires and a compact torus accelerator. (GHH)

  10. Laboratory directed research and development FY91

    International Nuclear Information System (INIS)

    Anderson, S.E.; Hedman, I.; Kirvel, R.D.; McGregor, C.K.

    1991-01-01

    This review of research programs at Lawrence Livermore National Laboratory is composed of individual papers on various subjects. Broad topics of interest are: chemistry and materials science, computation, earth sciences, engineering, nuclear physics, and physics, and biology. Director's initiatives include the development of a transgenic mouse, accelerator mass spectrometry, high-energy physics detectors, massive parallel computing, astronomical telescopes, the Kuwaiti oil fires and a compact torus accelerator

  11. Laboratory-directed research and development

    International Nuclear Information System (INIS)

    Gerstl, S.A.W.; Caughran, A.B.

    1992-05-01

    This report summarizes progress from the Laboratory-Directed Research and Development (LDRD) program during fiscal year 1991. In addition to a programmatic and financial overview, the report includes progress reports from 230 individual R ampersand D projects in 9 scientific categories: atomic and molecular physics; biosciences; chemistry; engineering and base technologies; geosciences; space sciences, and astrophysics; materials sciences; mathematics and computational sciences; nuclear and particle physics; and plasmas, fluids, and particle beams

  12. Managing Spent Nuclear Fuel at the Idaho National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Thomas Hill; Denzel L. Fillmore

    2005-10-01

    The Idaho National Laboratory (INL) has a large inventory of diverse types of spent nuclear fuel (SNF). This legacy derives from the history of the INL as the National Reactor Testing Station, and from its mission to recover HEU from SNF and to test and examine SNF after irradiation. The INL also has a large diversity of SNF storage facilities, some 50 years old. SNF at INL has many forms—from intact assemblies down to metallurgical mounts, and some fuel has been wet stored for over 40 years. SNF is stored bare or in metal cans under water, or dry in vaults, caissons or casks. Inspection shows varying corrosion and degradation of the SNF and its storage cans. SNF has been stored in 10 different facilities: 5 pools, one cask storage pad, one vault, two generations of caisson facilities, and one modular Independent Spent Fuel Storage Installation (ISFSI). The pools range in age from 40 years old to the most modern in the US Department of Energy (DOE) complex. The near-term objective is to move SNF from older pools to interim dry storage, allowing shutdown and decommissioning of the older facilities. This move involves drying methods that are dependent on fuel type. The long-term objective is to have INL SNF in safe dry storage and ready to be shipped to the National Repository. The unique features of the INL SNF requires special treatments and packaging to meet the proposed repository acceptance criteria and SNF will be repackaged in standardized canisters for shipment and disposal in the National Repository. Disposal will use the standardized canisters that can be co-disposed with High Level Waste glass logs to limit the total fissile material in a repository waste package. The DOE standardized canister also simplifies the repository handling of the multitude of DOE SNF sizes and shapes.

  13. United States Domestic Research Reactor Infrastructure - TRIGA Reactor Fuel Support

    International Nuclear Information System (INIS)

    Morrell, Douglas

    2008-01-01

    The purpose of the United State Domestic Research Reactor Infrastructure Program is to provide fresh nuclear reactor fuel to United States universities at no, or low, cost to the university. The title of the fuel remains with the United States government and when universities are finished with the fuel, the fuel is returned to the United States government. The program is funded by the United States Department of Energy - Nuclear Energy division, managed by Department of Energy - Idaho Field Office, and contracted to the Idaho National Laboratory's Management and Operations Contractor - Battelle Energy Alliance. Program has been at Idaho since 1977 and INL subcontracts with 26 United States domestic reactor facilities (13 TRIGA facilities, 9 plate fuel facilities, 2 AGN facilities, 1 Pulstar fuel facility, 1 Critical facility). University has not shipped fuel since 1968 and as such, we have no present procedures for shipping spent fuel. In addition: floor loading rate is unknown, many interferences must be removed to allow direct access to the reactor tank, floor space in the reactor cell is very limited, pavement ends inside our fence; some of the surface is not finished. The whole approach is narrow, curving and downhill. A truck large enough to transport the cask cannot pull into the lot and then back out (nearly impossible / refused by drivers); a large capacity (100 ton), long boom crane would have to be used due to loading dock obstructions. Access to the entrance door is on a sidewalk. The campus uses it as a road for construction equipment, deliveries and security response. Large trees are on both sides of sidewalk. Spent fuel shipments have never been done, no procedures approved or in place, no approved casks, no accident or safety analysis for spent fuel loading. Any cask assembly used in this facility will have to be removed from one crane, moved on the floor and then attached to another crane to get from the staging area to the reactor room. Reactor

  14. Status and prospects of safety research of fuel cycle facilities in France

    International Nuclear Information System (INIS)

    Auchere, H.; Mercier, J.P.

    1996-01-01

    The following themes of research are discussed: prolonged loss of cooling in concentrated fission product solution storage tanks; dewatering of a spent fuel storage pond; explosion risks in nuclear fuel cycle laboratories and plants; dissemination of radioactive materials in case of fire in fuel manufacturing plants and in spent fuel analysis laboratories; contamination transfer; phenomenology of liquid uranium hexafluoride vaporization into the atmosphere; ways and means of intervention in the event of liquid ClF 3 leakage; offsite explosion; seismic research. (K.A.)

  15. MSU-DOE Plant Research Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    1991-01-01

    This document is the compiled progress reports of research funded through the Michigan State University/Department of Energy Plant Research Laboratory. Fourteen reports are included, covering the molecular basis of plant/microbe symbiosis, cell wall biosynthesis and proteins, gene expression, stress responses, plant hormone biosynthesis, interactions between the nuclear and organelle genomes, sensory transduction and tropisms, intracellular sorting and trafficking, regulation of lipid metabolism, molecular basis of disease resistance and plant pathogenesis, developmental biology of Cyanobacteria, and hormonal involvement in environmental control of plant growth. 320 refs., 26 figs., 3 tabs. (MHB)

  16. Catalytic Fuel Conversion Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This facility enables unique catalysis research related to power and energy applications using military jet fuels and alternative fuels. It is equipped with research...

  17. Hazardous waste management in research laboratories

    International Nuclear Information System (INIS)

    Sundstrom, G.

    1989-01-01

    Hazardous waste management in research laboratories benefits from a fundamentally different approach to the hazardous waste determination from industry's. This paper introduces new, statue-based criteria for identifying hazardous wastes (such as radiological mixed wastes and waste oils) and links them to a forward-looking compliance of laboratories, the overall system integrates hazardous waste management activities with other environmental and hazard communication initiatives. It is generalizable to other waste generators, including industry. Although only the waste identification and classification aspects of the system are outlined in detail here, four other components are defined or supported, namely: routine and contingency practices; waste treatment/disposal option definition and selection; waste minimization, recycling, reuse, and substitution opportunities; and key interfaces with other systems, including pollution prevention

  18. Master plan of Mizunami underground research laboratory

    International Nuclear Information System (INIS)

    1999-04-01

    In June 1994, the Atomic Energy Commission of Japan reformulated the Long-Term Programme for Research, Development and Utilisation of Nuclear Energy (LTP). The LTP (item 7, chapter 3) sets out the guidelines which apply to promoting scientific studies of the deep geological environment, with a view to providing a sound basis for research and development programmes for geological disposal projects. The Japan Nuclear Cycle Development Institute (JNC) has been conducting scientific studies of the deep geological environment as part of its Geoscientific Research Programme. The LTP also emphasised the importance of deep underground research facilities in the following terms: Deep underground research facilities play an important role in research relating to geological disposal. They allow the characteristics and features of the geological environment, which require to be considered in performance assessment of disposal systems, to be investigated in situ and the reliability of the models used for evaluating system performance to be developed and refined. They also provide opportunities for carrying out comprehensive research that will contribute to an improved overall understanding of Japan's deep geological environment. It is recommended that more than one facility should be constructed, considering the range of characteristics and features of Japan's geology and other relevant factors. It is important to plan underground research facilities on the basis of results obtained from research and development work already carried out, particularly the results of scientific studies of the deep geological environment. Such a plan for underground research facilities should be clearly separated from the development of an actual repository. JNC's Mizunami underground research laboratory (MIU) Project will be a deep underground research facility as foreseen by the above provisions of the LTP. (author)

  19. Idaho National Laboratory - Nuclear Research Center

    International Nuclear Information System (INIS)

    Zaidi, M.K.

    2005-01-01

    Full text: The Idaho National Laboratory is committed to the providing international nuclear leadership for the 21st Century, developing and demonstrating compiling national security technologies, and delivering excellence in science and technology as one of the United States Department of Energy's (DOE) multiprogram national laboratories. INL runs three major programs - Nuclear, Security and Science. nuclear programs covers the Advanced test reactor, Six Generation technology concepts selected for R and D, Targeting tumors - Boron Neutron capture therapy. Homeland security - Homeland Security establishes the Control System Security and Test Center, Critical Infrastructure Test Range evaluates technologies on a scalable basis, INL conducts high performance computing and visualization research and science - INL facility established for Geocentrifuge Research, Idaho Laboratory, a Utah company achieved major milestone in hydrogen research and INL uses extremophile bacteria to ease bleaching's environmental cost. To provide leadership in the education and training, INL has established an Institute of Nuclear Science and Engineering (Inset). The institute will offer a four year degree based on a newly developed curriculum - two year of basic science course work and two years of participation in project planning and development. The students enrolled in this program can continue to get a masters or a doctoral degree. This summer Inset is the host for the training of the first international group selected by the World Nuclear University (WNU) - 75 fellowship holders and their 30 instructors from 40 countries. INL has been assigned to provide future global leadership in the field of nuclear science and technology. Here, at INL, we keep safety first above all things and our logo is 'Nuclear leadership synonymous with safety leadership'

  20. Transportable Heavy Duty Emissions Testing Laboratory and Research Program

    Energy Technology Data Exchange (ETDEWEB)

    David Lyons

    2008-03-31

    The objective of this program was to quantify the emissions from heavy-duty vehicles operating on alternative fuels or advanced fuel blends, often with novel engine technology or aftertreatment. In the first year of the program West Virginia University (WVU) researchers determined that a transportable chassis dynamometer emissions measurement approach was required so that fleets of trucks and buses did not need to be ferried across the nation to a fixed facility. A Transportable Heavy-Duty Vehicle Emissions Testing Laboratory (Translab) was designed, constructed and verified. This laboratory consisted of a chassis dynamometer semi-trailer and an analytic trailer housing a full scale exhaust dilution tunnel and sampling system which mimicked closely the system described in the Code of Federal Regulations for engine certification. The Translab was first used to quantify emissions from natural gas and methanol fueled transit buses, and a second Translab unit was constructed to satisfy research demand. Subsequent emissions measurement was performed on trucks and buses using ethanol, Fischer-Tropsch fuel, and biodiesel. A medium-duty chassis dynamometer was also designed and constructed to facilitate research on delivery vehicles in the 10,000 to 20,000lb range. The Translab participated in major programs to evaluate low-sulfur diesel in conjunction with passively regenerating exhaust particulate filtration technology, and substantial reductions in particulate matter were recorded. The researchers also participated in programs to evaluate emissions from advanced natural gas engines with closed loop feedback control. These natural gas engines showed substantially reduced levels of oxides of nitrogen. For all of the trucks and buses characterized, the levels of carbon monoxide, oxides of nitrogen, hydrocarbons, carbon dioxide and particulate matter were quantified, and in many cases non-regulated species such as aldehydes were also sampled. Particle size was also

  1. French experience in research reactor fuel transportation

    International Nuclear Information System (INIS)

    Raisonnier, Daniele

    1996-01-01

    Since 1963 Transnucleaire has safely performed a large number of national and international transports of radioactive material. Transnucleaire has also designed and supplied suitable packaging for all types of nuclear fuel cycle radioactive material from front-end and back-end products and for power or for research reactors. Transportation of spent fuel from power reactors are made on a regular and industrial basis, but this is not yet the case for the transport of spent fuel coming from research reactors. Each shipment is a permanent challenge and requires a reactive organization dealing with all the transportation issues. This presentation will explain the choices made by Transnucleaire and its associates to provide and optimize the corresponding services while remaining in full compliance with the applicable regulations and customer requirements. (author)

  2. Summary engineering description of underwater fuel storage facility for foreign research reactor spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Dahlke, H.J.; Johnson, D.A.; Rawlins, J.K.; Searle, D.K.; Wachs, G.W.

    1994-10-01

    This document is a summary description for an Underwater Fuel Storage Facility (UFSF) for foreign research reactor (FRR) spent nuclear fuel (SNF). A FRR SNF environmental Impact Statement (EIS) is being prepared and will include both wet and dry storage facilities as storage alternatives. For the UFSF presented in this document, a specific site is not chosen. This facility can be sited at any one of the five locations under consideration in the EIS. These locations are the Idaho National Engineering Laboratory, Savannah River Site, Hanford, Oak Ridge National Laboratory, and Nevada Test Site. Generic facility environmental impacts and emissions are provided in this report. A baseline fuel element is defined in Section 2.2, and the results of a fission product analysis are presented. Requirements for a storage facility have been researched and are summarized in Section 3. Section 4 describes three facility options: (1) the Centralized-UFSF, which would store the entire fuel element quantity in a single facility at a single location, (2) the Regionalized Large-UFSF, which would store 75% of the fuel element quantity in some region of the country, and (3) the Regionalized Small-UFSF, which would store 25% of the fuel element quantity, with the possibility of a number of these facilities in various regions throughout the country. The operational philosophy is presented in Section 5, and Section 6 contains a description of the equipment. Section 7 defines the utilities required for the facility. Cost estimates are discussed in Section 8, and detailed cost estimates are included. Impacts to worker safety, public safety, and the environment are discussed in Section 9. Accidental releases are presented in Section 10. Standard Environmental Impact Forms are included in Section 11.

  3. Hydraulic Hybrid and Conventional Parcel Delivery Vehicles' Measured Laboratory Fuel Economy on Targeted Drive Cycles

    Energy Technology Data Exchange (ETDEWEB)

    Lammert, M. P.; Burton, J.; Sindler, P.; Duran, A.

    2014-10-01

    This research project compares laboratory-measured fuel economy of a medium-duty diesel powered hydraulic hybrid vehicle drivetrain to both a conventional diesel drivetrain and a conventional gasoline drivetrain in a typical commercial parcel delivery application. Vehicles in this study included a model year 2012 Freightliner P100H hybrid compared to a 2012 conventional gasoline P100 and a 2012 conventional diesel parcel delivery van of similar specifications. Drive cycle analysis of 484 days of hybrid parcel delivery van commercial operation from multiple vehicles was used to select three standard laboratory drive cycles as well as to create a custom representative cycle. These four cycles encompass and bracket the range of real world in-use data observed in Baltimore United Parcel Service operations. The NY Composite cycle, the City Suburban Heavy Vehicle Cycle cycle, and the California Air Resources Board Heavy Heavy-Duty Diesel Truck (HHDDT) cycle as well as a custom Baltimore parcel delivery cycle were tested at the National Renewable Energy Laboratory's Renewable Fuels and Lubricants Laboratory. Fuel consumption was measured and analyzed for all three vehicles. Vehicle laboratory results are compared on the basis of fuel economy. The hydraulic hybrid parcel delivery van demonstrated 19%-52% better fuel economy than the conventional diesel parcel delivery van and 30%-56% better fuel economy than the conventional gasoline parcel delivery van on cycles other than the highway-oriented HHDDT cycle.

  4. Research Opportunities at Storm Peak Laboratory

    Science.gov (United States)

    Hallar, A. G.; McCubbin, I. B.

    2006-12-01

    The Desert Research Institute (DRI) operates a high elevation facility, Storm Peak Laboratory (SPL), located on the west summit of Mt. Werner in the Park Range near Steamboat Springs, Colorado at an elevation of 3210 m MSL (Borys and Wetzel, 1997). SPL provides an ideal location for long-term research on the interactions of atmospheric aerosol and gas- phase chemistry with cloud and natural radiation environments. The ridge-top location produces almost daily transition from free tropospheric to boundary layer air which occurs near midday in both summer and winter seasons. Long-term observations at SPL document the role of orographically induced mixing and convection on vertical pollutant transport and dispersion. During winter, SPL is above cloud base 25% of the time, providing a unique capability for studying aerosol-cloud interactions (Borys and Wetzel, 1997). A comprehensive set of continuous aerosol measurements was initiated at SPL in 2002. SPL includes an office-type laboratory room for computer and instrumentation setup with outside air ports and cable access to the roof deck, a cold room for precipitation and cloud rime ice sample handling and ice crystal microphotography, a 150 m2 roof deck area for outside sampling equipment, a full kitchen and two bunk rooms with sleeping space for nine persons. The laboratory is currently well equipped for aerosol and cloud measurements. Particles are sampled from an insulated, 15 cm diameter manifold within approximately 1 m of its horizontal entry point through an outside wall. The 4 m high vertical section outside the building is capped with an inverted can to exclude large particles.

  5. Laboratory Directed Research and Development FY 1992

    Energy Technology Data Exchange (ETDEWEB)

    Struble, G.L.; Middleton, C.; Anderson, S.E.; Baldwin, G.; Cherniak, J.C.; Corey, C.W.; Kirvel, R.D.; McElroy, L.A. [eds.

    1992-12-31

    The Laboratory Directed Research and Development (LDRD) Program at Lawrence Livermore National Laboratory (LLNL) funds projects that nurture and enrich the core competencies of the Laboratory. The scientific and technical output from the FY 1992 RD Program has been significant. Highlights include (1) Creating the first laser guide star to be coupled with adaptive optics, thus permitting ground-based telescopes to obtain the same resolution as smaller space-based instruments but with more light-gathering power. (2) Significantly improving the limit on the mass of the electron antineutrino so that neutrinos now become a useful tool in diagnosing supernovas and we disproved the existence of a 17-keV neutrino. (3) Developing a new class of organic aerogels that have robust mechanical properties and that have significantly lower thermal conductivity than inorganic aerogels. (4) Developing a new heavy-ion accelerator concept, which may enable us to design heavy-ion experimental systems and use a heavy-ion driver for inertial fusion. (5) Designing and demonstrating a high-power, diode-pumped, solid-state laser concept that will allow us to pursue a variety of research projects, including laser material processing. (6) Demonstrating that high-performance semiconductor arrays can be fabricated more efficiently, which will make this technology available to a broad range of applications such as inertial confinement fusion for civilian power. (7) Developing a new type of fiber channel switch and new fiber channel standards for use in local- and wide-area networks, which will allow scientists and engineers to transfer data at gigabit rates. (8) Developing the nation`s only numerical model for high-technology air filtration systems. Filter designs that use this model will provide safer and cleaner environments in work areas where contamination with particulate hazardous materials is possible.

  6. Laboratory Directed Research and Development FY 1992

    International Nuclear Information System (INIS)

    Struble, G.L.; Middleton, C.; Anderson, S.E.; Baldwin, G.; Cherniak, J.C.; Corey, C.W.; Kirvel, R.D.; McElroy, L.A.

    1992-01-01

    The Laboratory Directed Research and Development (LDRD) Program at Lawrence Livermore National Laboratory (LLNL) funds projects that nurture and enrich the core competencies of the Laboratory. The scientific and technical output from the FY 1992 RD Program has been significant. Highlights include (1) Creating the first laser guide star to be coupled with adaptive optics, thus permitting ground-based telescopes to obtain the same resolution as smaller space-based instruments but with more light-gathering power. (2) Significantly improving the limit on the mass of the electron antineutrino so that neutrinos now become a useful tool in diagnosing supernovas and we disproved the existence of a 17-keV neutrino. (3) Developing a new class of organic aerogels that have robust mechanical properties and that have significantly lower thermal conductivity than inorganic aerogels. (4) Developing a new heavy-ion accelerator concept, which may enable us to design heavy-ion experimental systems and use a heavy-ion driver for inertial fusion. (5) Designing and demonstrating a high-power, diode-pumped, solid-state laser concept that will allow us to pursue a variety of research projects, including laser material processing. (6) Demonstrating that high-performance semiconductor arrays can be fabricated more efficiently, which will make this technology available to a broad range of applications such as inertial confinement fusion for civilian power. (7) Developing a new type of fiber channel switch and new fiber channel standards for use in local- and wide-area networks, which will allow scientists and engineers to transfer data at gigabit rates. (8) Developing the nation's only numerical model for high-technology air filtration systems. Filter designs that use this model will provide safer and cleaner environments in work areas where contamination with particulate hazardous materials is possible

  7. New working paradigms in research laboratories.

    Science.gov (United States)

    Keighley, Wilma; Sewing, Andreas

    2009-07-01

    Work in research laboratories, especially within centralised functions in larger organisations, is changing fast. With easier access to external providers and Contract Research Organisations, and a focus on budgets and benchmarking, scientific expertise has to be complemented with operational excellence. New concepts, globally shared projects and restricted resources highlight the constraints of traditional operating models working from Monday to Friday and nine to five. Whilst many of our scientists welcome this new challenge, organisations have to enable and foster a more business-like mindset. Organisational structures, remuneration, as well as systems in finance need to be adapted to build operations that are best-in-class rather than merely minimising negative impacts of current organisational structures.

  8. Argonne National Laboratory Research Highlights 1988

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    The research and development highlights are summarized. The world's brightest source of X-rays could revolutionize materials research. Test of a prototype insertion device, a key in achieving brilliant X-ray beams, have given the first glimpse of the machine's power. Superconductivity research focuses on the new materials' structure, economics and applications. Other physical science programs advance knowledge of material structures and properties, nuclear physics, molecular structure, and the chemistry and structure of coal. New programming approaches make advanced computers more useful. Innovative approaches to fighting cancer are being developed. More experiments confirm the passive safety of Argonne's Integral Fast Reactor concept. Device simplifies nuclear-waste processing. Advanced fuel cell could provide better mileage, more power than internal combustion engine. New instruments find leaks in underground pipe, measure sodium impurities in molten liquids, detect flaws in ceramics. New antibody findings may explain ability to fight many diseases. Cadmium in cigarettes linked to bone loss in women. Programs fight deforestation in Nepal. New technology could reduce acid rain, mitigate greenhouse effect, enhance oil recovery. Innovative approaches transfer Argonne-developed technology to private industry. Each year Argonne educational programs reach some 1200 students

  9. Bringing ayahuasca to the clinical research laboratory.

    Science.gov (United States)

    Riba, Jordi; Barbanoj, Manel J

    2005-06-01

    Since the winter of 1999, the authors and their research team have been conducting clinical studies involving the administration of ayahuasca to healthy volunteers. The rationale for conducting this kind of research is twofold. First, the growing interest of many individuals for traditional indigenous practices involving the ingestion of natural psychotropic drugs such as ayahuasca demands the systematic study of their pharmacological profiles in the target species, i.e., human beings. The complex nature of ayahuasca brews combining a large number of pharmacologically active compounds requires that research be carried out to establish the safety and overall pharmacological profile of these products. Second, the authors believe that the study of psychedelics in general calls for renewed attention. Although the molecular and electrophysiological level effects of these drugs are relatively well characterized, current knowledge of the mechanisms by which these compounds modify the higher order cognitive processes in the way they do is still incomplete, to say the least. The present article describes the development of the research effort carried out at the Autonomous University of Barcelona, commenting on several methodological aspects and reviewing the basic clinical findings. It also describes the research currently underway in our laboratory, and briefly comments on two new studies we plan to undertake in order to further our knowledge of the pharmacology of ayahuasca.

  10. Radioactive waste management research at CEGB Berkeley nuclear laboratories

    International Nuclear Information System (INIS)

    Bradbury, D.

    1988-01-01

    The CEGB is the major electric utility in the United Kingdom. This paper discusses how, at the research laboratories at Berkeley (BNL), several programs of work are currently taking place in the radioactive waste management area. The theme running through all this work is the safe isolation of radionuclides from the environment. Normally this means disposal of waste in solid form, but it may also be desirable to segregate and release nonradioactive material from the waste to reduce volume or improve the solid waste characteristics (e.g., the release of liquid or gaseous effluents after treatment to convert the radioactivity to solid form). The fuel cycle and radioactive waste section at BNL has a research program into these aspects for wastes arising from the operation or decommissioning of power stations. The work is done both in-house and on contract, with primarily the UKAEA

  11. Aespoe hard rock laboratory. Current research projects 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

    In 1986 SKB decided to construct the Aespoe Hard Rock Laboratory (HRL) in order to provide an opportunity for research, development and demonstration in a realistic and undisturbed underground rock environment down to the depth planned for the future deep repository. The focus of current and future work is on development and testing of site characterization methods, verification of models describing the function of the natural and engineered barriers and development, testing, and demonstration of repository technology. The program has been organised so that all important steps in the development of a repository are covered, in other words the Aespoe HRL constitutes a `dress rehearsal` for the Swedish deep geological repository for spent fuel and other long-lived waste. Geoscientific investigations on Aespoe and nearby islands began in 1986. Aespoe was selected as the site for the laboratory in 1988. Construction of the facility, which reaches a depth of 460 m below the surface, began in 1990 and was completed in 1995. A major milestone had been reached in 1996 with the completion of the pre-investigation and construction phases of the Aespoe HRL. The comprehensive research conducted has permitted valuable development and verification of site characterization methods applied from the ground surface, boreholes, and underground excavations. The results of this research are summarised in the book `Aespoe Hard Rock Laboratory - 10 years of Research` published by SKB in 1996. The Operating Phase of the Aespoe HRL began in 1995 and is expected to continue for 15-20 years, that is until the first stage of the development of the Swedish deep geological repository for spent nuclear fuel is expected to be completed. A number of research projects were initiated at the start of the Operating Phase. Most of these projects have made substantial progress since then and important results have been obtained. The purpose of this brochure is to provide a brief presentation of the

  12. Aespoe hard rock laboratory. Current research projects 1998

    International Nuclear Information System (INIS)

    1998-01-01

    In 1986 SKB decided to construct the Aespoe Hard Rock Laboratory (HRL) in order to provide an opportunity for research, development and demonstration in a realistic and undisturbed underground rock environment down to the depth planned for the future deep repository. The focus of current and future work is on development and testing of site characterization methods, verification of models describing the function of the natural and engineered barriers and development, testing, and demonstration of repository technology. The program has been organised so that all important steps in the development of a repository are covered, in other words the Aespoe HRL constitutes a 'dress rehearsal' for the Swedish deep geological repository for spent fuel and other long-lived waste. Geoscientific investigations on Aespoe and nearby islands began in 1986. Aespoe was selected as the site for the laboratory in 1988. Construction of the facility, which reaches a depth of 460 m below the surface, began in 1990 and was completed in 1995. A major milestone had been reached in 1996 with the completion of the pre-investigation and construction phases of the Aespoe HRL. The comprehensive research conducted has permitted valuable development and verification of site characterization methods applied from the ground surface, boreholes, and underground excavations. The results of this research are summarised in the book 'Aespoe Hard Rock Laboratory - 10 years of Research' published by SKB in 1996. The Operating Phase of the Aespoe HRL began in 1995 and is expected to continue for 15-20 years, that is until the first stage of the development of the Swedish deep geological repository for spent nuclear fuel is expected to be completed. A number of research projects were initiated at the start of the Operating Phase. Most of these projects have made substantial progress since then and important results have been obtained. The purpose of this brochure is to provide a brief presentation of the

  13. United States Department of Energy commercial reactor spent fuel programs being conducted at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Piscitella, R.R.; Rasmussen, T.L.; Uhl, D.L.

    1987-01-01

    The Idaho National Engineering Laboratory participation in OCRWM programs includes the Spent Fuel Storage Cask Testing Program, Dry Rod Consolidation Technology Program, Prototypical Consolidation Demonstration Program, the Nuclear Fuel Services Project, and the Cask Systems Acquisition Program. The DOE has entered into a cooperative agreement with Virginia Power and the Electric Power Research Institute to demonstrate storage of commercial spent fuel in steel storage casks. The Program conducted heat transfer and shielding tests with three storage casks with intact spent fuel assemblies and two casks with consolidated spent fuel rods, one of which was previously tested with intact fuel, and provides test information in support of Virginia Power's at-reactor dry storage licensing effort. 3 figs., 1 tab

  14. US spent fuel research and experience

    Energy Technology Data Exchange (ETDEWEB)

    Machiels, A [EPRI and USDOE (United States)

    2012-07-01

    The structural performance of high-burnup spent fuel cladding during dry storage and transportation has been the subject of research and evaluation at EPRI for several years. The major issues addressed in this research program have included the following: Characterization and development of predictive models for damage mechanisms perceived to be potentially active during dry storage; Modeling and analysis of deformation processes during long-term dry storage; Development of cladding failure models and failure criteria, considering cladding material and physical conditions during dry storage and transportation; Failure analysis, considering end-of-dry-storage conditions, of spent fuel systems subjected to normal and accident conditions of transport, prescribed in Part 71 of Title 10 of the Code of Federal Regulations (10CFR71) While issues related to dry storage have largely been resolved, transportation issues have not, at least for spent fuel with discharge burnups greater than 45 GWd/MTU. A research program was launched in late 2002 following two NRC-industry meetings held on September 6, 2002 and October 23, 2002. The aim of the research program was to assess the performance of high-burnup spent fuel cladding under normal and accident conditions of transportation, as prescribed by 10CFR71, considering the physical characteristics and mechanical properties of cladding at the end of dry storage. The objective is to present a synthesis of the information that collectively forms a part of a technical basis intended to facilitate resolution of regulatory issues associated with the transportation of spent nuclear fuel characterized by discharge burnups greater than 45 GWd/MTU.

  15. Research reactors fuel cycle problems and dilemma

    International Nuclear Information System (INIS)

    Romano, R.

    2004-01-01

    During last 10 years, some problems appeared in different steps of research reactors fuel cycle. Actually the majority of these reactors have been built in the 60s and these reactors were operated during all this long period in a cycle with steps which were dedicated to this activity. Progressively and for reasons often economical, certain steps of the cycle became more and more difficult to manage due to closing of some specialised workshops in the activities of scraps recycling, irradiated fuel reprocessing, even fuel fabrication. Other steps of the cycle meet or will meet difficulties, in particular supplying of fissile raw material LEU or HEU because this material was mostly produced in enrichment units existing mainly for military reason. Rarefaction of fissile material lead to use more and more enriched uraniums said 'of technical quality', that is to say which come from mixing of varied qualities of enriched material, containing products resulting from reprocessing. Actually, problems of end of fuel cycle are increased, either consisting of intermediary storage on the site of reactor or on specialised sites, or consisting of reprocessing. This brief summary shows most difficulties which are met today by a major part of industrials of the fuel cycle in the exercise of their activities

  16. Pacific Northwest Laboratory (PNL) spent fuel transportation and handling facility models

    International Nuclear Information System (INIS)

    Andrews, W.B.; Bower, J.C.; Burnett, R.A.; Engel, R.L.; Rolland, C.W.

    1979-09-01

    A spent fuel logistics study was conducted in support of the US DOE program to develop facilities for preparing spent unreprocessed fuel from commercial LWRs for geological storage. Two computerized logistics models were developed. The first one was the site evaluation model. Two studies of spent fuel handling facility and spent fuel disposal facility siting were completed; the first postulates a single spent fuel handling facility located at any of six DOE laboratory sites, while the second study examined siting strategies with the spent fuel repository relative to the spent fuel handling facility. A second model to conduct storage/handling facility simulations was developed

  17. Pacific Northwest Laboratory (PNL) spent fuel transportation and handling facility models

    Energy Technology Data Exchange (ETDEWEB)

    Andrews, W.B.; Bower, J.C.; Burnett, R.A.; Engel, R.L.; Rolland, C.W.

    1979-09-01

    A spent fuel logistics study was conducted in support of the US DOE program to develop facilities for preparing spent unreprocessed fuel from commercial LWRs for geological storage. Two computerized logistics models were developed. The first one was the site evaluation model. Two studies of spent fuel handling facility and spent fuel disposal facility siting were completed; the first postulates a single spent fuel handling facility located at any of six DOE laboratory sites, while the second study examined siting strategies with the spent fuel repository relative to the spent fuel handling facility. A second model to conduct storage/handling facility simulations was developed. (DLC)

  18. Fuel Combustion and Engine Performance | Transportation Research | NREL

    Science.gov (United States)

    Fuel Combustion and Engine Performance Fuel Combustion and Engine Performance Photo of a gasoline emissions in advanced engine technologies. Photo by Dennis Schroeder, NREL NREL's combustion research and combustion and engine research activities include: Developing experimental and simulation research platforms

  19. National Storage Laboratory: a collaborative research project

    Science.gov (United States)

    Coyne, Robert A.; Hulen, Harry; Watson, Richard W.

    1993-01-01

    The grand challenges of science and industry that are driving computing and communications have created corresponding challenges in information storage and retrieval. An industry-led collaborative project has been organized to investigate technology for storage systems that will be the future repositories of national information assets. Industry participants are IBM Federal Systems Company, Ampex Recording Systems Corporation, General Atomics DISCOS Division, IBM ADSTAR, Maximum Strategy Corporation, Network Systems Corporation, and Zitel Corporation. Industry members of the collaborative project are funding their own participation. Lawrence Livermore National Laboratory through its National Energy Research Supercomputer Center (NERSC) will participate in the project as the operational site and provider of applications. The expected result is the creation of a National Storage Laboratory to serve as a prototype and demonstration facility. It is expected that this prototype will represent a significant advance in the technology for distributed storage systems capable of handling gigabyte-class files at gigabit-per-second data rates. Specifically, the collaboration expects to make significant advances in hardware, software, and systems technology in four areas of need, (1) network-attached high performance storage; (2) multiple, dynamic, distributed storage hierarchies; (3) layered access to storage system services; and (4) storage system management.

  20. Idaho national laboratory - a nuclear research center

    International Nuclear Information System (INIS)

    Zaidi Mohammed, K.

    2006-01-01

    Full text: The Idaho National Laboratory (INL) is committed to providing international nuclear leadership for the 21st Century, developing and demonstrating compelling national security technologies, and delivering excellence in science and technology as one of the United States Department of Energy's (DOE) multi program national laboratories. INL runs three major programs - Nuclear, Security and Science. Nuclear programs covers the Advanced test reactor, Six Generation IV technology concepts selected for Rand D, targeting tumors - Boron Neutron Capture therapy. Homeland Security establishes the Control System Security and Test Center, Critical Infrastructure Test Range evaluates technologies on a scalable basis, INL conducts high performance computing and visualization research and science. To provide leadership in the education and training, INL has established an Institute of Nuclear Science and Engineering (INSE) under the Center for Advanced Energy Studies (CAES) and the Idaho State University (ISU). INSE will offer a four year degree based on a newly developed curriculum - two year of basic science course work and two years of participation in project planning and development. The students enrolled in this program can continue to get a masters or a doctoral degree. This summer INSE is the host for the training of the first international group selected by the World Nuclear University (WNU) - 75 fellowship holders and their 30 instructors from 40 countries. INL has been assigned to provide future global leadership in the field of nuclear science and technology. Here, at INL, we keep safety first above all things and our logo is 'Nuclear leadership synonymous with safety leadership'. (author)

  1. Status of Zircaloy deformation and oxidation research at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Chapman, R.H.; Cathcart, J.V.; Hobson, D.O.

    1976-01-01

    The U.S. Nuclear Regulatory Commission sponsors a broad range of research on the response of nuclear fuel assemblies to normal, off-normal, and accident conditions in light-water reactors. The paper reviews the current status of three Zircaloy cladding research programs in progress at the Oak Ridge National Laboratory and presents some preliminary results from each

  2. A wonderful laboratory and a great researcher

    Science.gov (United States)

    Sheikh, N. M.

    2004-05-01

    It was great to be associated with Prof. Dr. Karl Rawer. He devoted his life to make use of the wonderful laboratory of Nature, the Ionosphere. Through acquisition of the experimental data from AEROS satellites and embedding it with data from ground stations, it was possible to achieve a better empirical model, the International Reference Ionosphere. Prof. Dr. Karl Rawer has been as dynamic as the Ionosphere. His vision about the ionospheric data is exceptional and has helped the scientific and engineering community to make use of his vision in advancing the dimensions of empirical modelling. As a human being, Prof. Dr. Karl Rawer has all the traits of an angel from Heaven. In short he developed a large team of researchers forming a blooming tree from the parent node. Ionosphere still plays an important role in over the horizon HF Radar and GPs satellite data reduction.

  3. Research reactor fuel development at AECL

    International Nuclear Information System (INIS)

    Sears, D.F.; Wang, N.

    2000-09-01

    This paper reviews recent U 3 Si 2 and U-Mo dispersion fuel development activities at AECL. The scope of work includes fabrication development, irradiation testing, post-irradiation examination and performance qualification. U-Mo alloys with a variety of compositions, ranging from 6 to 10 wt % Mo, have been fabricated with high purity and homogeneity in the product. The alloys and powders were characterized using optical and scanning electron microscopy, chemical analysis, and X-ray diffraction and neutron diffraction analysis. U-Mo powder samples have been supplied to the Argonne National Laboratory for irradiation testing in the ATR reactor. Low-enriched uranium fuel elements containing U-7 wt % Mo and U-10 wt % Mo with loadings up to 4.5 gU/cm 3 have been fabricated at CRL for irradiation testing in the NRU reactor. The U-Mo fuel elements will be tested in NRU at linear powers up to 145 kW/m, and to 85 atom % 235 U burnup. (author)

  4. Research reactor fuel development at AECL

    International Nuclear Information System (INIS)

    Sears, D.F.; Wang, N.

    2000-01-01

    This paper reviews recent U 3 Si 2 and U-Mo dispersion fuel development activities at AECL. The scope of work includes fabrication development, irradiation testing, postirradiation examination and performance qualification. U-Mo alloys with a variety of compositions, ranging from 6 to 10 wt % Mo, have been fabricated with high purity and homogeneity in the product. The alloys and powders were characterized using optical and scanning electron microscopy, chemical analysis, and X-ray diffraction and neutron diffraction analysis. U-Mo powder samples have been supplied to the Argonne National Laboratory for irradiation testing in the ATR reactor. Low-enriched uranium fuel elements containing U-7 wt % Mo and U-10 wt % Mo with loadings up to 4.5 gU/cm 3 have been fabricated at CRL for irradiation testing in the NRU reactor. The U-Mo fuel elements will be tested in NRU at linear powers up to 145 kW/m, and to 85 atom % 235 U burnup. (author)

  5. Understanding Our Energy Footprint: Undergraduate Chemistry Laboratory Investigation of Environmental Impacts of Solid Fossil Fuel Wastes

    Science.gov (United States)

    Berger, Michael; Goldfarb, Jillian L.

    2017-01-01

    Engaging undergraduates in the environmental consequences of fossil fuel usage primes them to consider their own anthropogenic impact, and the benefits and trade-offs of converting to renewable fuel strategies. This laboratory activity explores the potential contaminants (both inorganic and organic) present in the raw fuel and solid waste…

  6. Fuel Management at the Dalat Nuclear Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Pham, V.L.; Nguyen, N.D.; Luong, B.V.; Le, V.V.; Huynh, T.N.; Nguyen, K.C. [Nuclear Research Institute, 01 Nguyen Tu Luc Street, Dalat City (Viet Nam)

    2011-07-01

    The Dalat Nuclear Research Reactor (DNRR) is a pool type research reactor which was reconstructed in 1982 from the old 250 kW TRIGA-MARK II reactor. The spent fuel storage was newly designed and installed in the place of the old thermalizing column for biological irradiation. The core was loaded by Russian WWR-M2 fuel assemblies (FAs) with 36% enrichment. The reconstructed reactor reached its initial criticality in November 1983 and attained it nominal power of 500 kW in February 1984. The first fuel reloading was executed in April 1994 after more than 10 years of operation with 89 highly enriched uranium (HEU) FAs. The third fuel reloading by shuffling of HEU FAs was executed in June 2004. After the shuffling the working configuration of reactor core kept unchanged of 104 HEU FAs. The fourth fuel reloading was executed in November 2006. The 2 new HEU FAs were loaded in the core periphery, at previous locations of wet irradiation channel and dry irradiation channel. After reloading the working configuration of reactor core consisted of 106 HEU FAs. Contracts for reactor core conversion between USA, Russia, Vietnam and the International Atomic Energy Agency for Nuclear fuel manufacture and supply for DNRR and Return of Russian-origin non-irradiated highly enriched uranium fuel to the Russian Federation have been realized in 2007. According to the results of design and safety analyses performed by the joint study between RERTR Program at Argonne National Laboratory and Vietnam Atomic Energy Institute the mixed core configurations of irradiated HEU and new low enriched uranium (LEU) FAs has been created on 12 September, 2007 and on 20 July, 2009. After reloading in 2009, the 14 HEU FAs with highest burnup were removed from the core and put in the interim storage in reactor pool. The works on full core conversion for the DNRR are being realized in cooperation with the organizations, DOE and IAEA. Contract for Nuclear fuel manufacture and supply of 66 LEU FAs for DNRR

  7. A university hot laboratory for teaching and research

    International Nuclear Information System (INIS)

    Heinonen, O.; Miettinen, J.K.

    1976-01-01

    In small countries which have limited material and capital resources there is more need for studying and teaching reactor chemistry in universities than there is in countries with special nuclear research and training centres. A new 150-m 2 laboratory of reactor chemistry was added to the premises of the Department of Radiochemistry, University of Helsinki, in October 1975. It contains a hot area with low-pressure air-conditioning, a sanitary room, a low-activity area, and an office area. The main instrument is a mass-spectrometer MI-1309 equipped with an ion counter which is particularly useful for plutonium analysis. The laboratory can handle samples up-to 10Ci gamma-acitivity - which equals one pellet of a fuel rod - in a sealed lead cell which has an interchangeable box for alpha-active work. Pretreated samples are submitted to chemical separations in glove-boxes. Samples for alpha and mass spectroscopy are also prepared in glove-boxes. Also the laboratory is provided with fume hoods suitable for building lead shields. Radiation protection and special features typical to the university environment are discussed. Methods for verfication of contamination and protection against internal and external contamination are applied. These include air monitoring, analysis of excreta, and whole-body counting. (author)

  8. Research reactor spent fuel management in Argentina

    International Nuclear Information System (INIS)

    Audero, M.A.; Bevilacqua, A.M.; Mehlich, A.M.; Novara, O.

    2002-01-01

    The research reactor spent fuel (RRSF) management strategy will be presented as well as the interim storage experience. Currently, low-enriched uranium RRSF is in wet interim storage either at reactor site or away from reactor site in a centralized storage facility. High-enriched uranium RRSF from the centralized storage facility has been sent to the USA in the framework of the Foreign Research Reactor Spent Nuclear Fuel Acceptance Program. The strategy for the management of the RRSF could implement the encapsulation for interim dry storage. As an alternative to encapsulation for dry storage some conditioning processes are being studied which include decladding, isotopic dilution, oxidation and immobilization. The immobilized material will be suitable for final disposal. (author)

  9. Monitoring and information management system at the Underground Research Laboratory

    International Nuclear Information System (INIS)

    Strobel, G.S.; Chernis, P.J.; Bushman, A.T.; Spinney, M.H.; Backer, R.J.

    1996-01-01

    Atomic Energy of Canada Limited (AECL) has developed a customer oriented monitoring and information management system at the Underground Research Laboratory (URL) near Lac du Bonnet, Manitoba. The system is used to monitor instruments and manage, process, and distribute data. It consists of signal conditioners and remote loggers, central schedule and control systems, computer aided design and drafting work centres, and the communications linking them. The monitoring and communications elements are designed to meet the harsh demands of underground conditions while providing accurate monitoring of sensitive instruments to rigorous quality assured specifications. These instruments are used for testing of the concept for the deep geological disposal of nuclear fuel waste as part of the Canadian Nuclear Fuel Waste Management Program. Many of the tests are done in situ and at full-scale. The monitoring and information management system services engineering, research, and support staff working to design, develop, and demonstrate and present the concept. Experience gained during development of the monitoring and information management system at the URL, can be directly applied at the final disposal site. (author)

  10. Monitoring and information management system at the Underground Research Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Strobel, G.S.; Chernis, P.J.; Bushman, A.T.; Spinney, M.H.; Backer, R.J. [Atomic Energy of Canada Limited, Pinawa, Manitoba (Canada)

    1996-07-01

    Atomic Energy of Canada Limited (AECL) has developed a customer oriented monitoring and information management system at the Underground Research Laboratory (URL) near Lac du Bonnet, Manitoba. The system is used to monitor instruments and manage, process, and distribute data. It consists of signal conditioners and remote loggers, central schedule and control systems, computer aided design and drafting work centres, and the communications linking them. The monitoring and communications elements are designed to meet the harsh demands of underground conditions while providing accurate monitoring of sensitive instruments to rigorous quality assured specifications. These instruments are used for testing of the concept for the deep geological disposal of nuclear fuel waste as part of the Canadian Nuclear Fuel Waste Management Program. Many of the tests are done in situ and at full-scale. The monitoring and information management system services engineering, research, and support staff working to design, develop, and demonstrate and present the concept. Experience gained during development of the monitoring and information management system at the URL, can be directly applied at the final disposal site. (author)

  11. Decommissioning program and future plan for research hot laboratory (2)

    International Nuclear Information System (INIS)

    Koya, Toshio; Nozawa, Yukio; Hanada, Yasushi; Ono, Katsuto; Kanazawa, Hiroyuki; Nihei, Yasuo; Owada, Isao

    2010-01-01

    The Research Hot Laboratory (RHL) in Japan Atomic Energy Agency (JAEA) was constructed in 1961, as the first one in JAPAN, to perform the examinations of irradiated fuels and materials. RHL consists of 10 heavy concrete cells and 38 lead cells, which had been contributed to research and development program in or out of JAEA for the investigation of irradiation behavior for fuels and nuclear materials. However, RHL is the one of target as the rationalization program for decrepit facilities in former Tokai institute. Therefore the decommissioning works of RHL have been started on April 2003. The decommissioning work will be progressing, dismantling the lead cells and decontamination of concrete caves then release in the regulation of controlled area. The 18 lead cells (including semi-hot cell and junior-cell) had been dismantled. Removal of the applause from the cells, survey of the contamination revel in the lead cells and prediction of radio active waste have been finished as the preparing work for dismantling of the remained 20 lead cells. The future plan of decommissioning work has been prepared to incarnate the basic vision and dismantling procedure. (author)

  12. Ambient Laboratory Coater for Advanced Gas Reactor Fuel Development

    International Nuclear Information System (INIS)

    Bruns, Duane D.; Counce, Robert M.; Lima Rojas, Irma D.

    2010-01-01

    This research is targeted at developing improved experimentally-based scaling relationships for the hydrodynamics of shallow, gas-spouted beds of dense particles. The work is motivated by the need to more effctively scale up shallow spouted beds used in processes such as in the coating of nuclear fuel particles where precise control of solids and gas circulation is critically important. Experimental results reported here are for a 50 mm diameter spouted bed containing two different types of bed solids (alumina and zirconia) at different static bed depths and fluidized by air and helium. Measurements of multiple local average pressures, inlet gas pressure fluctuations, and spout height were used to characterize the bed hydrodynamics for each operating condition. Follow-on studies are planned that include additional variations in bed size, particle properties, and fluidizing gas. The ultimate objective is to identify the most important non-dimensional hydrodynamic scaling groups and possible spouted-bed design correlations based on these groups.

  13. Convective parameters in fuel elements for research nuclear reactors

    International Nuclear Information System (INIS)

    Lopez Martinez, C.D.

    1992-01-01

    The study of a prototype for the simulation of fuel elements for research nuclear reactors by natural convection in water is presented in this paper. This project is carry out in the thermofluids laboratory of National Institute of Nuclear Research. The fuel prototype has already been test for natural convection in air, and the first results in water are presented in this work. In chapter I, a general description of Triga Mark III is made, paying special atention to fuel-moderator components. In chapter II and III an approach to convection subject in its global aspects is made, since the intention is to give a general idea of the events occuring around fuel elements in a nuclear reactor. In chapter II, where an emphasis on forced convection is made, some basic concepts for forced convection as well as for natural convection are included. The subject of flow through cylinders is annotated only as a comparative reference with natural convection in vertical cylinders, noting the difference between used correlations and the involved variables. In chapter III a compilation of correlation found in the bibliography about natural convection in vertical cylinders is presented, since its geometry is the more suitable in the analysis of a fuel rod. Finally, in chapter IV performed experiments in the test bench are detailed, and the results are presented in form of tables and graphs, showing the used equations for the calculations and the restrictions used in each case. For the analysis of the prototypes used in the test bench, a constant and uniform flow of heat in the whole length of the fuel rod is considered. At the end of this chapter, the work conclusions and a brief explanation of the results are presented (Author)

  14. Tritium Research Laboratory safety analysis report

    Energy Technology Data Exchange (ETDEWEB)

    Wright, D.A.

    1979-03-01

    Design and operational philosophy has been evolved to keep radiation exposures to personnel and radiation releases to the environment as low as reasonably achievable. Each experiment will be doubly contained in a glove box and will be limited to 10 grams of tritium gas. Specially designed solid-hydride storage beds may be used to store temporarily up to 25 grams of tritium in the form of tritides. To evaluate possible risks to the public or the environment, a review of the Sandia Laboratories Livermore (SLL) site was carried out. Considered were location, population, land use, meteorology, hydrology, geology, and seismology. The risks and the extent of damage to the TRL and vital systems were evaluated for flooding, lightning, severe winds, earthquakes, explosions, and fires. All of the natural phenomena and human error accidents were considered credible, although the extent of potential damage varied. However, rather than address the myriad of specific individual consequences of each accident scenario, a worst-case tritium release caused indirectly by an unspecified natural phenomenon or human error was evaluated. The maximum credible radiological accident is postulated to result from the release of the maximum quantity of gas from one experiment. Thus 10 grams of tritium gas was used in the analysis to conservatively estimate the maximum whole-body dose of 1 rem at the site boundary and a maximum population dose of 600 man-rem. Accidental release of this amount of tritium implies simultaneous failure of two doubly contained systems, an occurrence considered not credible. Nuclear criticality is impossible in this facility. Based upon the analyses performed for this report, we conclude that the Tritium Research Laboratory can be operated without undue risk to employees, the general public, or the environment. (ERB)

  15. Tritium Research Laboratory safety analysis report

    International Nuclear Information System (INIS)

    Wright, D.A.

    1979-03-01

    Design and operational philosophy has been evolved to keep radiation exposures to personnel and radiation releases to the environment as low as reasonably achievable. Each experiment will be doubly contained in a glove box and will be limited to 10 grams of tritium gas. Specially designed solid-hydride storage beds may be used to store temporarily up to 25 grams of tritium in the form of tritides. To evaluate possible risks to the public or the environment, a review of the Sandia Laboratories Livermore (SLL) site was carried out. Considered were location, population, land use, meteorology, hydrology, geology, and seismology. The risks and the extent of damage to the TRL and vital systems were evaluated for flooding, lightning, severe winds, earthquakes, explosions, and fires. All of the natural phenomena and human error accidents were considered credible, although the extent of potential damage varied. However, rather than address the myriad of specific individual consequences of each accident scenario, a worst-case tritium release caused indirectly by an unspecified natural phenomenon or human error was evaluated. The maximum credible radiological accident is postulated to result from the release of the maximum quantity of gas from one experiment. Thus 10 grams of tritium gas was used in the analysis to conservatively estimate the maximum whole-body dose of 1 rem at the site boundary and a maximum population dose of 600 man-rem. Accidental release of this amount of tritium implies simultaneous failure of two doubly contained systems, an occurrence considered not credible. Nuclear criticality is impossible in this facility. Based upon the analyses performed for this report, we conclude that the Tritium Research Laboratory can be operated without undue risk to employees, the general public, or the environment

  16. BWR Spent Nuclear Fuel Integrity Research and Development Survey for UKABWR Spent Fuel Interim Storage

    Energy Technology Data Exchange (ETDEWEB)

    Bevard, Bruce Balkcom [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Mertyurek, Ugur [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Belles, Randy [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Scaglione, John M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-10-01

    The objective of this report is to identify issues and support documentation and identify and detail existing research on spent fuel dry storage; provide information to support potential R&D for the UKABWR (United Kingdom Advanced Boiling Water Reactor) Spent Fuel Interim Storage (SFIS) Pre-Construction Safety Report; and support development of answers to questions developed by the regulator. Where there are gaps or insufficient data, Oak Ridge National Laboratory (ORNL) has summarized the research planned to provide the necessary data along with the schedule for the research, if known. Spent nuclear fuel (SNF) from nuclear power plants has historically been stored on site (wet) in spent fuel pools pending ultimate disposition. Nuclear power users (countries, utilities, vendors) are developing a suite of options and set of supporting analyses that will enable future informed choices about how best to manage these materials. As part of that effort, they are beginning to lay the groundwork for implementing longer-term interim storage of the SNF and the Greater Than Class C (CTCC) waste (dry). Deploying dry storage will require a number of technical issues to be addressed. For the past 4-5 years, ORNL has been supporting the U.S. Department of Energy (DOE) in identifying these key technical issues, managing the collection of data to be used in issue resolution, and identifying gaps in the needed data. During this effort, ORNL subject matter experts (SMEs) have become expert in understanding what information is publicly available and what gaps in data remain. To ensure the safety of the spent fuel under normal and frequent conditions of wet and subsequent dry storage, intact fuel must be shown to: 1.Maintain fuel cladding integrity; 2.Maintain its geometry for cooling, shielding, and subcriticality; 3.Maintain retrievability, and damaged fuel with pinhole or hairline cracks must be shown not to degrade further. Where PWR (pressurized water reactor) information is

  17. Research Laboratory of Mixed Radiation Dosimetry

    International Nuclear Information System (INIS)

    2002-01-01

    Full text: Two main topics of the research work in the Laboratory of Mixed Radiation Dosimetry in 2001 were: development of recombination methods for dosimetry of mixed radiation fields and maintenance and development of unique in Poland reference neutron fields. Additionally research project on internal dosimetry were carried out in collaboration with Division of Radiation Protection Service. RECOMBINATION METHODS Recombination methods make use of the fact that the initial recombination of ions in the gas cavity of the ionization chamber depends on local ionization density. The later can be related to linear energy transfer (LET) and provides information on radiation quality of the investigated radiation fields. Another key feature of the initial recombination is that it does not depend of dose rate. Conditions of initial (local) recombination can be achieved in specially designed high pressure tissue-equivalent ionization chambers, called the recombination chambers. They are usually parallel-plate ionization chambers filled with a tissue-equivalent gas mixture under a pressure of order 1 MPa. The spacing between electrodes is of order of millimeters. At larger spacing, the volume recombination limits the maximum dose rate at which the chamber can be properly operated. The output of the chamber is the ionization current (or collected charge) as a function of collecting voltage. All the recombination methods require the measurement of the ionization current (or charge) at least at two values of the collecting voltage applied to the chamber. The highest voltage should provide the conditions close to saturation (but below discharge or multiplication). The ionization current measured at maximum applied voltage is proportional to the absorbed dose, D, (some small corrections for lack of saturation can be introduced when needed). Measurements at other voltages are needed for the determination of radiation quality. The total dose equivalent in a mixed radiation field is

  18. Research programs at the Department of Energy National Laboratories. Volume 2: Laboratory matrix

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-01

    For nearly fifty years, the US national laboratories, under the direction of the Department of Energy, have maintained a tradition of outstanding scientific research and innovative technological development. With the end of the Cold War, their roles have undergone profound changes. Although many of their original priorities remain--stewardship of the nation`s nuclear stockpile, for example--pressing budget constraints and new federal mandates have altered their focus. Promotion of energy efficiency, environmental restoration, human health, and technology partnerships with the goal of enhancing US economic and technological competitiveness are key new priorities. The multiprogram national laboratories offer unparalleled expertise in meeting the challenge of changing priorities. This volume aims to demonstrate each laboratory`s uniqueness in applying this expertise. It describes the laboratories` activities in eleven broad areas of research that most or all share in common. Each section of this volume is devoted to a single laboratory. Those included are: Argonne National Laboratory; Brookhaven National Laboratory; Idaho National Engineering Laboratory; Lawrence Berkeley Laboratory; Lawrence Livermore National Laboratory; Los Alamos National Laboratory; National Renewable Energy Laboratory; Oak Ridge National Laboratory; Pacific Northwest Laboratory; and Sandia National Laboratories. The information in this volume was provided by the multiprogram national laboratories and compiled at Lawrence Berkeley Laboratory.

  19. Shifting to non-explosive fuels for research reactors

    International Nuclear Information System (INIS)

    Gilinsky, Victor

    1984-01-01

    The RERTR program is not just an American program, it is an international program and it can succeed only with wide support and participation. Excellent work underway at research laboratories in several countries is making a vital contribution. The cooperative spirit shown by all participants is particularly gratifying. Some practical difficulties may be encountered with the safety regulatory agencies in different countries when modifying the reactors. The US NRC intends to demonstrate that conversion to low enriched fuel is not a difficult process by taking steps to enable domestic reactors operating in the United States to convert to low enriched fuels. A proposed regulation is being prepared limiting the use of highly enriched uranium in domestic reactors. In this connection, The US NRC will be prepared tp cooperate with reactor operators from other countries in the safety area as it relates to the conversion process

  20. Research and Progress on Virtual Cloud Laboratory

    OpenAIRE

    Zhang Jian Wei; Shang Zhi Hui; Yuan Chen; Ma Lin Lin; Cai Zeng Yu; Hu Chun Hui

    2016-01-01

    In recent years, cloud computing technology has experienced continuous development and improvement, and has gradually expanded to the education sector. First, this paper will introduce the background knowledge of the current virtual cloud laboratory; by comparing the advantages and disadvantages between traditional laboratory and virtual cloud laboratory, and comparing the application, advantages and disadvantages, and development trend of OpenStack technology and VMWare technology in safety,...

  1. Network Science Research Laboratory (NSRL) Discrete Event Toolkit

    Science.gov (United States)

    2016-01-01

    ARL-TR-7579 ● JAN 2016 US Army Research Laboratory Network Science Research Laboratory (NSRL) Discrete Event Toolkit by...Laboratory (NSRL) Discrete Event Toolkit by Theron Trout and Andrew J Toth Computational and Information Sciences Directorate, ARL...Research Laboratory (NSRL) Discrete Event Toolkit 5a. CONTRACT NUMBER 5b. GRANT NUMBER 5c. PROGRAM ELEMENT NUMBER 6. AUTHOR(S) Theron Trout

  2. Integrated safeguards testing laboratories in support of the advanced fuel cycle initiative

    International Nuclear Information System (INIS)

    Santi, Peter A.; Demuth, Scott F.; Klasky, Kristen L.; Lee, Haeok; Miller, Michael C.; Sprinkle, James K.; Tobin, Stephen J.; Williams, Bradley

    2009-01-01

    A key enabler for advanced fuel cycle safeguards research and technology development for programs such as the Advanced Fuel Cycle Initiative (AFCI) is access to facilities and nuclear materials. This access is necessary in many cases in order to ensure that advanced safeguards techniques and technologies meet the measurement needs for which they were designed. One such crucial facility is a hot cell based laboratory which would allow developers from universities, national laboratories, and commercial companies to perform iterative research and development of advanced safeguards instrumentation under realistic operating conditions but not be subject to production schedule limitations. The need for such a facility arises from the requirement to accurately measure minor actinide and/or fission product bearing nuclear materials that cannot be adequately shielded in glove boxes. With the contraction of the DOE nuclear complex following the end of the cold war, many suitable facilities at DOE sites are increasingly costly to operate and are being evaluated for closure. A hot cell based laboratory that allowed developers to install and remove instrumentation from the hot cell would allow for both risk mitigation and performance optimization of the instrumentation prior to fielding equipment in facilities where maintenance and repair of the instrumentation is difficult or impossible. These benefits are accomplished by providing developers the opportunity to iterate between testing the performance of the instrumentation by measuring realistic types and amounts of nuclear material, and adjusting and refining the instrumentation based on the results of these measurements. In this paper, we review the requirements for such a facility using the Wing 9 hot cells in the Los Alamos National Laboratory's Chemistry and Metallurgy Research facility as a model for such a facility and describe recent use of these hot cells in support of AFCI.

  3. Integrated safeguards testing laboratories in support of the advanced fuel cycle initiative

    Energy Technology Data Exchange (ETDEWEB)

    Santi, Peter A [Los Alamos National Laboratory; Demuth, Scott F [Los Alamos National Laboratory; Klasky, Kristen L [Los Alamos National Laboratory; Lee, Haeok [Los Alamos National Laboratory; Miller, Michael C [Los Alamos National Laboratory; Sprinkle, James K [Los Alamos National Laboratory; Tobin, Stephen J [Los Alamos National Laboratory; Williams, Bradley [DOE, NE

    2009-01-01

    A key enabler for advanced fuel cycle safeguards research and technology development for programs such as the Advanced Fuel Cycle Initiative (AFCI) is access to facilities and nuclear materials. This access is necessary in many cases in order to ensure that advanced safeguards techniques and technologies meet the measurement needs for which they were designed. One such crucial facility is a hot cell based laboratory which would allow developers from universities, national laboratories, and commercial companies to perform iterative research and development of advanced safeguards instrumentation under realistic operating conditions but not be subject to production schedule limitations. The need for such a facility arises from the requirement to accurately measure minor actinide and/or fission product bearing nuclear materials that cannot be adequately shielded in glove boxes. With the contraction of the DOE nuclear complex following the end of the cold war, many suitable facilities at DOE sites are increasingly costly to operate and are being evaluated for closure. A hot cell based laboratory that allowed developers to install and remove instrumentation from the hot cell would allow for both risk mitigation and performance optimization of the instrumentation prior to fielding equipment in facilities where maintenance and repair of the instrumentation is difficult or impossible. These benefits are accomplished by providing developers the opportunity to iterate between testing the performance of the instrumentation by measuring realistic types and amounts of nuclear material, and adjusting and refining the instrumentation based on the results of these measurements. In this paper, we review the requirements for such a facility using the Wing 9 hot cells in the Los Alamos National Laboratory's Chemistry and Metallurgy Research facility as a model for such a facility and describe recent use of these hot cells in support of AFCI.

  4. Administrative mechanics of research fuel transportation

    International Nuclear Information System (INIS)

    Harmon, Diane W.

    1983-01-01

    This presentation contains the discussion on the multitude of administrative mechanics that have to be meshed for the successful completion of a shipment of spent fuel, HEU or LEU in the research reactors fuel cycle. The costs associated with transportation may be the equivalent of 'a black hole', so an overview of cost factors is given. At the end one could find that this black hole factor in the budget is actually a bargain. The first step is the quotation phase. The cost variables in the quotation contain the cost of packaging i.e. containers; the complete routing of the packages and the materials. Factors that are of outmost importance are the routing restrictions and regulations, physical security regulations. All of this effort is just to provide a valid quotation not to accomplish the goal of completing a shipment. Public relations cannot be omitted either

  5. Administrative mechanics of research fuel transportation

    Energy Technology Data Exchange (ETDEWEB)

    Harmon, Diane W [Edlow International Company, Washington, DC (United States)

    1983-09-01

    This presentation contains the discussion on the multitude of administrative mechanics that have to be meshed for the successful completion of a shipment of spent fuel, HEU or LEU in the research reactors fuel cycle. The costs associated with transportation may be the equivalent of 'a black hole', so an overview of cost factors is given. At the end one could find that this black hole factor in the budget is actually a bargain. The first step is the quotation phase. The cost variables in the quotation contain the cost of packaging i.e. containers; the complete routing of the packages and the materials. Factors that are of outmost importance are the routing restrictions and regulations, physical security regulations. All of this effort is just to provide a valid quotation not to accomplish the goal of completing a shipment. Public relations cannot be omitted either.

  6. Neutron Focusing Mirrors for Neutron Radiography of Irradiated Nuclear Fuel at Idaho National Laboratory

    Science.gov (United States)

    Rai, Durgesh K.; Wu, Huarui; Abir, Muhammad; Giglio, Jeffrey; Khaykovich, Boris

    Post irradiation examination (PIE) of samples irradiated in nuclear reactors is a challenging but necessary task for the development on novel nuclear power reactors. Idaho National Laboratory (INL) has neutron radiography capabilities, which are especially useful for the PIE of irradiated nuclear fuel. These capabilities are limited due to the extremely high gamma-ray radiation from the irradiated fuel, which precludes the use of standard digital detectors, in turn limiting the ability to do tomography and driving the cost of the measurements. In addition, the small 250 kW Neutron Radiography Reactor (NRAD) provides a relatively weak neutron flux, which leads to low signal-to-noise ratio. In this work, we develop neutron focusing optics suitable for the installation at NRAD. The optics would separate the sample and the detector, potentially allowing for the use of digital radiography detectors, and would provide significant intensity enhancement as well. The optics consist of several coaxial nested Wolter mirrors and is suited for polychromatic thermal neutron radiation. Laboratory Directed Research and Development program of Idaho National Laboratory.

  7. Fuels from microalgae: Technology status, potential, and research requirements

    Energy Technology Data Exchange (ETDEWEB)

    Neenan, B.; Feinberg, D.; Hill, A.; McIntosh, R.; Terry, K.

    1986-08-01

    Although numerous options for the production of fuels from microalgae have been proposed, our analysis indicates that only two qualify for extensive development - gasoline and ester fuel. In developing the comparisons that support this conclusion, we have identified the major areas of microalgae production and processing that require extensive development. Technology success requires developing and testing processes that fully utilize the polar and nonpolar lipids produced by microalgae. Process designs used in these analyses were derived from fragmented, preliminary laboratory data. These results must be substantiated and integrated processes proposed, tested, and refined to be able to evaluate the commercial feasibility from microalgae. The production of algal feedstocks for processing to gasoline or ester fuel requires algae of high productivity and high lipid content that efficiently utilize saline waters. Species screening and development suggest that algae can achieve required standards taken individually, but algae that can meet the integrated requirements still elude researchers. Effective development of fuels from microalgae technology requires that R and D be directed toward meeting the integrated standards set out in the analysis. As technology analysts, it is inappropriate for us to dictate how the R and D effort should proceed to meet these standards. We end our role by noting that alternative approaches to meeting the feasibility targets have been identified, and it is now the task of program managers and scientists to choose the appropriate approach to assure the greatest likelihood of realizing a commercially viable technology. 70 refs., 39 figs., 35 tabs.

  8. Analyses of the transportation of spent research reactor fuel in the United States

    International Nuclear Information System (INIS)

    Cashwell, J.W.; Neuhauser, K.S.

    1989-01-01

    The Transportation Technology Center at Sandia National Laboratories has analyzed the impacts of transportation of research reactor spent fuel from US and foreign reactors for the US Department of Energy (DOE) Office of Defense Programs. This effort represents the first comprehensive analytical evaluation of the risks of transporting high-, medium-, and low-enriched uranium spent research reactor fuel by both sea and land. Two separate shipment programs have been analyzed: the shipment of research reactor spent fuel from Taiwan to the US (Fuel Movement Program), and the return of research reactor spent fuels of US origin from foreign and domestic reactors (Research Reactor Fuel Return Program). In order to perform these analyses, a comprehensive methodology for analyzing the probabilities and consequences of transportation in coastal waters and port facilities, handling at the port, and shipment by truck to reprocessing facilities was developed. The Taiwanese fuel consists of low-burnup aluminum-clad metallic uranium research reactor spent fuel; the other fuels are primarily aluminum-clad oxide fuels. The Fuel Movement Program is ongoing, while the Fuel Return Program addresses future shipments over a ten-year period. The operational aspects of the Taiwanese shipments have been uniform, but several possible shipping configurations are possible for the Fuel Return Program shipments. Comprehensive assessments, which bound the impacts of spent fuel transport, demonstrate that when shipments are made in compliance with applicable regulations, the risks for all such transport are low. For comparison with previously licensed transport activities and to provide continuity with earlier analyses, the results for shipment of 150-day-old commercial pressurized water reactor (PWR) spent fuel are presented as part of this study

  9. Advanced Combustion and Fuels; NREL (National Renewable Energy Laboratory)

    Energy Technology Data Exchange (ETDEWEB)

    Zigler, Brad

    2015-06-08

    Presented at the U.S. Department of Energy Vehicle Technologies Office 2015 Annual Merit Review and Peer Evaluation Meeting, held June 8-12, 2015, in Arlington, Virginia. It addresses technical barriers of inadequate data and predictive tools for fuel and lubricant effects on advanced combustion engines, with the strategy being through collaboration, develop techniques, tools, and data to quantify critical fuel physico-chemical effects to enable development of advanced combustion engines that use alternative fuels.

  10. Welded rupture disc assemblies for use in Tritium Research Laboratory

    International Nuclear Information System (INIS)

    Faltings, R.E.

    1976-01-01

    Welded rupture disc assemblies were investigated and developed in various ranges for probable use by experimenters in their activities in the Tritium Research Laboratory at Sandia Laboratories, Livermore. This study indicates that currently welded rupture disc assemblies with appropriate testing and installation by certified pressure installers may be used in pressure systems in the Tritium Research Laboratory and other areas at SLL

  11. AECL's underground research laboratory: technical achievements and lessons learned

    International Nuclear Information System (INIS)

    Ohta, M.M.; Chandler, N.A.

    1997-03-01

    During the development of the research program for the Canadian Nuclear Fuel Waste Management Program in the 1970's, the need for an underground facility was recognized. AECL constructed an Underground Research Laboratory (URL) for large-scale testing and in situ engineering and performance-assessment-related experiments on key aspects of deep geological disposal in a representative geological environment. Ale URL is a unique geotechnical research and development facility because it was constructed in a previously undisturbed portion of a granitic pluton that was well characterized before construction began, and because most of the shaft and experimental areas are below the water table. The specific areas of research, development and demonstration include surface and underground characterization; groundwater and solute transport; in situ rock stress conditions; temperature and time-dependent deformation and failure characteristics of rock; excavation techniques to minimize damage to surrounding rock and to ensure safe working conditions; and the performance of seals and backfills. This report traces the evolution of the URL and summarizes the technical achievements and lessons learned during its siting, design and construction, and operating phases over the last 18 years. (author)

  12. Fuel Fabrication Capability Research and Development Plan

    Energy Technology Data Exchange (ETDEWEB)

    Senor, David J.; Burkes, Douglas

    2014-04-17

    The purpose of this document is to provide a comprehensive review of the mission of the Fuel Fabrication Capability (FFC) within the Global Threat Reduction Initiative Convert Program, along with research and development (R&D) needs that have been identified as necessary to ensuring mission success. The design and fabrication of successful nuclear fuels must be closely linked endeavors. Therefore, the overriding motivation behind the FFC R&D program described in this plan is to foster closer integration between fuel design and fabrication to reduce programmatic risk. These motivating factors are all interrelated, and progress addressing one will aid understanding of the others. The FFC R&D needs fall into two principal categories, 1) baseline process optimization, to refine the existing fabrication technologies, and 2) manufacturing process alternatives, to evaluate new fabrication technologies that could provide improvements in quality, repeatability, material utilization, or cost. The FFC R&D Plan examines efforts currently under way in regard to coupon, foil, plate, and fuel element manufacturing, and provides recommendations for a number of R&D topics that are of high priority but not currently funded (i.e., knowledge gaps). The plan ties all FFC R&D efforts into a unified vision that supports the overall Convert Program schedule in general, and the fabrication schedule leading up to the MP-1 and FSP-1 irradiation experiments specifically. The fabrication technology decision gates and down-selection logic and schedules are tied to the schedule for fabricating the MP-1 fuel plates, which will provide the necessary data to make a final fuel fabrication process down-selection. Because of the short turnaround between MP-1 and the follow-on FSP-1 and MP-2 experiments, the suite of specimen types that will be available for MP-1 will be the same as those available for FSP-1 and MP-2. Therefore, the only opportunity to explore parameter space and alternative processing

  13. Research at the Oak Ridge National Laboratory (ORNL)

    International Nuclear Information System (INIS)

    Postma, H.

    1980-01-01

    The Oak Ridge National Laboratory is a large (5300 people), US-government-funded laboratory, which performs research in many disciplines and in many technological areas. Programs and organization of ORNL are described for the People's Republic of China

  14. GCFR Fuels and Materials Program at Argonne National Laboratory

    International Nuclear Information System (INIS)

    Neimark, L.A.; Greenberg, S.; Johnson, C.E.; Purohit, A.; Liu, Y.Y.; Rest, J.; Reimann, K.J.; McLennan, G.A.

    1979-01-01

    The F-5 fuel-pin irradiation experiment in EBR-II is a cornerstone of the GCFR program. It is the largest-scale fuel-pin experiment in the present program and will provide data on the performance of pins and a pin-support structure that are prototypic of the GCFR Demonstration Plant. The fuel pins are presently undergoing interim examination after successfully achieving 4.6 at.% burnup. Studies of the thermodynamics and kinetics of the U--Cs--O system, supplemented by analysis of the results of previously irradiated fuel pins, have led to the incorporation of fuel-design modifications in the F-5 experiment to insure adequate performance of the vented fuel. The effect of ribbing, as well as the ribbing process, on the short- and long-term structural performance of fuel-pin cladding is being evaluated via in-reactor and out-of-reactor tests and with the fuel-element modeling code LIFE-GCFR and the finite element program, ADINA

  15. Development of excavation technologies at the Canadian underground research laboratory

    International Nuclear Information System (INIS)

    Kuzyk, Gregory W.; Martino, Jason B.

    2008-01-01

    Several countries, Canada being among them, are developing concepts for disposal of used fuel from power generating nuclear reactors. As in underground mining operations, the disposal facilities will require excavation of many kilometres of shafts and tunnels through the host rock mass. The need to maintain the stability of excavations and safety of workers will be of paramount importance. Also, excavations required for many radioactive waste repositories will ultimately need to be backfilled and sealed to maintain stability and minimize any potential for migration of radionuclides, should they escape their disposal containers. The method used to excavate the tunnels and shafts, and the rock damage that occurs due to excavation, will greatly affect the performance characteristics of repository sealing systems. The underground rock mechanics and geotechnical engineering work performed at the Canadian Underground Research Laboratory (URL) has led to the development of excavation technologies that reduce rock damage in subsurface excavations. This paper discusses the excavation methods used to construct the URL and their application in planning for the construction of similar underground laboratories and repositories for radioactive wastes. (author)

  16. Research and development of nitride fuel cycle technology in Japan

    International Nuclear Information System (INIS)

    Minato, Kazuo; Arai, Yasuo; Akabori, Mitsuo; Tamaki, Yoshihisa; Itoh, Kunihiro

    2004-01-01

    The research on the nitride fuel was started for an advanced fuel, (U, Pn)N, for fast reactors, and the research activities have been expanded to minor actinide bearing nitride fuels. The fuel fabrication, property measurements, irradiation tests and pyrochemical process experiments have been made. In 2002 a five-year-program named PROMINENT was started for the development of nitride fuel cycle technology within the framework of the Development of Innovative Nuclear Technologies by the Ministry of Education, Culture, Sports, Science and Technology of Japan. In the research program PROMINENT, property measurements, pyrochemical process and irradiation experiments needed for nitride fuel cycle technology are being made. (author)

  17. Status of research reactor spent fuel world-wide

    International Nuclear Information System (INIS)

    Ritchie, I.G.

    2004-01-01

    Results compiled in the research reactor spent fuel database are used to assess the status of research reactor spent fuel world-wide. Fuel assemblies, their types, enrichment, origin of enrichment and geological distribution among the industrialised and developed countries of the world are discussed. Fuel management practices in wet and dry storage facilities and the concerns of reactor operators about long-term storage of their spent fuel are presented and some of the activities carried out by the International Atomic Energy Agency to address the issues associated with research reactor spent fuel are outlined. (author)

  18. Shaping future US fuels: A local market laboratory

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    As air pollution becomes a worsening problem around the world, alternative fuels are supported by many as a way to reduce vehicle emissions without impeding mobility. On June 22, 1992, the South Coast Alternative Fuels Demonstration Project, CleanFleet, was launched. CleanFleet is a two-year program that will evaluate the performance of five alternative transportation fuels in a major commercial fleet. The study promises to identify the advantages and pitfalls of five alternative fuels on the basis of emissions, safety, maintenance, reliability, performance, and durability. This issue also contains the following: (1) the ED Refining Netback Data Series for the US Gulf and West Coasts, Rotterdam, and Singapore as of July 10, 1992; and (2) the ED Fuel Price/Tax Series for countries of the Western Hemisphere, July 1992 Edition

  19. Fuel cells - from the laboratory to the road

    Energy Technology Data Exchange (ETDEWEB)

    Fronk, M.H. [Delphi Energy and Engine Management Systems, Rochester, NY (United States)

    1996-12-31

    The polymer electrolyte membrane (PEM) Fuel Cell faces stiff competition from existing automotive powerplants and other Hybrid APUs. To be successful, the Fuel Cell will have to demonstrate real customer advantages such as fuel economy and emissions. The PEM technology has an inherent advantage over other powerplants in both thermal efficiency and emission performance, and as such fits in very well with the future regulations that strive to clean up the environment. In addition, it will need to be cost competitive and provide acceptable performance. The majority of development activity on PEM Fuel Cells to date has concentrated primarily in the area of Stack refinement and optimization with improvements coming in higher power densities and higher specific power. To make the Fuel Cell compatible with an automotive environment the entire system will need to be analyzed, understood, and then engineered to work together in an efficient manner.

  20. Examination in hot laboratories of irradiated fuels from fast reactors

    International Nuclear Information System (INIS)

    Clottes, G.; Peray, R.; Ratier, J.L.

    1980-05-01

    Low irradiation rate examinations were carried out soon after the Rapsodie, Rapsodie Fortissimo and Phenix reactors were started up for the first time in order to check the level of maximum temperatures reached and the radial migration of oxygen and plutonium and to assess the movements of fuels inside the cladding. The other examinations were effected at a high specific burnup in order to defines the limit specific burnup securing the integrity of the fuel pin claddings (distortion, ruptures and possible consequences). The examinations carried out so far on fuel elements coming from Phenix or Rapsodie have allowed good fuel surveillance to be undertaken and the acquisition of a large number of data, thanks to which the fuel characteristics of future reactors of the system have been developed [fr

  1. 78 FR 28292 - Joint Biomedical Laboratory Research and Development and Clinical Science Research and...

    Science.gov (United States)

    2013-05-14

    ... DEPARTMENT OF VETERANS AFFAIRS Joint Biomedical Laboratory Research and Development and Clinical Science Research and Development Services Scientific Merit Review Board; Notice of Meetings; Amendment The... Joint Biomedical Laboratory Research and Development and Clinical Science Research and Development...

  2. Fuels and Combustion | Transportation Research | NREL

    Science.gov (United States)

    Fuels and Combustion Fuels and Combustion This is the March 2015 issue of the Transportation and , combustion strategy, and engine design hold the potential to maximize vehicle energy efficiency and performance of low-carbon fuels in internal combustion engines with a whole-systems approach to fuel chemistry

  3. The Swedish Research Councils' Laboratory progress report for 1975

    International Nuclear Information System (INIS)

    Rudstam, G.

    1976-01-01

    The Swedish Research Councils' Laboratory herewith presents its progress report for 1975. The report summarizes the current projects carried out by the research groups working at the laboratory. The very efficient assistance of the staff of the laboratory is greatfully acknowledged. The laboratory has been financially supported by the Atomic Research Council, the Medical Research Council, the Natural Science Research Council, and the Board of Technical Development. Valuable support in various ways has also been given by the Atomic Energy Company (AB Atomenergi). (author)

  4. Research report 1987-1989: Environmental Quality Laboratory and Environmental Engineering Science, W. M. Keck Laboratories

    OpenAIRE

    Brooks, Norman H.

    1990-01-01

    This research biennial report for 1987-89 covers the activities of both the Environmental Engineering Science program and the Environmental Quality Laboratory for the period October 1987-November 1989. Environmental Engineering Science is the degree-granting academic program housed in the Keck Laboratories, with associated research projects. The Environmental Quality Laboratory is a research center focusing on large scale problems of environmental quality and natural resources. All the facult...

  5. Overview of remote technologies applied to research reactor fuel

    International Nuclear Information System (INIS)

    Oerdoegh, M.; Takats, F.

    1999-01-01

    This paper gives a brief overview of the remote technologies applied to research reactor fuels. Due to many reasons, the remote technology utilization to research reactor fuel is not so widespread as it is for power reactor fuels, however, the advantages of the application of such techniques are obvious. (author)

  6. Mobile teleoperator research at Savannah River Laboratory

    International Nuclear Information System (INIS)

    Byrd, J.S.

    1985-01-01

    A Robotics Technology Group was organized at Savannah River Laboratory to employ modern automation and robotics for applications at the Savannah River site. Several industrial robots have been installed in plant processes. Other robotics systems are under development in the laboratories, including mobile teleoperators for general remote tasks and emergency response operations. This paper discusses present work on a low-cost wheeled mobile vehicle, a modular light duty manipulator arm, a large gantry telerobot system, and a high technology six-legged walking robot with a teleoperated arm

  7. Social science to improve fuels management: a synthesis of research on aesthetics and fuels management

    Science.gov (United States)

    Robert L. Ryan

    2005-01-01

    A series of syntheses were commissioned by the USDA Forest Service to aid in fuels mitigation project planning. This synthesis focuses on research addressing aesthetic considerations of fuels management. A general finding is that fuels management activities can contribute to the visual quality of a landscape. Topics covered in the synthesis include research findings on...

  8. Management and storage of spent fuel from CEA research reactors

    International Nuclear Information System (INIS)

    Merchie, F.

    1996-01-01

    CEA research reactors and their interim spent fuel storage facilities are described. Long-term solutions for spent fuel storage problems, involving wet storage at PEGASE or dry storage at CASCAD, are outlined in some detail. (author)

  9. Corrosion of research reactor aluminium clad spent fuel in water

    International Nuclear Information System (INIS)

    2003-01-01

    This report describes research performed in ten laboratories within the framework of the IAEA Co-ordinated Research Project on Corrosion of Research Reactor Aluminium Clad Spent Fuel in Water. The project consisted of exposure of standard racks of corrosion coupons in the spent fuel pools of the participating research reactor laboratories and the evaluation of the coupons after predetermined exposure times, along with periodic monitoring of the storage water. A group of experts in the field contributed a state of the art review and provided technical supervision of the project. Localized corrosion mechanisms are notoriously difficult to understand, and it was clear from the outset that obtaining consistency in the results and their interpretation from laboratory to laboratory would depend on the development of an excellent set of experimental protocols. These experimental protocols are described in the report together with guidelines for the maintenance of optimum water chemistry to minimize the corrosion of aluminium clad research reactor fuel in wet storage. A large database on corrosion of aluminium clad materials has been generated from the CRP and the SRS corrosion surveillance programme. An evaluation of these data indicates that the most important factors contributing to the corrosion of the aluminium are: (1) High water conductivity (100-200 μS/cm); (2) Aggressive impurity ion concentrations (Cl - ); (3) Deposition of cathodic particles on aluminium (Fe, etc.); (4) Sludge (containing Fe, Cl - and other ions in concentrations greater than ten times the concentrations in the water); (5) Galvanic couples between dissimilar metals (stainless steel-aluminium, aluminium-uranium, etc); (6) Scratches and imperfections (in protective oxide coating on cladding); (7) Poor water circulation. These factors operating both independently and synergistically may cause corrosion of the aluminium. The single most important key to preventing corrosion is maintaining good

  10. Laboratory characterization of PM emissions from combustion of wildland biomass fuels

    Science.gov (United States)

    Seyedehsan Hosseini; Shawn Urbanski; P. Dixit; Qi Li; Ian Burling; Robert Yokelson; Timothy E. Johnson; Manish Sharivastava; Heejung Jung; David R. Weise; Wayne Miller; David Cocker

    2013-01-01

    Particle emissions from open burning of southwestern (SW) and southeastern (SE) U.S. fuel types during 77 controlled laboratory burns are presented. The fuels include SW vegetation types: ceanothus, chamise/scrub oak, coastal sage scrub, California sagebrush, manzanita, maritime chaparral, masticated mesquite, oak savanna, and oak woodland, as well as SE vegetation...

  11. Fuel particle coating data. [Detailed information on coating runs at Los Alamos Scientific Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Hollabaugh, C.M.; Wagner, P.; Wahman, L.A.; White, R.W.

    1977-01-01

    Development of coating on nuclear fuel particles for the High-Temperature Fuels Technology program at the Los Alamos Scientific Laboratory included process studies for low-density porous and high-density isotropic carbon coats, and for ZrC and ''alloy'' C/ZrC coats. This report documents the data generated by these studies.

  12. Ultra-Short-Pulse Laser Effects Research and Analysis Laboratory

    Data.gov (United States)

    Federal Laboratory Consortium — FUNCTION: Enables research into advanced laser countermeasure techniques.DESCRIPTION: This laser facility has a capability to produce very high peak power levels of...

  13. Solar Radiation Research Laboratory | Energy Systems Integration Facility |

    Science.gov (United States)

    Solar Radiation Research Laboratory (SRRL) has been collecting continuous measurements of basic solar continuous operation. More than 75 instruments contribute to the Baseline Measurement System by recording

  14. Management of legacy spent nuclear fuel wastes at the Chalk River Laboratories: operating experience and progress towards waste remediation

    International Nuclear Information System (INIS)

    Cox, D.S.; Bainbridge, I.B.; Greenfield, K.R.

    2006-01-01

    AECL has been managing and storing a diversity of spent nuclear fuel, arising from operations at its Chalk River Laboratories (CRL) site over more than 50 years. A subset of about 22 tonnes of research reactor fuels, primarily metallic uranium, have been identified as a high priority for remediation, based on monitoring and inspection that has determined that these fuels and their storage containers are corroding. This paper describes the Fuel Packaging and Storage (FPS) project, which AECL has launched to retrieve these fuels from current storage, and to emplace them in a new above-ground dry storage system, as a prerequisite step to decommissioning some of the early-design waste storage structures at CRL. The retrieved fuels will be packaged in a new storage container, and subjected to a cold vacuum drying process that will remove moisture, and thereby reduce the extent of future corrosion and degradation. The FPS project will enable improved interim storage to be implemented for legacy fuels at CRL, until a decision is made on the ultimate disposition of legacy fuels in Canada. (author)

  15. Sandia, California Tritium Research Laboratory transition and reutilization project

    Energy Technology Data Exchange (ETDEWEB)

    Garcia, T.B. [Sandia National Lab., Albuquerque, NM (United States)

    1997-02-01

    This paper describes a project within Sandia National Laboratory to convert the shut down Tritium Research Laboratory into a facility which could be reused within the laboratory complex. In the process of decommissioning and decontaminating the facility, the laboratory was able to save substantial financial resources by transferring much existing equipment to other DOE facilities, and then expeditiously implementing a decontamination program which has resulted in the building being converted into laboratory space for new lab programs. This project of facility reuse has been a significant financial benefit to the laboratory.

  16. Alternative Fuel Research in Fischer-Tropsch Synthesis

    Science.gov (United States)

    Surgenor, Angela D.; Klettlinger, Jennifer L.; Yen, Chia H.; Nakley, Leah M.

    2011-01-01

    NASA Glenn Research Center has recently constructed an Alternative Fuels Laboratory which is solely being used to perform Fischer-Tropsch (F-T) reactor studies, novel catalyst development and thermal stability experiments. Facility systems have demonstrated reliability and consistency for continuous and safe operations in Fischer-Tropsch synthesis. The purpose of this test facility is to conduct bench scale Fischer-Tropsch (F-T) catalyst screening experiments while focusing on reducing energy inputs, reducing CO2 emissions and increasing product yields within the F-T process. Fischer-Tropsch synthesis is considered a gas to liquid process which reacts syn-gas (a gaseous mixture of hydrogen and carbon monoxide), over the surface of a catalyst material which is then converted into liquids of various hydrocarbon chain length and product distributions1. These hydrocarbons can then be further processed into higher quality liquid fuels such as gasoline and diesel. The experiments performed in this laboratory will enable the investigation of F-T reaction kinetics to focus on newly formulated catalysts, improved process conditions and enhanced catalyst activation methods. Currently the facility has the capability of performing three simultaneous reactor screening tests, along with a fourth fixed-bed reactor used solely for cobalt catalyst activation.

  17. The use of medium enriched uranium fuel for research reactors

    International Nuclear Information System (INIS)

    1979-01-01

    The evaluation described in the present paper concerns the use of medium enriched uranium fuel for our research reactors. The underlying assumptions set up for the evaluation are as follows: (1) At first, the use of alternative fuel should not affect, even to a small extent, research and development programs in nuclear energy utilization, which were described in the previous paper. Hence the use of lower enrichment fuel should not cause any reduction in reactor performances. (2) The fuel cycle cost for operating research reactors with alternative fuel, excepting R and D cost for such fuel, should not increase beyond an acceptable limit. (3) The use of alternative fuel should be satisfactory with respect to non-proliferation purposes, to the almost same degree as the use of 20% enriched uranium fuel

  18. Annual report on operation, utilization and technical development of research reactors and hot laboratory

    International Nuclear Information System (INIS)

    1990-09-01

    This report describes the activities of the Department of Research Reactor Operation in fiscal year of 1989. It also presents some technical topics on the reactor operation and utilization in details. The Department is responsible for operation of the research reactors, JRR-2 and JRR-4, and the Hot Laboratory. The research reactor JRR-3 was reconstructed to enhance the performance for utilization. The first criticality was achieved on March 22, 1989, and it subsequently went into operation. In connection with the reactor operation, the various research and development activities in the area of fuel management, water chemistry, radiation monitoring and material irradiation have been made. In the Hot Laboratory, post-irradiation examinations of fuels and materials have been carried out along with the development of related techniques. (author)

  19. Laboratory Directed Research and Development FY-15 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    Pillai, Rekha Sukamar [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-03-01

    The Laboratory Directed Research and Development (LDRD) Program at Idaho National Laboratory (INL) reports its status to the U.S. Department of Energy (DOE) by March of each year. The program operates under the authority of DOE Order 413.2B, “Laboratory Directed Research and Development” (April 19, 2006), which establishes DOE’s requirements for the program while providing the laboratory director broad flexibility for program implementation. LDRD funds are obtained through a charge to all INL programs. This report includes summaries of all INL LDRD research activities supported during Fiscal Year (FY) 2015.

  20. LDRD 2013 Annual Report: Laboratory Directed Research and Development Program Activities

    Energy Technology Data Exchange (ETDEWEB)

    Bookless, W. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2013-12-31

    This LDRD project establishes a research program led by Jingguang Chen, who has started a new position as a Joint Appointee between BNL and Columbia University as of FY2013. Under this project, Dr. Chen will establish a new program in catalysis science at BNL and Columbia University. The LDRD program will provide initial research funding to start research at both BNL and Columbia. At BNL, Dr. Chen will initiate laboratory research, including hiring research staff, and will collaborate with the existing BNL catalysis and electrocatalysis research groups. At Columbia, a subcontract to Dr. Chen will provide startup funding for his laboratory research, including initial graduate student costs. The research efforts will be linked under a common Catalysis Program in Sustainable Fuels. The overall impact of this project will be to strengthen the BNL catalysis science program through new linked research thrusts and the addition of an internationally distinguished catalysis scientist.

  1. High Burnup Fuel Performance and Safety Research

    Energy Technology Data Exchange (ETDEWEB)

    Bang, Je Keun; Lee, Chan Bok; Kim, Dae Ho (and others)

    2007-03-15

    The worldwide trend of nuclear fuel development is to develop a high burnup and high performance nuclear fuel with high economies and safety. Because the fuel performance evaluation code, INFRA, has a patent, and the superiority for prediction of fuel performance was proven through the IAEA CRP FUMEX-II program, the INFRA code can be utilized with commercial purpose in the industry. The INFRA code was provided and utilized usefully in the universities and relevant institutes domesticallly and it has been used as a reference code in the industry for the development of the intrinsic fuel rod design code.

  2. Laboratory Directed Research and Development FY-10 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    Dena Tomchak

    2011-03-01

    The FY 2010 Laboratory Directed Research and Development (LDRD) Annual Report is a compendium of the diverse research performed to develop and ensure the INL's technical capabilities can support the future DOE missions and national research priorities. LDRD is essential to the INL -- it provides a means for the laboratory to pursue novel scientific and engineering research in areas that are deemed too basic or risky for programmatic investments. This research enhances technical capabilities at the laboratory, providing scientific and engineering staff with opportunities for skill building and partnership development.

  3. Advancing Molten Salts and Fuels at Sandia National Laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez, Salvador B. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-09-26

    SNL has a combination of experimental facilities, nuclear engineering, nuclear security, severe nuclear accidents, and nuclear safeguards expertise that can enable significant progress towards molten salts and fuels for Molten Salt Reactors (MSRs). The following areas and opportunities are discussed in more detail in this white paper.

  4. Material Transfer Agreement (MTA) | Frederick National Laboratory for Cancer Research

    Science.gov (United States)

    Material Transfer Agreements are appropriate for exchange of materials into or out of the Frederick National Laboratory for research or testing purposes, with no collaborative research by parties involving the materials.

  5. Senior Laboratory Animal Technician | Center for Cancer Research

    Science.gov (United States)

    PROGRAM DESCRIPTION The Laboratory Animal Sciences Program (LASP) provides exceptional quality animal care and technical support services for animal research performed at the National Cancer Institute at the Frederick National Laboratory for Cancer Research. LASP executes this mission by providing a broad spectrum of state-of-the-art technologies and services that are focused

  6. Project development laboratories energy fuels and oils based on NRU “MPEI”

    Science.gov (United States)

    Burakov, I. A.; Burakov, A. Y.; Nikitina, I. S.; Khomenkov, A. M.; Paramonova, A. O.; Khtoo Naing, Aung

    2017-11-01

    In the process of improving the efficiency of power plants a hot topic is the use of high-quality fuels and lubricants. In the process of transportation, preparation for use, storage and maintenance of the properties of fuels and lubricants may deteriorate, which entails a reduction in the efficiency of power plants. One of the ways to prevent the deterioration of the properties is a timely analysis of the relevant laboratories. In this day, the existence of laboratories of energy fuels and energy laboratory oil at thermal power stations is satisfactory character. However, the training of qualified personnel to work in these laboratories is a serious problem, as the lack of opportunities in these laboratories a complete list of required tests. The solution to this problem is to explore the possibility of application of methods of analysis of the properties of fuels and lubricants in the stage of training and re-training of qualified personnel. In this regard, on the basis of MPEI developed laboratory projects of solid, liquid and gaseous fuels, power and energy oils and lubricants. Projects allow for a complete list of tests required for the timely control of properties and prevent the deterioration of these properties. Assess the financial component of the implementation of the developed projects based on the use of modern equipment used for tests. Projects allow for a complete list of tests required for the timely control of properties and prevent the deterioration of these properties.

  7. Laboratory Directed Research and Development annual report, fiscal year 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    The Department of Energy Order 413.2(a) establishes DOE`s policy and guidelines regarding Laboratory Directed Research and Development (LDRD) at its multiprogram laboratories. As described in 413.2, LDRD is research and development of a creative and innovative nature which is selected by the Laboratory Director or his or her designee, for the purpose of maintaining the scientific and technological vitality of the Laboratory and to respond to scientific and technological opportunities in conformance with the guidelines in this Order. DOE Order 413.2 requires that each laboratory submit an annual report on its LDRD activities to the cognizant Secretarial Officer through the appropriate Operations Office Manager. The report provided in this document represents Pacific Northwest National Laboratory`s LDRD report for FY 1997.

  8. The risks of the Taiwan research reactor spent fuel project

    International Nuclear Information System (INIS)

    1991-06-01

    The proposed action is to transport up to 118 spent fuel rods, to include canned spent fuel rod particulates immobilized on filters, from a research reactor in Taiwan by sea to Hampton Roads, Virginia, and then overland by truck to the Receiving Basin for Offsite Fuels at the Savannah River Site (SRS). At SRS, the spent fuel will be reprocessed to recover uranium and plutonium. 55 refs., 8 tabs

  9. Laboratory Technology Research: Abstracts of FY 1996 projects

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    The Laboratory Technology Research (LTR) program supports high-risk, multidisciplinary research partnerships to investigate challenging scientific problems whose solutions have promising commercial potential. These partnerships capitalize on two great strengths of this country: the world-class basic research capability of the DOE Energy Research (ER) multi-program national laboratories and the unparalleled entrepreneurial spirit of American industry. Projects supported by the LTR program are conducted by the five ER multi-program laboratories: Argonne, Brookhaven, Lawrence Berkeley, Oak Ridge, and Pacific Northwest National Laboratories. These projects explore the applications of basic research advances relevant to Department of Energy`s (DOE) mission over a full range of scientific disciplines. The program presently emphasizes three critical areas of mission-related research: advanced materials, intelligent processing/manufacturing research, and sustainable environments.

  10. Logistic Fuel Processor Development

    National Research Council Canada - National Science Library

    Salavani, Reza

    2004-01-01

    The Air Base Technologies Division of the Air Force Research Laboratory has developed a logistic fuel processor that removes the sulfur content of the fuel and in the process converts logistic fuel...

  11. Fiscal 1974-1975 Sunshine Project research report. Hydrogen energy research results (National laboratories and institutes); 1974, 1975 nendo suiso energy kenkyu seika hokokushu. Kokuritsu shiken kenkyusho kankei

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1976-10-01

    This report summarizes the 21 research results on hydrogen energy promoted by 3 national laboratories and 2 national institutes. (1) Tokyo National Industrial Research Institute (TNIRI): Ca-I system, Mn system, S system and hybrid cycles, and water decomposition reaction by CO as thermochemical hydrogen production technique. (2) Osaka National Industrial Research Institute (ONIRI): Fe system, Cu system and ammonia system cycles, and high-temperature high-pressure water electrolysis. (3) Electrotechnical Laboratory: high- temperature direct thermolysis hydrogen production technique. (4) TNIRI: Mg-base and transition metal-base hydrogen solidification technique. (5) ONIRI: Ti-base and rare metal- base hydrogen solidification technique. (6) Mechanical Engineering Laboratory: hydrogen-fuel engines. (7) Electrotechnical Laboratory and ONIRI: fuel cell. (8) TNIRI: disaster preventive technology for gaseous and liquid hydrogen. (9) Chugoku National Industrial Research Institute: preventing materials from embrittlement due to hydrogen. (10) Electrotechnical Laboratory: hydrogen energy system. (NEDO)

  12. Safeguards research at Lawrence Livermore Laboratory

    International Nuclear Information System (INIS)

    Dunn, D.R.; Huebel, J.G.; Poggio, A.J.

    1980-01-01

    The LLL safeguards research program includes inspection methods, facility assessment methodologies, value-impact analysis, vulnerability analysis of accounting systems, compliance with regulations, process monitoring, etc. Each of those projects is described as are their goals and progress

  13. Laboratory Directed Research and Development Program: FY 2015 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    SLAC,

    2016-04-04

    The Department of Energy (DOE) and the SLAC National Accelerator Laboratory (SLAC) encourage innovation, creativity, originality and quality to maintain the Laboratory’s research activities and staff at the forefront of science and technology. To further advance its scientific research capabilities, the Laboratory allocates a portion of its funds for the Laboratory Directed Research and Development (LDRD) program. With DOE guidance, the LDRD program enables SLAC scientists to make rapid and significant contributions that seed new strategies for solving important national science and technology problems. The LDRD program is conducted using existing research facilities.

  14. Research on bioorganic fuels as power sources

    Energy Technology Data Exchange (ETDEWEB)

    Lampinen, Markku J.; Spets, Jukka-Pekka [Aalto University, Department of Energy Technology-TKK, Applied Thermodynamics, PO Box 4400, FI-02201 TKK (Finland); Kiros, Yohannes [Royal Institute of Technology-KTH, Department of Chemical Engineering and Technology, S100-44 Stockholm (Sweden); Anttila, Tomi [Oy Hydrocell Ltd, Minkkikatu 1-3, 04430 Jaervenpaeae (Finland)

    2010-11-15

    This paper deals with the kind of the bioorganic fuel cells that are equipped with or without ion exchange membranes. The bioorganic materials of interest are alcohols (methanol, ethanol) and glucose, which are obtained from renewable energy sources such as biomass. The operation temperatures of the direct fuel cells cover from room temperature up to 150 C. The direct bioorganic fuel cells belong to the subject area of 'Advanced fuel cells' of the Working group 4 in the EU COST Action 543 among the collaborating Universities and Institutes. Bioorganic fuel cells are suitable for application in small portable power sources, such as backups, battery chargers and in electronic devices. A number of current and earlier works are summarised and advances are highlighted in this area with special emphasis on glucose as a fuel. (author)

  15. Laboratory Directed Research and Development Annual Report FY 2017

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan, Kelly O.

    2018-03-30

    A national laboratory must establish and maintain an environment in which creativity and innovation are encouraged and supported in order to fulfill its missions and remain viable in the long term. As such, multiprogram laboratories are given discretion to allocate a percentage of their operating budgets to support research and development projects that align to PNNL’s and DOE’s missions and support the missions of other federal agencies, including DHS, DOD, and others. DOE Order 413.2C sets forth DOE’s Laboratory Directed Research and Development (LDRD) policy and guidelines for DOE multiprogram laboratories, and it authorizes the national laboratories to allocate up to 6 percent of their operating budgets to fund the program. LDRD is innovative research and development, selected by the Laboratory Director or his/her designee, for the purpose of maintaining the scientific and technological vitality of the Laboratory. The projects supported by LDRD funding all have demonstrable ties to DOE/DHS missions and may also be relevant to the missions of other federal agencies that sponsor work at the Laboratory. The program plays a key role in attracting the best and brightest scientific staff, which is needed to serve the highest priority DOE mission objectives. Individual project reports comprise the bulk of this LDRD report. The Laboratory focuses its LDRD research on scientific assets that often address more than one scientific discipline.

  16. Laboratory Directed Research and Development Annual Report FY 2016

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan, Kelly O. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2017-03-30

    A national laboratory must establish and maintain an environment in which creativity and innovation are encouraged and supported in order to fulfill its missions and remain viable in the long term. As such, multiprogram laboratories are given discretion to allocate a percentage of their operating budgets to support research and development projects that align to PNNL’s and DOE’s missions and support the missions of other federal agencies, including DHS, DOD, and others. DOE Order 413.2C sets forth DOE’s Laboratory Directed Research and Development (LDRD) policy and guidelines for DOE multiprogram laboratories, and it authorizes the national laboratories to allocate up to 6 percent of their operating budgets to fund the program. LDRD is innovative research and development, selected by the Laboratory Director or his/her designee, for the purpose of maintaining the scientific and technological vitality of the Laboratory. The projects supported by LDRD funding all have demonstrable ties to DOE/DHS missions and may also be relevant to the missions of other federal agencies that sponsor work at the Laboratory. The program plays a key role in attracting the best and brightest scientific staff, which is needed to serve the highest priority DOE mission objectives. Individual project reports comprise the bulk of this LDRD report. The Laboratory focuses its LDRD research on scientific assets that often address more than one scientific discipline.

  17. PCI fuel failure analysis: a report on a cooperative program undertaken by Pacific Northwest Laboratory and Chalk River Nuclear Laboratories

    International Nuclear Information System (INIS)

    Mohr, C.L.; Pankaskie, P.J.; Heasler, P.G.; Wood, J.C.

    1979-12-01

    Reactor fuel failure data sets in the form of initial power (P/sub i/), final power (P/sub f/), transient increase in power (ΔP), and burnup (Bu) were obtained for pressurized heavy water reactors (PHWRs), boiling water reactors (BWRs), and pressurized water reactors (PWRs). These data sets were evaluated and used as the basis for developing two predictive fuel failure models, a graphical concept called the PCI-OGRAM, and a nonlinear regression based model called PROFIT. The PCI-OGRAM is an extension of the FUELOGRAM developed by AECL. It is based on a critical threshold concept for stress dependent stress corrosion cracking. The PROFIT model, developed at Pacific Northwest Laboratory, is the result of applying standard statistical regression methods to the available PCI fuel failure data and an analysis of the environmental and strain rate dependent stress-strain properties of the Zircaloy cladding

  18. DIissolution of low enriched uranium from the experimental breeder reactor-II fuel stored at the Idaho National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Daniel, G. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Rudisill, T. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Almond, P. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); O' Rourke, P. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-06-28

    The Idaho National Laboratory (INL) is actively engaged in the development of electrochemical processing technology for the treatment of fast reactor fuels using irradiated fuel from the Experimental Breeder Reactor-II (EBR-II) as the primary test material. The research and development (R&D) activities generate a low enriched uranium (LEU) metal product from the electrorefining of the EBR-II fuel and the subsequent consolidation and removal of chloride salts by the cathode processor. The LEU metal ingots from past R&D activities are currently stored at INL awaiting disposition. One potential disposition pathway is the shipment of the ingots to the Savannah River Site (SRS) for dissolution in H-Canyon. Carbon steel cans containing the LEU metal would be loaded into reusable charging bundles in the H-Canyon Crane Maintenance Area and charged to the 6.4D or 6.1D dissolver. The LEU dissolution would be accomplished as the final charge in a dissolver batch (following the dissolution of multiple charges of spent nuclear fuel (SNF)). The solution would then be purified and the 235U enrichment downblended to allow use of the U in commercial reactor fuel. To support this potential disposition path, the Savannah River National Laboratory (SRNL) developed a dissolution flowsheet for the LEU using samples of the material received from INL.

  19. Research Review: Laboratory Student Magazine Programs.

    Science.gov (United States)

    Wheeler, Tom

    1994-01-01

    Explores research on student-produced magazines at journalism schools, including the nature of various programs and curricular structures, ethical considerations, and the role of faculty advisors. Addresses collateral sources that provide practical and philosophical foundations for the establishment and conduct of magazine production programs.…

  20. Naval Research Laboratory Fact Book 2012

    Science.gov (United States)

    2012-11-01

    markets NRL’s patented inventions, negotiates patent license agreements under which the Navy grants a licensee the right to make, use, and sell NRL...Sr. Licensing Associate Social Media Marketing Associate Licensing Associate Management Analyst Administrative Assistant (SCEP) Administrative...ADMINISTRATIVE OFFICE SENIOR SCIENTIST FOR SUN-EARTH SYSTEMS RESEARCH 7605 GEOSPACE SCIENCE AND TECHNOLOGY BRANCH 7630 SPACE TEST PROGRAM ( STP

  1. Complete Flow Blockage of a Fuel Channel for Research Reactor

    International Nuclear Information System (INIS)

    Lee, Byeonghee; Park, Suki

    2015-01-01

    The CHF correlation suitable for narrow rectangular channels are implemented in RELAP5/MOD3.3 code for the analyses, and the behavior of fuel temperatures and MCHFR(minimum critical heat flux ratio) are compared between the original and modified codes. The complete flow blockage of fuel channel for research reactor is analyzed using original and modified RELAP5/MOD3.3 and the results are compared each other. The Sudo-Kaminaga CHF correlation is implemented into RELAP5/MOD3.3 for analyzing the behavior of fuel adjacent to the blocked channel. A flow blockage of fuel channels can be postulated by a foreign object blocking cooling channels of fuels. Since a research reactor with plate type fuel has isolated fuel channels, a complete flow blockage of one fuel channel can cause a failure of adjacent fuel plates by the loss of cooling capability. Although research reactor systems are designed to prevent foreign materials from entering into the core, partial flow blockage accidents and following fuel failures are reported in some old research reactors. In this report, an analysis of complete flow blockage accident is presented for a 15MW pool-type research reactor with plate type fuels. The fuel surface experience different heat transfer regime in the results from original and modified RELAP5/MOD3.3. By the discrepancy in heat transfer mode of two cases, a fuel melting is expected by the modified RELAP5/MOD3.3, whereas the fuel integrity is ensured by the original code

  2. Shipments of irradiated DIDO fuel from Risoe National Laboratory to the Savannah River Site - Challenges and achievements

    International Nuclear Information System (INIS)

    Anne, C.; Patterson, J.

    2003-01-01

    On September 28, 2000, the Board of Governors of Risoe National Laboratory decided to shut down the Danish research reactor DR3 due to technical problems (corrosion on the reactor aluminum tank). Shortly thereafter, the Danish Government asked the National Laboratory to empty the reactor and its storage pools containing a total of 255 DIDO irradiated elements and ship them to Savannah River Site in the USA as soon as possible. Risoe National Laboratory had previously contracted with Cogema Logistics to ship DR3 DIDO fuel elements to SRS through the end of the return program. The quantity of fuel was less than originally intended but the schedule was significantly shorter. It was agreed in June 2001 that a combination of Cogema Logistics' and NAC casks would be preferable, as it would allow Risoe to ship all the irradiated fuel in two shipments and complete the shipments by June 2002. Risoe National Laboratory, Cogema Logistics and NAC International had twelve months to perform the shipments including licensing, basket fabrication for the NAC-LWT casks and actual transport. The paper describes the challenging work that was accomplished to meet the date of June 2002. (author)

  3. Network Science Research Laboratory (NSRL) Telemetry Warehouse

    Science.gov (United States)

    2016-06-01

    Development of an architectural framework to validate performance of a distributed trust management protocol, called trustd, required a high...all of the most popular programming languages currently in use, including Java , Python, and C#. Work is underway to provide Python bindings to the...client library. NSRL researchers plan to develop Python and Java wrappers for this library. Sensors must obtain an experiment session token in

  4. Air Force Research Laboratory Technology Milestones 2007

    Science.gov (United States)

    2007-01-01

    alertness. For more information contact7 publicaffairs@afosraf.mil , (703)696-7797 ....... F d ed Researc ers Develop New Software Model to Improve Aircraft...and replacing conventional tail control surfaces with more innovative control U effectors. m For more information contact 22 afri. rb. marketing ...City, New Jersey). U For more information contact 23 ofr1.rb, marketing @wpafb.afmi1 (937)255-2074 AFRL Researchers Perform Functionally - Graded Material

  5. Fuels for research and test reactors, status review: July 1982

    International Nuclear Information System (INIS)

    Stahl, D.

    1982-12-01

    A thorough review is provided on nuclear fuels for steady-state thermal research and test reactors. The review was conducted to provide a documented data base in support of recent advances in research and test reactor fuel development, manufacture, and demonstration in response to current US policy on availability of enriched uranium. The review covers current fabrication practice, fabrication development efforts, irradiation performance, and properties affecting fuel utilization, including thermal conductivity, specific heat, density, thermal expansion, corrosion, phase stability, mechanical properties, and fission-product release. The emphasis is on US activities, but major work in Europe and elsewhere is included. The standard fuel types discussed are the U-Al alloy, UZrH/sub x/, and UO 2 rod fuels. Among new fuels, those given major emphasis include H 3 Si-Al dispersion and UO 2 caramel plate fuels

  6. Back-end of the research reactor fuel cycle

    International Nuclear Information System (INIS)

    Gruber, Gehard J.

    1996-01-01

    This paper outlines the status of topics and issues related to: (1) Research Reactor Spent Nuclear Fuel Return to the U.S., including policy, shipments and ports of entry, management sites, fees, storage technologies, contracts, actual shipment, and legal process, (2) UKAEA: MTR Spent Nuclear Fuel Reprocessing, (3) COGEMA: MTR Spent Nuclear Fuel Reprocessing, and (4) Intermediate Storage + Direct Disposal for Research Reactors. (author)

  7. Laboratory Directed Research and Development Program FY 2006 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    Sjoreen, Terrence P [ORNL

    2007-04-01

    The Oak Ridge National Laboratory (ORNL) Laboratory Directed Research and Development (LDRD) Program reports its status to the US Departmental of Energy (DOE) in March of each year. The program operates under the authority of DOE Order 413.2B, 'Laboratory Directed Research and Development' (April 19, 2006), which establishes DOE's requirements for the program while providing the Laboratory Director broad flexibility for program implementation. LDRD funds are obtained through a charge to all Laboratory programs. This report includes summaries all ORNL LDRD research activities supported during FY 2006. The associated FY 2006 ORNL LDRD Self-Assessment (ORNL/PPA-2007/2) provides financial data about the FY 2006 projects and an internal evaluation of the program's management process.

  8. Subcritical Noise Analysis Measurements with Fresh and Spent Research Reactor Fuels Elements

    International Nuclear Information System (INIS)

    Valentine, T.E.; Mihalczo, J.T.; Kryter, R.C.; Miller, V.C.

    1999-01-01

    The verification of the subcriticality is of utmost importance for the safe transportation and storage of nuclear reactor fuels. Transportation containers and storage facilities are designed such that nuclear fuels remain in a subcritical state. Such designs often involve excess conservatism because of the lack of relevant experimental data to verify the accuracy of Monte Carlo codes used in nuclear criticality safety analyses. A joint experimental research program between Oak Ridge National Laboratory, Westinghouse Safety Management Solutions, Inc., and the University of Missouri was initiated to obtain measured quantities that could be directly related to the subcriticality of simple arrays of Missouri University Research Reactor (MURR) fuel elements. A series of measurement were performed to assess the reactivity of materials such as BORAL, stainless steel, aluminum, and lead that are typically used in the construction of shipping casks. These materials were positioned between the fuel elements. In addition, a limited number of measurements were performed with configurations of fresh and spent (irradiated) fuel elements to ascertain the reactivity of the spent fuel elements. In these experiments, fresh fuel elements were replaced by spent fuel elements such that the subcritical reactivity change could be measured. The results of these measurements were used by Westinghouse Safety Management Solutions to determine the subcriticality of MURR fuel elements isolated by absorbing materials. The measurements were interpreted using the MCNP-DSP Monte Carlo code to obtain the subcritical neutron multiplication factor k(sub eff), and the bias in K(sub eff) that are used in criticality safety analyses

  9. Adverse reproduction outcomes among employees working in biomedical research laboratories

    DEFF Research Database (Denmark)

    Wennborg, H.; Bonde, Jens Peter; Stenbeck, M.

    2002-01-01

    Objectives The aim of the study was to investigate reproductive outcomes such as birthweight, preterm births, and postterm births among women working in research laboratories while pregnant. Methods Female university personnel were identified from a source cohort of Swedish laboratory employees...

  10. Laboratory Directed Research and Development Program Assessment for FY 2014

    Energy Technology Data Exchange (ETDEWEB)

    Hatton, D. [Brookhaven National Lab. (BNL), Upton, NY (United States)

    2014-03-01

    Each year, Brookhaven National Laboratory (BNL) is required to provide a program description and overview of its Laboratory Directed Research and Development Program (LDRD) to the Department of Energy in accordance with DOE Order 413.2B dated April 19, 2006. This report fulfills that requirement.

  11. Laboratory directed research and development program, FY 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-01

    The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab) Laboratory Directed Research and Development Program FY 1996 report is compiled from annual reports submitted by principal investigators following the close of the fiscal year. This report describes the projects supported and summarizes their accomplishments. It constitutes a part of the Laboratory Directed Research and Development (LDRD) program planning and documentation process that includes an annual planning cycle, projection selection, implementation, and review. The Berkeley Lab LDRD program is a critical tool for directing the Laboratory`s forefront scientific research capabilities toward vital, excellent, and emerging scientific challenges. The program provides the resources for Berkeley Lab scientists to make rapid and significant contributions to critical national science and technology problems. The LDRD program also advances the Laboratory`s core competencies, foundations, and scientific capability, and permits exploration of exciting new opportunities. Areas eligible for support include: (1) Work in forefront areas of science and technology that enrich Laboratory research and development capability; (2) Advanced study of new hypotheses, new experiments, and innovative approaches to develop new concepts or knowledge; (3) Experiments directed toward proof of principle for initial hypothesis testing or verification; and (4) Conception and preliminary technical analysis to explore possible instrumentation, experimental facilities, or new devices.

  12. New fuels for proliferation-safe research reactors. SCK-CEN a kingpin in international research

    International Nuclear Information System (INIS)

    Van den Berghe, S.

    2011-01-01

    A number of research reactors in the world, including BR2, are still working on highly enriched proliferation sensitive nuclear fuel. Extremely high-density fuel is required to make possible the switch to low-enriched fuel without loss of effectiveness. In the past few years, SCK-CEN has developed into the global test station for new, low-enriched fuels.

  13. Storage experience in Hungary with fuel from research reactors

    International Nuclear Information System (INIS)

    Gado, J.; Hargitai, T.

    1996-01-01

    In Hungary several critical assemblies, a training reactor and a research reactor have been in operation. The fuel used in the research and training reactors are of Soviet origin. Though spent fuel storage experience is fairly good, medium and long term storage solutions are needed. (author)

  14. Kinetic parameters of a material test research reactor fueled with various low enriched uranium dispersion fuels

    International Nuclear Information System (INIS)

    Muhammad, Farhan; Majid, Asad

    2009-01-01

    The effects of using different low enriched uranium fuels, having same uranium density, on the kinetic parameters of a material test research reactor were studied. For this purpose, the original aluminide fuel (UAl x -Al) containing 4.40 gU/cm 3 of an MTR was replaced with silicide (U 3 Si-Al and U 3 Si 2 -Al) and oxide (U 3 O 8 -Al) dispersion fuels having the same uranium density as of the original fuel. Simulations were carried out to calculate prompt neutron generation time, effective delayed-neutron fraction, core excess reactivity and neutron flux spectrum. Nuclear reactor analysis codes including WIMS-D4 and CITATION were used to carry out these calculations. It was observed that both the silicide fuels had the same prompt neutron generation time 0.02% more than that of the original aluminide fuel, while the oxide fuel had a prompt neutron generation time 0.05% less than that of the original aluminide fuel. The effective delayed-neutron fraction decreased for all the fuels; the decrease was maximum at 0.06% for U 3 Si 2 -Al followed by 0.03% for U 3 Si-Al, and 0.01% for U 3 O 8 -Al fuel. The U 3 O 8 -Al fueled reactor gave the maximum ρ excess at BOL which was 21.67% more than the original fuel followed by U 3 Si-Al which was 2.55% more, while that of U 3 Si 2 -Al was 2.50% more than the original UAl x -Al fuel. The neutron flux of all the fuels was more thermalized, than in the original fuel, in the active fuel region of the core. The thermalization was maximum for U 3 O 8 -Al followed by U 3 Si-Al and then U 3 Si 2 -Al fuel.

  15. Researches of WWER fuel rods behaviour under RIA accident conditions

    International Nuclear Information System (INIS)

    Nechaeva, O.; Medvedev, A.; Novikov, V.; Salatov, A.

    2003-01-01

    Unirradiated fuel rod and refabricated fuel rod tests in the BIGR as well as acceptance criteria proving absence of fragmentation and the settlement modeling of refabricated fuel rods thermomechanical behavior in the BIGR-tests using RAPTA-5 code are discussed in this paper. The behaviour of WWER type simulators with E110 and E635 cladding was researched at the BIGR reactor under power pulse conditions simulating reactivity initiated accident. The results of the tests in four variants of experimental conditions are submitted. The behaviour of 12 WWER type refabricated fuel rods was researched in the BIGR reactor under power pulse conditions simulating reactivity initiated accident: burnup 48 and 60 MWd/kgU, pulse width 3 ms, peak fuel enthalpy 115-190 cal/g. The program of future tests in the research reactor MIR with high burnup fuel rod (up to 70 MWd/kgU) under conditions simulating design RIA in WWER-1000 is presented

  16. 238Pu fuel form processes. Savannah River Laboratory monthly report

    International Nuclear Information System (INIS)

    1976-05-01

    Progress in the Savannah River 238 Pu fuel form program is summarized. Suspended solids observed in the technical-grade oxalic acid solution used in H-Area B-Line had no significant effect on particle size or morphology. A small but significant increase in product purity was noted with the use of reagent-grade oxalic acid. The density of hot-pressed LCHP pellets made from both problem and standardized feed decreased with longer milling times as was observed for multi-hundred watt (MHW) pellets. The LCHP pellets (greater than 90 percent theoretical density) generally cracked following final heat treatment. Cold-pressing studies indicate the anticipated pressure variation during cold pressing in the PuFF facility will have negligible effect on the density of MHW spheres. Construction of the plutonium experimental facility is 72 percent complete

  17. Radiotracer laboratory for agricultural research at the Malaysian Nuclear Agency

    International Nuclear Information System (INIS)

    Nashriyah Mat; Misman Sumin; Maizatul Akmam Mhd Nasir

    2007-01-01

    Radiotracer Laboratory for agricultural research at the Malaysian Nuclear Agency was established since 1990. It accommodates three laboratories, three chemical temporary storage compartments plus one compartment for storage of pressurized gas. This facility is situated in ground floor of Block 44, Agrotechnology and Biosciences Division, Dengkil Complex. Currently it houses a liquid scintillation counter, sample oxidizer, gas liquid chromatography, high performance liquid chromatography and auxiliary equipments. A road map for this laboratory will be discussed in relation with present scenario i.e. R and D service, training and consultancy provided by this laboratory; and future requirements and direction. (Author)

  18. Savannah River Laboratory environmental transport and effects research. Annual report, 1978

    Energy Technology Data Exchange (ETDEWEB)

    Crawford, T.V. (comp.)

    1979-11-01

    Research in the environmental sciences by the Savannah River Laboratory during 1978 is described in 43 articles. These articles are in the fields of terrestrial ecology, geologic studies, aquatic transport, aquatic ecology, atmospheric transport, emergency response, computer methods development, ocean program, and fuel cycle program. Thirty-seven of the articles were abstracted individually for ERA/EDB; those in scope were also included in INIS.

  19. Argonne National Laboratory research offers clues to Alzheimer's plaques

    CERN Multimedia

    2003-01-01

    Researchers from Argonne National Laboratory and the University of Chicago have developed methods to directly observe the structure and growth of microscopic filaments that form the characteristic plaques found in the brains of those with Alzheimer's Disease (1 page).

  20. Laboratory directed research and development 2006 annual report.

    Energy Technology Data Exchange (ETDEWEB)

    Westrich, Henry Roger

    2007-03-01

    This report summarizes progress from the Laboratory Directed Research and Development (LDRD) program during fiscal year 2006. In addition to a programmatic and financial overview, the report includes progress reports from 430 individual R&D projects in 17 categories.

  1. Global Impact | Frederick National Laboratory for Cancer Research

    Science.gov (United States)

    Through its direct support of clinical research, Frederick National Laboratory activities are not limited to national programs. The labis actively involved in more than 400 domestic and international studies related to cancer; influenza, HIV, E

  2. Earth System Research Laboratory Long-Term Surface Aerosol Measurements

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Aerosol measurements began at the NOAA Earth System Research Laboratory (ESRL) Global Monitoring Division (GMD) baseline observatories in the mid-1970's with the...

  3. Technical Service Agreement (TSA) | Frederick National Laboratory for Cancer Research

    Science.gov (United States)

    Frederick National Laboratory for Cancer Research (FNLCR) scientists provide services and solutions to collaborators through the Technical Services Program, whose portfolio includes more than 200 collaborations with more than 80 partners. The Frederi

  4. FTA fuel cell bus program : research accomplishments through 2011.

    Science.gov (United States)

    2012-03-01

    Prepared by the Federal Transit Administration (FTA) Office of Research, Demonstration, and Innovation (TRI), this report summarizes the accomplishments of fuel-cell-transit-bus-related research and demonstrations projects supported by FTA through 20...

  5. Electrocatalysis research for fuel cells and hydrogen production

    CSIR Research Space (South Africa)

    Mathe, MK

    2012-01-01

    Full Text Available The CSIR undertakes research in the Electrocatalysis of fuel cells and for hydrogen production. The Hydrogen South Africa (HySA) strategy supports research on electrocatalysts due to their importance to the national beneficiation strategy. The work...

  6. Laboratory Directed Research and Development Program

    International Nuclear Information System (INIS)

    Ogeka, G.J.; Romano, A.J.

    1992-12-01

    This report briefly discusses the following research: Advances in Geoexploration; Transvenous Coronary Angiography with Synchrotron X-Rays; Borehole Measurements of Global Warming; Molecular Ecology: Development of Field Methods for Microbial Growth Rate and Activity Measurements; A New Malaria Enzyme - A Potential Source for a New Diagnostic Test for Malaria and a Target for a New Antimalarial Drug; Basic Studies on Thoron and Thoron Precursors; Cloning of the cDNA for a Human Serine/Threonine Protein Kinase that is Activated Specifically by Double-Stranded DNA; Development of an Ultra-Fast Laser System for Accelerator Applications; Cluster Impact Fusion; Effect of a Bacterial Spore Protein on Mutagenesis; Structure and Function of Adenovirus Penton Base Protein; High Resolution Fast X-Ray Detector; Coherent Synchrotron Radiation Longitudinal Bunch Shape Monitor; High Grain Harmonic Generation Experiment; BNL Maglev Studies; Structural Investigations of Pt-Based Catalysts; Studies on the Cellular Toxicity of Cocaine and Cocaethylene; Human Melanocyte Transformation; Exploratory Applications of X-Ray Microscopy; Determination of the Higher Ordered Structure of Eukaryotic Chromosomes; Uranium Neutron Capture Therapy; Tunneling Microscopy Studies of Nanoscale Structures; Nuclear Techiques for Study of Biological Channels; RF Sources for Accelerator Physics; Induction and Repair of Double-Strand Breaks in the DNA of Human Lymphocytes; and An EBIS Source of High Charge State Ions up to Uranium

  7. Laboratory Directed Research and Development Program

    Energy Technology Data Exchange (ETDEWEB)

    Ogeka, G.J.; Romano, A.J.

    1992-12-01

    This report briefly discusses the following research: Advances in Geoexploration; Transvenous Coronary Angiography with Synchrotron X-Rays; Borehole Measurements of Global Warming; Molecular Ecology: Development of Field Methods for Microbial Growth Rate and Activity Measurements; A New Malaria Enzyme - A Potential Source for a New Diagnostic Test for Malaria and a Target for a New Antimalarial Drug; Basic Studies on Thoron and Thoron Precursors; Cloning of the cDNA for a Human Serine/Threonine Protein Kinase that is Activated Specifically by Double-Stranded DNA; Development of an Ultra-Fast Laser System for Accelerator Applications; Cluster Impact Fusion; Effect of a Bacterial Spore Protein on Mutagenesis; Structure and Function of Adenovirus Penton Base Protein; High Resolution Fast X-Ray Detector; Coherent Synchrotron Radiation Longitudinal Bunch Shape Monitor; High Grain Harmonic Generation Experiment; BNL Maglev Studies; Structural Investigations of Pt-Based Catalysts; Studies on the Cellular Toxicity of Cocaine and Cocaethylene; Human Melanocyte Transformation; Exploratory Applications of X-Ray Microscopy; Determination of the Higher Ordered Structure of Eukaryotic Chromosomes; Uranium Neutron Capture Therapy; Tunneling Microscopy Studies of Nanoscale Structures; Nuclear Techiques for Study of Biological Channels; RF Sources for Accelerator Physics; Induction and Repair of Double-Strand Breaks in the DNA of Human Lymphocytes; and An EBIS Source of High Charge State Ions up to Uranium.

  8. Research and Test Reactor Fuel Elements (RTRFE)

    International Nuclear Information System (INIS)

    Pace, Brett W.; Marinak, Edward A.

    1999-01-01

    BWX Technologies Inc. (BWXT) has experienced several production improvements over the past year. The homogeneity yields in 4.8 gU/cc U 3 Si 2 plates have increased over last year's already high yields. Through teamwork and innovative manufacturing techniques, maintaining high quality surface finishes on plates and elements is becoming easier and less expensive. Currently, BWXT is designing a fabrication development plan to reach a fuel loading of 9 gU/cc within 2 - 4 years. This development will involve a step approach requested by ANL to produce plates using U-8Mo at a loading of 6 gU/cc first and qualify the fuel at those levels. In achieving the goal of a very high-density fuel loading of 9 gU/cc, BWXT is considering employing several new, state of the art, ultrasonic testing techniques for fuel core evaluation. (author)

  9. Experimental research of fuel element reliability

    International Nuclear Information System (INIS)

    Cech, B.; Novak, J.; Chamrad, B.

    1980-01-01

    The rate and extent of the damage of the can integrity for fission products is the basic criterion of reliability. The extent of damage is measurable by the fission product leakage into the reactor coolant circuit. An analysis is made of the causes of the fuel element can damage and a model is proposed for testing fuel element reliability. Special experiments should be carried out to assess partial processes, such as heat transfer and fuel element surface temperature, fission gas liberation and pressure changes inside the element, corrosion weakening of the can wall, can deformation as a result of mechanical interactions. The irradiation probe for reliability testing of fuel elements is described. (M.S.)

  10. High Performance Fuel Laboratory, Hanford Reservation, Richland, Washington. Final environmental impact statement

    International Nuclear Information System (INIS)

    1977-09-01

    The High Performance Fuel Laboratory (HPFL) will provide pilot scale tests of manufacturing processes, equipment, and handling systems and of accountability and safeguards, methods, and equipment while keeping radiological and chemical exposures of the workers, public, and environment at the lowest practicable levels. The experience gained from designing, constructing and operating the HPFL can be used in future commitments to commercial fuel fabrication plants in the late 1980s and beyond for processing of nuclear fuel. The HPFL site is located in the 400 Area of the 559-square mile, federally owned Hanford Reservation. This environmental impact statement considers effects of the HPFL under normal conditions and in the event of an accident

  11. Laboratory Scale Coal And Biomass To Drop-In Fuels (CBDF) Production And Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Lux, Kenneth [Altex Technologies Corporation, Sunnyvale, CA (United States); Imam, Tahmina [Altex Technologies Corporation, Sunnyvale, CA (United States); Chevanan, Nehru [Altex Technologies Corporation, Sunnyvale, CA (United States); Namazian, Mehdi [Altex Technologies Corporation, Sunnyvale, CA (United States); Wang, Xiaoxing [Pennsylvania State Univ., University Park, PA (United States); Song, Chunshan [Pennsylvania State Univ., University Park, PA (United States)

    2016-06-29

    This Final Technical Report describes the work and accomplishments of the project entitled, “Laboratory Scale Coal and Biomass to Drop-In Fuels (CBDF) Production and Assessment.” The main objective of the project was to fabricate and test a lab-scale liquid-fuel production system using coal containing different percentages of biomass such as corn stover and switchgrass at a rate of 2 liters per day. The system utilizes the patented Altex fuel-production technology, which incorporates advanced catalysts developed by Pennsylvania State University. The system was designed, fabricated, tested, and assessed for economic and environmental feasibility relative to competing technologies.

  12. Space Station life science research facility - The vivarium/laboratory

    Science.gov (United States)

    Hilchey, J. D.; Arno, R. D.

    1985-01-01

    Research opportunities possible with the Space Station are discussed. The objective of the research program will be study gravity relationships for animal and plant species. The equipment necessary for space experiments including vivarium facilities are described. The cost of the development of research facilities such as the vivarium/laboratory and a bioresearch centrifuge is examined.

  13. Biological and Physical Space Research Laboratory 2002 Science Review

    Science.gov (United States)

    Curreri, P. A. (Editor); Robinson, M. B. (Editor); Murphy, K. L. (Editor)

    2003-01-01

    With the International Space Station Program approaching core complete, our NASA Headquarters sponsor, the new Code U Enterprise, Biological and Physical Research, is shifting its research emphasis from purely fundamental microgravity and biological sciences to strategic research aimed at enabling human missions beyond Earth orbit. Although we anticipate supporting microgravity research on the ISS for some time to come, our laboratory has been vigorously engaged in developing these new strategic research areas.This Technical Memorandum documents the internal science research at our laboratory as presented in a review to Dr. Ann Whitaker, MSFC Science Director, in July 2002. These presentations have been revised and updated as appropriate for this report. It provides a snapshot of the internal science capability of our laboratory as an aid to other NASA organizations and the external scientific community.

  14. 1995 Laboratory-Directed Research and Development Annual report

    Energy Technology Data Exchange (ETDEWEB)

    Cauffman, D.P.; Shoaf, D.L.; Hill, D.A.; Denison, A.B.

    1995-12-31

    The Laboratory-Directed Research and Development Program (LDRD) is a key component of the discretionary research conducted by Lockheed Idaho Technologies Company (Lockheed Idaho) at the Idaho National Engineering Laboratory (INEL). The threefold purpose and goal of the LDRD program is to maintain the scientific and technical vitality of the INEL, respond to and support new technical opportunities, and enhance the agility and flexibility of the national laboratory and Lockheed Idaho to address the current and future missions of the Department of Energy.

  15. 1995 Laboratory-Directed Research and Development Annual report

    International Nuclear Information System (INIS)

    Cauffman, D.P.; Shoaf, D.L.; Hill, D.A.; Denison, A.B.

    1995-01-01

    The Laboratory-Directed Research and Development Program (LDRD) is a key component of the discretionary research conducted by Lockheed Idaho Technologies Company (Lockheed Idaho) at the Idaho National Engineering Laboratory (INEL). The threefold purpose and goal of the LDRD program is to maintain the scientific and technical vitality of the INEL, respond to and support new technical opportunities, and enhance the agility and flexibility of the national laboratory and Lockheed Idaho to address the current and future missions of the Department of Energy

  16. Solid Oxide Fuel Cell Development at Topsoe Fuel Cell A/S and Risø National Laboratory

    DEFF Research Database (Denmark)

    Christiansen, Niels; Hansen, J B.; Larsen, H H.

    2007-01-01

    The consortium of Topsoe Fuel Cell A/S and Riso National Laboratory has up-scaled its production capacity of anode-supported cells to about 1100 per week. Stacks are based on a compact thin plate multilayer design with metallic interconnects and 12x12 cm(2) or 18x18 cm(2) foot print. Larger (500 ...... to include ethanol and coal syngas by development of a new coke resistant catalyst suitable for future SOFC technology....

  17. Corrosion of research reactor aluminium clad spent fuel in water. Additional information

    International Nuclear Information System (INIS)

    2009-12-01

    reactor aluminium clad spent fuel. These corrosion activities were quite similar to those carried out in the CRP. Eight Member States participated in Phase-II of the CRP and five Member States in the Regional Project RLA/4/018. Two of the countries participating in the regional project were also participants in the CRP. This report documents the work performed in the IAEA Coordinated Research Project (CRP) on Corrosion of Research Reactor Aluminium Clad Spent Fuel in Water (Phase II) and in the IAEA's Technical Cooperation Regional Project for Latin America (RLA/4/018) entitled Management of Spent Fuel from Research Reactors. The key activity of both, the CRP and the Regional Project, consisted of the exposure of standard racks of corrosion coupons in the spent fuel pools of the participating research reactor laboratories and the evaluation of the coupons after predetermined exposure times, along with periodic monitoring of the storage water and evaluation of sediments settling in the spent fuel pools. The report includes: a description of the standard corrosion racks, experimental protocols, test procedures and water quality monitoring; the specific contributions by each of the participating laboratories; a compilation of all experimental results obtained and the analysis and discussion of the results, along with conclusions

  18. Laboratory Directed Research and Development Program Assessment for FY 2008

    Energy Technology Data Exchange (ETDEWEB)

    Looney, J P; Fox, K J

    2008-03-31

    Brookhaven National Laboratory (BNL) is a multidisciplinary Laboratory that carries out basic and applied research in the physical, biomedical, and environmental sciences, and in selected energy technologies. It is managed by Brookhaven Science Associates, LLC, (BSA) under contract with the U. S. Department of Energy (DOE). BNL's Fiscal Year 2008 spending was $531.6 million. There are approximately 2,800 employees, and another 4,300 guest scientists and students who come each year to use the Laboratory's facilities and work with the staff. The BNL Laboratory Directed Research and Development (LDRD) Program reports its status to the U.S. Department of Energy (DOE) annually in March, as required by DOE Order 413.2B, 'Laboratory Directed Research and Development,' April 19, 2006, and the Roles, Responsibilities, and Guidelines for Laboratory Directed Research and Development at the Department of Energy/National Nuclear Security Administration Laboratories dated June 13, 2006. The goals and objectives of BNL's LDRD Program can be inferred from the Program's stated purposes. These are to (1) encourage and support the development of new ideas and technology, (2) promote the early exploration and exploitation of creative and innovative concepts, and (3) develop new 'fundable' R&D projects and programs. The emphasis is clearly articulated by BNL to be on supporting exploratory research 'which could lead to new programs, projects, and directions' for the Laboratory. To be a premier scientific Laboratory, BNL must continuously foster groundbreaking scientific research and renew its research agenda. The competition for LDRD funds stimulates Laboratory scientists to think in new and creative ways, which becomes a major factor in achieving and maintaining research excellence and a means to address National needs within the overall mission of the DOE and BNL. By fostering high-risk, exploratory research, the LDRD program helps

  19. The Johns Hopkins Hunterian Laboratory Philosophy: Mentoring Students in a Scientific Neurosurgical Research Laboratory.

    Science.gov (United States)

    Tyler, Betty M; Liu, Ann; Sankey, Eric W; Mangraviti, Antonella; Barone, Michael A; Brem, Henry

    2016-06-01

    After over 50 years of scientific contribution under the leadership of Harvey Cushing and later Walter Dandy, the Johns Hopkins Hunterian Laboratory entered a period of dormancy between the 1960s and early 1980s. In 1984, Henry Brem reinstituted the Hunterian Neurosurgical Laboratory, with a new focus on localized delivery of therapies for brain tumors, leading to several discoveries such as new antiangiogenic agents and Gliadel chemotherapy wafers for the treatment of malignant gliomas. Since that time, it has been the training ground for 310 trainees who have dedicated their time to scientific exploration in the lab, resulting in numerous discoveries in the area of neurosurgical research. The Hunterian Neurosurgical Laboratory has been a unique example of successful mentoring in a translational research environment. The laboratory's philosophy emphasizes mentorship, independence, self-directed learning, creativity, and people-centered collaboration, while maintaining productivity with a focus on improving clinical outcomes. This focus has been served by the diverse backgrounds of its trainees, both in regard to educational status as well as culturally. Through this philosophy and strong legacy of scientific contribution, the Hunterian Laboratory has maintained a positive and productive research environment that supports highly motivated students and trainees. In this article, the authors discuss the laboratory's training philosophy, linked to the principles of adult learning (andragogy), as well as the successes and the limitations of including a wide educational range of students in a neurosurgical translational laboratory and the phenomenon of combining clinical expertise with rigorous scientific training.

  20. Status of Research on Pebble Bed HTR Fuel Fabrication Technology in Indonesia

    International Nuclear Information System (INIS)

    Rachmawati, M.; Sarjono; Ridwan; Langenati, R.

    2014-01-01

    Research on pebble bed HTR fuel fabrication is conducted in Indonesia. One of the aims is to build a knowledge base on pebble bed HTR fuel element fabrication technology for fuel procurement. The steps of research strategies are firstly to understand the basic design research of TRISO fuel, properties, and requirements, and secondly to understand the TRISO fuel manufacturing technology, which comprises fabrication and quality control, including its facility. Both steps are adopted from research and experiences of the countries with HTR fuel element fabrication technology. From the knowledge gained in the research, an experimental design of the process and a set of prototype process equipment for fabrication are developed, namely kernels production using external gelation process, TRISO coating of the kernel, and pebble compacting. Experiments using the prototypes have been conducted. Characterization of the kernel product, i.e. diameter, sphericity, density and O/U ratio, shows that the kernel product is still not in compliance with the specification requirements. These are deemed to be caused mainly by the selected vibrating system and the viscosity adjustment. Another major cause is the selected NH3 and air feeding method for both NH3 and air layer in the preparation for spherical droplets of liquid. The FB-CVD TRISO coating of the kernel has been experimented but unsuccessful by using an FB-CVD once‐through continuous coating process. For the pebble compacting, the process is still in the early stage of setting-up compaction equipment. This paper summarizes the current status of research on HTR fuel fabrication technology in Indonesia, the proposed process and its equipment setting-up for improvement of the kernel production. The knowledge and lessons learned gained from the research is useful and can be an assistance in planning for fuel development laboratory facilities procurement, formulating User Requirement Document and Bid Invitation Specification for

  1. Pollution prevention for cleaner air: EPA's air and energy engineering research laboratory

    International Nuclear Information System (INIS)

    Shaver, E.M.

    1992-01-01

    The article discusses the role of EPA's Air and Energy Engineering Research Laboratory (AEERL) in pollution prevention research for cleaner air. For more than 20 years, AEERL has been conducting research to identify control approaches for the pollutants and sources which contribute to air quality problems. The Laboratory has successfully developed and demonstrated cost-effective sulfur dioxide, nitrogen oxides, and particulate control technologies for fossil fuel combustion sources. More recently, it has expanded its research activities to include indoor air quality, radon, organic control, stratospheric ozone depletion, and global warming. AEERL also develops inventories of air emissions of many types. Over the last several years, it has made substantial efforts to expand research on pollution prevention as the preferred choice for air emissions reduction

  2. Material test reactor fuel research at the BR2 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Dyck, Steven Van; Koonen, Edgar; Berghe, Sven van den [Institute for Nuclear Materials Science, SCK-CEN, Boeretang, Mol (Belgium)

    2012-03-15

    The construction of new, high performance material test reactor or the conversion of such reactors' core from high enriched uranium (HEU) to low enriched uranium (LEU) based fuel requires several fuel qualification steps. For the conversion of high performance reactors, high density dispersion or monolithic fuel types are being developed. The Uranium-Molybdenum fuel system has been selected as reference system for the qualification of LEU fuels. For reactors with lower performance characteristics, or as medium enriched fuel for high performance reactors, uranium silicide dispersion fuel is applied. However, on the longer term, the U-Mo based fuel types may offer a more efficient fuel alternative and-or an easier back-end solution with respect to the silicide based fuels. At the BR2 reactor of the Belgian nuclear research center, SCK-CEN in Mol, several types of fuel testing opportunities are present to contribute to such qualification process. A generic validation test for a selected fuel system is the irradiation of flat plates with representative dimensions for a fuel element. By flexible positioning and core loading, bounding irradiation conditions for fuel elements can be performed in a standard device in the BR2. For fuel element designs with curved plates, the element fabrication method compatibility of the fuel type can be addressed by incorporating a set of prototype fuel plates in a mixed driver fuel element of the BR2 reactor. These generic types of tests are performed directly in the primary coolant flow conditions of the BR2 reactor. The experiment control and interpretation is supported by detailed neutronic and thermal-hydraulic modeling of the experiments. Finally, the BR2 reactor offers the flexibility for irradiation of full size prototype fuel elements, as 200mm diameter irradiation channels are available. These channels allow the accommodation of various types of prototype fuel elements, eventually using a dedicated cooling loop to provide the

  3. Laboratory directed research and development annual report: Fiscal year 1992

    International Nuclear Information System (INIS)

    1993-01-01

    The Department of Energy Order DOE 5000.4A establishes DOE's policy and guidelines regarding Laboratory Directed Research and Development (LDRD) at its multiprogram laboratories. As described in 5000.4A, LDRD is ''research and development of a creative and innovative nature which is selected by the Laboratory Director or his or her designee, for the purpose of maintaining the scientific and technological vitality of the Laboratory and to respond to scientific and technological opportunities in conformance with the guidelines in this order. Consistent with the Mission Statement and Strategic Plan provided in PNL's Institutional Plan, the LDRD investments are focused on developing new and innovative approaches to research related to our ''core competencies.'' Currently, PNL's core competencies have been identified as: integrated environmental research; process science and engineering; energy distribution and utilization. In this report, the individual summaries of Laboratory-level LDRD projects are organized according to these corecompetencies. The largest proportion of Laboratory-level LDRD funds is allocated to the core competency of integrated environmental research. The projects described in this report represent PNL's investment in its future and are vital to maintaining the ability to develop creative solutions for the scientific and technical challenges faced by DOE and the nation. The report provides an overview of PNL's LDRD program and the management process used for the program and project summaries for each LDRD project

  4. Laboratory directed research and development annual report: Fiscal year 1992

    Energy Technology Data Exchange (ETDEWEB)

    1993-01-01

    The Department of Energy Order DOE 5000.4A establishes DOE`s policy and guidelines regarding Laboratory Directed Research and Development (LDRD) at its multiprogram laboratories. As described in 5000.4A, LDRD is ``research and development of a creative and innovative nature which is selected by the Laboratory Director or his or her designee, for the purpose of maintaining the scientific and technological vitality of the Laboratory and to respond to scientific and technological opportunities in conformance with the guidelines in this order. Consistent with the Mission Statement and Strategic Plan provided in PNL`s Institutional Plan, the LDRD investments are focused on developing new and innovative approaches to research related to our ``core competencies.`` Currently, PNL`s core competencies have been identified as: integrated environmental research; process science and engineering; energy distribution and utilization. In this report, the individual summaries of Laboratory-level LDRD projects are organized according to these corecompetencies. The largest proportion of Laboratory-level LDRD funds is allocated to the core competency of integrated environmental research. The projects described in this report represent PNL`s investment in its future and are vital to maintaining the ability to develop creative solutions for the scientific and technical challenges faced by DOE and the nation. The report provides an overview of PNL`s LDRD program and the management process used for the program and project summaries for each LDRD project.

  5. Laboratory directed research and development annual report: Fiscal year 1992

    Energy Technology Data Exchange (ETDEWEB)

    1993-01-01

    The Department of Energy Order DOE 5000.4A establishes DOE's policy and guidelines regarding Laboratory Directed Research and Development (LDRD) at its multiprogram laboratories. As described in 5000.4A, LDRD is research and development of a creative and innovative nature which is selected by the Laboratory Director or his or her designee, for the purpose of maintaining the scientific and technological vitality of the Laboratory and to respond to scientific and technological opportunities in conformance with the guidelines in this order. Consistent with the Mission Statement and Strategic Plan provided in PNL's Institutional Plan, the LDRD investments are focused on developing new and innovative approaches to research related to our core competencies.'' Currently, PNL's core competencies have been identified as: integrated environmental research; process science and engineering; energy distribution and utilization. In this report, the individual summaries of Laboratory-level LDRD projects are organized according to these corecompetencies. The largest proportion of Laboratory-level LDRD funds is allocated to the core competency of integrated environmental research. The projects described in this report represent PNL's investment in its future and are vital to maintaining the ability to develop creative solutions for the scientific and technical challenges faced by DOE and the nation. The report provides an overview of PNL's LDRD program and the management process used for the program and project summaries for each LDRD project.

  6. Cost aspects of the research reactor fuel cycle

    International Nuclear Information System (INIS)

    2010-01-01

    Research reactors have made valuable contributions to the development of nuclear power, basic science, materials development, radioisotope production for medicine and industry, and education and training. In doing so, they have provided an invaluable service to humanity. Research reactors are expected to make important contributions in the coming decades to further development of the peaceful uses of nuclear technology, in particular for advanced nuclear fission reactors and fuel cycles, fusion, high energy physics, basic research, materials science, nuclear medicine, and biological sciences. However, in the context of decreased public sector support, research reactors are increasingly faced with financial constraints. It is therefore of great importance that their operations are based on a sound understanding of the costs of the complete research reactor fuel cycle, and that they are managed according to sound financial and economic principles. This publication is targeted at individuals and organizations involved with research reactor operations, with the aim of providing both information and an analytical framework for assessing and determining the cost structure of fuel cycle related activities. Efficient management of fuel cycle expenditures is an important component in developing strategies for sustainable future operation of a research reactor. The elements of the fuel cycle are presented with a description of how they can affect the cost efficient operation of a research reactor. A systematic review of fuel cycle choices is particularly important when a new reactor is being planned or when an existing reactor is facing major changes in its fuel cycle structure, for example because of conversion of the core from high enriched uranium (HEU) to low enriched uranium (LEU) fuel, or the changes in spent fuel management provision. Review and optimization of fuel cycle issues is also recommended for existing research reactors, even in cases where research reactor

  7. 76 FR 19188 - Joint Biomedical Laboratory Research and Development and Clinical Science Research and...

    Science.gov (United States)

    2011-04-06

    ... DEPARTMENT OF VETERANS AFFAIRS Joint Biomedical Laboratory Research and Development and Clinical... the panels of the Joint Biomedical Laboratory Research and Development and Clinical Science Research.... Neurobiology-D June 10, 2011 Crowne Plaza DC/Silver Spring. Clinical Research Program June 13, 2011 VA Central...

  8. 78 FR 66992 - Joint Biomedical Laboratory Research and Development and Clinical Science Research and...

    Science.gov (United States)

    2013-11-07

    ... DEPARTMENT OF VETERANS AFFAIRS Joint Biomedical Laboratory Research and Development and Clinical... the panels of the Joint Biomedical Laboratory Research and Development and Clinical Science Research..., behavioral, and clinical science research. The panel meetings will be open to the public for approximately...

  9. 75 FR 57833 - Joint Biomedical Laboratory Research and Development and Clinical Science Research and...

    Science.gov (United States)

    2010-09-22

    ... DEPARTMENT OF VETERANS AFFAIRS Joint Biomedical Laboratory Research and Development and Clinical... the panels of the Joint Biomedical Laboratory Research and Development and Clinical Science Research... Crowne Plaza Clinical Research Program December 3, 2010 *VA Central Office Mental Hlth & Behav Sci-A...

  10. 78 FR 22622 - Joint Biomedical Laboratory Research and Development and Clinical Science Research and...

    Science.gov (United States)

    2013-04-16

    ... DEPARTMENT OF VETERANS AFFAIRS Joint Biomedical Laboratory Research and Development and Clinical... the panels of the Joint Biomedical Laboratory Research and Development and Clinical Science Research... biomedical, behavioral and clinical science research. The panel meetings will be open to the public for...

  11. 75 FR 23847 - Joint Biomedical Laboratory Research and Development and Clinical Science Research and...

    Science.gov (United States)

    2010-05-04

    ... DEPARTMENT OF VETERANS AFFAIRS Joint Biomedical Laboratory Research and Development and Clinical... panels of the Joint Biomedical Laboratory Research and Development and Clinical Science Research and... & Behav Sci-A June 7, 2010 L'Enfant Plaza Hotel. Clinical Research Program June 9, 2010 *VA Central Office...

  12. Research on burning of biomass fuels, KTH

    Energy Technology Data Exchange (ETDEWEB)

    Hagstroem, U.; Zoukatas, N.; Kutscher, E.; Megas, L.

    1983-05-01

    The three main principles of combustion, namely burning over the fuel bed, under the bed, and the inverted flame have been investigated. Combustion under the fuel bed rendered the lowest emission of carbon monoxide, hydrocarbons, benzopyrene, particulates and tar. Emission is also reduced by preheating the primary incoming air. Burning of pine gives variable emissions whereas birch tree and lying log gives satisfactory combustion. High flame intensity and Reynolds number of the flame zone in the interval 5 to 8 x 10/sup 3/ also give low emission. A conventional wood burner with its flame over the fuel bed and with a water cooled combustion chamber produces 100 times more carbon monoxide than an advanced construction.

  13. Growing dimensions. Spent fuel management at research reactors

    International Nuclear Information System (INIS)

    Ritchie, I.G.

    1998-01-01

    More than 550 nuclear research reactors are operating or shout down around the world. At many of these reactors, spent fuel from their operations is stored, pending decisions on its final disposition. In recent years, problems associated with this spent fuel storage have loomed larger in the international nuclear community. In efforts to determine the overall scope of problems and to develop a database on the subject, the IAEA has surveyed research reactor operators in its Member States. Information for the Research Reactor Spent Fuel Database (RRSFDB) so far has been obtained from a limited but representative number of research reactors. It supplements data already on hand in the Agency's more established Research Reactor Database (RRDB). Drawing upon these database resources, this article presents an overall picture of spent fuel management and storage at the world's research reactors, in the context of associated national and international programmes in the field

  14. Laboratory Directed Research and Development annual report, Fiscal year 1993

    International Nuclear Information System (INIS)

    1994-01-01

    The Department of Energy Order DOE 5000.4A establishes DOE's policy and guidelines regarding Laboratory Directed Research and Development (LDRD) at its multiprogram laboratories. As described in 5000.4A, LDRD is ''research and development of a creative and innovative nature which is selected by the Laboratory Director or his or her designee, for the purpose of maintaining the scientific and technological vitality of the Laboratory and to respond to scientific and technological opportunities in conformance with the guidelines in this Order. LDRD includes activities previously defined as ER ampersand D, as well as other discretionary research and development activities not provided for in a DOE program.'' Consistent with the Mission Statement and Strategic Plan provided in PNL's Institutional Plan, the LDRD investments are focused on developing new and innovative approaches in research related to our ''core competencies.'' Currently, PNL's core competencies have been identified as integrated environmental research; process technology; energy systems research. In this report, the individual summaries of Laboratory-level LDRD projects are organized according to these core competencies. The largest proportion of Laboratory-level LDRD funds is allocated to the core competency of integrated environmental research. A significant proportion of PNL's LDRD funds are also allocated to projects within the various research centers that are proposed by individual researchers or small research teams. The projects are described in Section 2.0. The projects described in this report represent PNL's investment in its future and are vital to maintaining the ability to develop creative solutions for the scientific and technical challenges faced by DOE and the nation. In accordance with DOE guidelines, the report provides an overview of PNL's LDRD program and the management process used for the program and project summaries for each LDRD project

  15. Laboratory Directed Research and Development annual report, Fiscal year 1993

    Energy Technology Data Exchange (ETDEWEB)

    1994-01-01

    The Department of Energy Order DOE 5000.4A establishes DOE`s policy and guidelines regarding Laboratory Directed Research and Development (LDRD) at its multiprogram laboratories. As described in 5000.4A, LDRD is ``research and development of a creative and innovative nature which is selected by the Laboratory Director or his or her designee, for the purpose of maintaining the scientific and technological vitality of the Laboratory and to respond to scientific and technological opportunities in conformance with the guidelines in this Order. LDRD includes activities previously defined as ER&D, as well as other discretionary research and development activities not provided for in a DOE program.`` Consistent with the Mission Statement and Strategic Plan provided in PNL`s Institutional Plan, the LDRD investments are focused on developing new and innovative approaches in research related to our ``core competencies.`` Currently, PNL`s core competencies have been identified as integrated environmental research; process technology; energy systems research. In this report, the individual summaries of Laboratory-level LDRD projects are organized according to these core competencies. The largest proportion of Laboratory-level LDRD funds is allocated to the core competency of integrated environmental research. A significant proportion of PNL`s LDRD funds are also allocated to projects within the various research centers that are proposed by individual researchers or small research teams. The projects are described in Section 2.0. The projects described in this report represent PNL`s investment in its future and are vital to maintaining the ability to develop creative solutions for the scientific and technical challenges faced by DOE and the nation. In accordance with DOE guidelines, the report provides an overview of PNL`s LDRD program and the management process used for the program and project summaries for each LDRD project.

  16. Results of fuel elements fabrication on the basis of increased concentration dioxide fuel for research reactors

    International Nuclear Information System (INIS)

    Alexandrov, A.B.; Afanasiev, V.L.; Enin, A.A.; Suprun, V.B.

    1996-01-01

    According to the Russian Reduced Enrichment for Research and Test Reactors (RERTR) program, that were constructed under the Russian projects, at the Novosibirsk Chemical Concentrates Plant the pilot series of different configuration (WR-M2, MR, IRT-4M) fuel elements, based on increased concentration uranium dioxide fuel, have been fabricated for reactor tests. Comprehensive fabricated fuel elements quality estimation has been carried out. (author)

  17. LABORATORY DIRECTED RESEARCH AND DEVELOPMENT PROGRAM ASSESSMENT FOR FY 2006.

    Energy Technology Data Exchange (ETDEWEB)

    FOX,K.J.

    2006-01-01

    Brookhaven National Laboratory (BNL) is a multidisciplinary laboratory that carries out basic and applied research in the physical, biomedical, and environmental sciences, and in selected energy technologies. It is managed by Brookhaven Science Associates, LLC, (BSA) under contract with the U. S. Department of Energy (DOE). BNL's total annual budget has averaged about $460 million. There are about 2,500 employees, and another 4,500 guest scientists and students who come each year to use the Laboratory's facilities and work with the staff. The BNL Laboratory Directed Research and Development (LDRD) Program reports its status to the U.S. Department of Energy (DOE) annually in March, as required by DOE Order 413.2B, ''Laboratory Directed Research and Development,'' April 19,2006, and the Roles, Responsibilities, and Guidelines for Laboratory Directed Research and Development at the Department of Energy National Nuclear Security Administration Laboratories dated June 13,2006. The goals and' objectives of BNL's LDRD Program can be inferred from the Program's stated purposes. These are to (1) encourage and support the development of new ideas and technology, (2) promote the early exploration and exploitation of creative and innovative concepts, and (3) develop new ''fundable'' R&D projects and programs. The emphasis is clearly articulated by BNL to be on supporting exploratory research ''which could lead to new programs, projects, and directions'' for the Laboratory. As one of the premier scientific laboratories of the DOE, BNL must continuously foster groundbreaking scientific research. At Brookhaven National Laboratory one such method is through its LDRD Program. This discretionary research and development tool is critical in maintaining the scientific excellence and long-term vitality of the Laboratory. Additionally, it is a means to stimulate the scientific community and foster new

  18. Laboratory Directed Research and Development Program Assessment for FY 2007

    Energy Technology Data Exchange (ETDEWEB)

    Newman,L.; Fox, K.J.

    2007-12-31

    Brookhaven National Laboratory (BNL) is a multidisciplinary laboratory that carries out basic and applied research in the physical, biomedical, and environmental sciences, and in selected energy technologies. It is managed by Brookhaven Science Associates, LLC, (BSA) under contract with the U. S. Department of Energy (DOE). BNL's Fiscal Year 2007 spending was $515 million. There are approximately 2,600 employees, and another 4,500 guest scientists and students who come each year to use the Laboratory's facilities and work with the staff. The BNL Laboratory Directed Research and Development (LDRD) Program reports its status to the U.S. Department of Energy (DOE) annually in March, as required by DOE Order 413.2B, 'Laboratory Directed Research and Development', April 19, 2006, and the Roles, Responsibilities, and Guidelines for Laboratory Directed Research and Development at the Department of Energy/National Nuclear Security Administration Laboratories dated June 13, 2006. The goals and objectives of BNL's LDRD Program can be inferred from the Program's stated purposes. These are to (1) encourage and support the development of new ideas and technology, (2) promote the early exploration and exploitation of creative and innovative concepts, and (3) develop new 'fundable' R&D projects and programs. The emphasis is clearly articulated by BNL to be on supporting exploratory research 'which could lead to new programs, projects, and directions' for the Laboratory. As one of the premier scientific laboratories of the DOE, BNL must continuously foster groundbreaking scientific research. At Brookhaven National Laboratory one such method is through its LDRD Program. This discretionary research and development tool is critical in maintaining the scientific excellence and long-term vitality of the Laboratory. Additionally, it is a means to stimulate the scientific community and foster new science and technology ideas, which

  19. National Renewable Energy Laboratory 2002 Research Review (Booklet)

    Energy Technology Data Exchange (ETDEWEB)

    Cook, G.; Epstein, K.; Brown, H.

    2002-07-01

    America is making a long transition to a future in which conventional, fossil fuel technologies will be displaced by new renewable energy and energy efficiency technologies. This first biannual research review describes NREL's R&D in seven technology areas--biorefineries, transportation, hydrogen, solar electricity, distributed energy, energy-efficient buildings, and low-wind-speed turbines.

  20. Laboratory technology research - abstracts of FY 1997 projects

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-11-01

    The Laboratory Technology Research (LTR) program supports high-risk, multidisciplinary research partnerships to investigate challenging scientific problems whose solutions have promising commercial potential. These partnerships capitalize on two great strengths of this country: the world-class basic research capability of the DOE Energy Research (ER) multi-program national laboratories and the unparalleled entrepreneurial spirit of American industry. A distinguishing feature of the ER multi-program national laboratories is their ability to integrate broad areas of science and engineering in support of national research and development goals. The LTR program leverages this strength for the Nation`s benefit by fostering partnerships with US industry. The partners jointly bring technology research to a point where industry or the Department`s technology development programs can pursue final development and commercialization. Projects supported by the LTR program are conducted by the five ER multi-program laboratories. These projects explore the applications of basic research advances relevant to DOE`s mission over a full range of scientific disciplines. The program presently emphasizes three critical areas of mission-related research: advanced materials; intelligent processing/manufacturing research; and sustainable environments.

  1. Tensions within an industrial research laboratory: the Philips laboratory's x-ray department between the wars

    NARCIS (Netherlands)

    Boersma, F.K.

    2003-01-01

    Tensions arose in the X-ray department of the Philips research laboratory during the interwar period, caused by the interplay among technological development, organizational culture, and individual behavior. This article traces the efforts of Philips researchers to find a balance between their

  2. Laboratory services series: the utilization of scientific glassblowing in a national research and development laboratory

    International Nuclear Information System (INIS)

    Farnham, R.M.; Poole, R.W.

    1976-04-01

    Glassblowing services at a national research and development laboratory provide unique equipment tailored for specific research efforts, small-scale process items for flowsheet demonstrations, and solutions for unusual technical problems such as glass-ceramic unions. Facilities, equipment, and personnel necessary for such services are described

  3. Developing and Implementing a Simple, Affordable Hydrogen Fuel Cell Laboratory in Introductory Chemistry

    Science.gov (United States)

    Klara, Kristina; Hou, Ning; Lawman, Allison; Wu, Liheng; Morrill, Drew; Tente, Alfred; Wang, Li-Qiong

    2014-01-01

    A simple, affordable hydrogen proton exchange membrane (PEM) fuel cell laboratory was developed through a collaborative effort between faculty and undergraduate students at Brown University. It has been incorporated into the introductory chemistry curriculum and successfully implemented in a class of over 500 students per academic year for over 3…

  4. Laboratory directed research and development program, FY 1996

    International Nuclear Information System (INIS)

    1997-02-01

    The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab) Laboratory Directed Research and Development Program FY 1996 report is compiled from annual reports submitted by principal investigators following the close of the fiscal year. This report describes the projects supported and summarizes their accomplishments. It constitutes a part of the Laboratory Directed Research and Development (LDRD) program planning and documentation process that includes an annual planning cycle, projection selection, implementation, and review. The Berkeley Lab LDRD program is a critical tool for directing the Laboratory's forefront scientific research capabilities toward vital, excellent, and emerging scientific challenges. The program provides the resources for Berkeley Lab scientists to make rapid and significant contributions to critical national science and technology problems. The LDRD program also advances the Laboratory's core competencies, foundations, and scientific capability, and permits exploration of exciting new opportunities. Areas eligible for support include: (1) Work in forefront areas of science and technology that enrich Laboratory research and development capability; (2) Advanced study of new hypotheses, new experiments, and innovative approaches to develop new concepts or knowledge; (3) Experiments directed toward proof of principle for initial hypothesis testing or verification; and (4) Conception and preliminary technical analysis to explore possible instrumentation, experimental facilities, or new devices

  5. Research and development of FBR fuel reprocessing in PNC

    International Nuclear Information System (INIS)

    Hoshino, T.

    1976-05-01

    The research program of the PNC for FBR fuel reprocessing in Japan is discussed. The general characteristics of FBR fuel reprocessing are pointed out and a comparison with LWR fuel is made. The R and D program is based on reprocessing using the aqueous Purex process. So far, some preliminary steps of the research program have been carried out, these include solvent extraction test, off-gas treatment test, voloxidation process study, solidification test of high-level liquid waste, and study of the dissolution behaviour of irradiated mixed oxide fuel. By the end of the 1980s, a pilot plant for FBR fuel reprocessing will be completed. For the design of the pilot plant, further research will be carried out in the following fields: head-end techniques; voloxidation process; dissolution and extraction techniques; waste treatment techniques. A time schedule for the different steps of the program is included

  6. Conversion of research reactors to low-enrichment uranium fuels

    International Nuclear Information System (INIS)

    Muranaka, R.G.

    1983-01-01

    There are at present approximately 350 research reactors in 52 countries ranging in power from less than 1 watt to 100 Megawatt and over. In the 1970's, many people became concerned about the possibility that some fuels and fuel cycles could provide an easy route to the acquisition of nuclear weapons. Since enrichment to less than 20% is internationally recognized as a fully adequate barrier to weapons usability, certain Member States have moved to minimize the international trade in highly enriched uranium and have established programmes to develop the technical means to help convert research reactors to the use of low-enrichment fuels with minimum penalties. This could involve modifications in the design of the reactor and development of new fuels. As a result of these programmes, it is expected that most research reactors can be converted to the use of low-enriched fuel

  7. Annual report of Nuclear Engineering Research Laboratory, University of Tokyo in fiscal 1991

    International Nuclear Information System (INIS)

    1992-07-01

    In this annual report, the activities of education and research, the state of operation of research facilities and others in Nuclear Engineering Research Laboratory, University of Tokyo in fiscal year 1991 are summarized. In this Laboratory, there are four large research facilities, that is, the fast neutron source reactor 'Yayoi', the electron beam linac, the nuclear fusion reactor blanket experiment facility and the heavy irradiation research facility. Those are used for carrying out education and research in the wide fields of nuclear engineering, and are offered also for joint utilization. The results of the research by using respective research facilities were summarized in separate reports. In this annual report, the course of the management and operation of respective research facilities is described, and the research activities, the theses for doctorate and graduation theses of the teachers, personnel and graduate students in the Laboratory are summarized. In the research, those on first wall engineering for fusion reactors, fuel cycle engineering, electromagnetic structure engineering, AI and robotics, quantum beam engineering, new type reactor design and so on are included. (K.I.)

  8. Development of a new bench for puncturing of irradiated fuel rods in STAR hot laboratory

    Science.gov (United States)

    Petitprez, B.; Silvestre, P.; Valenza, P.; Boulore, A.; David, T.

    2018-01-01

    A new device for puncturing of irradiated fuel rods in commercial power plants has been designed by Fuel Research Department of CEA Cadarache in order to provide experimental data of high precision on fuel pins with various designs. It will replace the current set-up that has been used since 1998 in hot cell 2 of STAR facility with more than 200 rod puncturing experiments. Based on this consistent experimental feedback, the heavy-duty technique of rod perforation by clad punching has been preserved for the new bench. The method of double expansion of rod gases is also retained since it allows upgrading the confidence interval of volumetric results obtained from rod puncturing. Furthermore, many evolutions have been introduced in the new design in order to improve its reliability, to make the maintenance easier by remote handling and to reduce experimental uncertainties. Tightness components have been studied with Sealing Laboratory Maestral at Pierrelatte so as to make them able to work under mixed pressure conditions (from vacuum at 10-5 mbar up to pressure at 50 bars) and to lengthen their lifetime under permanent gamma irradiation in hot cell. Bench ergonomics has been optimized to make its operating by remote handling easier and to secure the critical phases of a puncturing experiment. A high pressure gas line equipped with high precision pressure sensors out of cell can be connected to the bench in cell for calibration purposes. Uncertainty analyses using Monte Carlo calculations have been performed in order to optimize capacity of the different volumes of the apparatus according to volumetric characteristics of the rod to be punctured. At last this device is composed of independent modules which allow puncturing fuel pins out of different geometries (PWR, BWR, VVER). After leak tests of the device and remote handling simulation in a mock-up cell, several punctures of calibrated specimens have been performed in 2016. The bench will be implemented soon in hot

  9. Management and storage of nuclear fuel from Belgian research reactors

    International Nuclear Information System (INIS)

    Gubel, P.

    1996-01-01

    Experiences and problems with the storage of irradiated fuel at research reactors in Belgium are described. In particular, interim storage problems exist for spent fuel elements at the BR2 and the shut down BR3 reactors in Mol. (author). 1 ref

  10. Research reactor fuel transport in the U.K

    Energy Technology Data Exchange (ETDEWEB)

    Panter, R [U.K. Atomic Energy Authority, Harwell (United Kingdom)

    1983-09-01

    This paper describes the containers currently used for transport of fresh or spent fuel elements for Research and Materials Test Reactors in the U.K., their status, operating procedures and some of the practical difficulties. In the U.K., MTR fuel cycle work is almost entirely the responsibility of the U.K. Atomic Energy Authority.

  11. CNG INJECTOR RESEARCH FOR DUAL FUEL ENGINE

    Directory of Open Access Journals (Sweden)

    Adam Majczak

    2017-03-01

    Full Text Available The article presents the tests results of the prototype design of hydraulically assisted injector, that is designed for gas supply into diesel engines. The construction of the injector allows for it positioning in the glow plug socket, so that the gas is injected directly into the combustion chamber. The cycle analysis of the four-cylinder Andoria ADCR engine with a capacity of 2.6 dm3 for different crankshaft rotational speeds allowed to determine the necessary time for fuel injection. Because of that, it was possible to determine the required mass flow rate of the injector, for replacing as much of the original fuel by gaseous fuel. To ensure a high value of flow inside the injector, supply pressure equal to 1 MPa was applied. High gas supply pressure requires high value of valve opening forces. For this purpose a injector with hydraulic control system, using a liquid under pressure for the opening process was designed. On the basis of air pressure measurements in the flow line after the injector, the analysis of opening and closing of the valve was made. Measurements of outflow mass of the injector were also carried out. The results showed that the designed injector meets the requirements necessary to supply ADCR engine by the CNG fuel.

  12. Biorefinery and Hydrogen Fuel Cell Research

    Energy Technology Data Exchange (ETDEWEB)

    K.C. Das; Thomas T. Adams; Mark A. Eiteman; John Stickney; Joy Doran Peterson; James R. Kastner; Sudhagar Mani; Ryan Adolphson

    2012-06-12

    In this project we focused on several aspects of technology development that advances the formation of an integrated biorefinery. These focus areas include: [1] establishment of pyrolysis processing systems and characterization of the product oils for fuel applications, including engine testing of a preferred product and its pro forma economic analysis; [2] extraction of sugars through a novel hotwater extaction process, and the development of levoglucosan (a pyrolysis BioOil intermediate); [3] identification and testing of the use of biochar, the coproduct from pyrolysis, for soil applications; [4] developments in methods of atomic layer epitaxy (for efficient development of coatings as in fuel cells); [5] advancement in fermentation of lignocellulosics, [6] development of algal biomass as a potential substrate for the biorefinery, and [7] development of catalysts from coproducts. These advancements are intended to provide a diverse set of product choices within the biorefinery, thus improving the cost effectiveness of the system. Technical effectiveness was demonstrated in the pyrolysis biooil based diesel fuel supplement, sugar extraction from lignocelluose, use of biochar, production of algal biomass in wastewaters, and the development of catalysts. Economic feasibility of algal biomass production systems seems attractive, relative to the other options. However, further optimization in all paths, and testing/demonstration at larger scales are required to fully understand the economic viabilities. The various coproducts provide a clear picture that multiple streams of value can be generated within an integrated biorefinery, and these include fuels and products.

  13. GaInSn usage in the research laboratory

    International Nuclear Information System (INIS)

    Morley, N. B.; Burris, J.; Cadwallader, L. C.; Nornberg, M. D.

    2008-01-01

    GaInSn, a eutectic alloy, has been successfully used in the Magneto-Thermofluid Research Laboratory at the University of California-Los Angeles and at the Princeton Plasma Physics Laboratory for the past six years. This paper describes the handling and safety of GaInSn based on the experience gained in these institutions, augmented by observations from other researchers in the liquid metal experimental community. GaInSn is an alloy with benign properties and shows considerable potential in liquid metal experimental research and cooling applications

  14. Use of Laboratory Animals in Biomedical and Behavioral Research

    National Research Council Canada - National Science Library

    1988-01-01

    ... of Laboratory Animals in Biomedical and Behavioral Research Commission on Life Sciences National Research Council Institute of Medicine NATIONAL ACADEMY PRESS Washington, D.C. 1988 Copyrightoriginal retained, the be not from cannot book, paper original however, for version formatting, authoritative the typesetting-specific created from the as publ...

  15. Quality assurance in a large research and development laboratory

    International Nuclear Information System (INIS)

    Neill, F.H.

    1980-01-01

    Developing a quality assurance program for a large research and development laboratory provided a unique opportunity for innovative planning. The quality assurance program that emerged has been tailored to meet the requirements of several sponsoring organizations and contains the flexibility for experimental programs ranging from large engineering-scale development projects to bench-scale basic research programs

  16. Integrating Interdisciplinary Research-Based Experiences in Biotechnology Laboratories

    Science.gov (United States)

    Iyer, Rupa S.; Wales, Melinda E.

    2012-01-01

    The increasingly interdisciplinary nature of today's scientific research is leading to the transformation of undergraduate education. In addressing these needs, the University of Houston's College of Technology has developed a new interdisciplinary research-based biotechnology laboratory curriculum. Using the pesticide degrading bacterium,…

  17. Laboratory directed research and development. FY 1995 progress report

    Energy Technology Data Exchange (ETDEWEB)

    Vigil, J.; Prono, J. [comps.

    1996-03-01

    This document presents an overview of Laboratory Directed Research and Development Programs at Los Alamos. The nine technical disciplines in which research is described include materials, engineering and base technologies, plasma, fluids, and particle beams, chemistry, mathematics and computational science, atmic and molecular physics, geoscience, space science, and astrophysics, nuclear and particle physics, and biosciences. Brief descriptions are provided in the above programs.

  18. Field Research Studying Whales in an Undergraduate Animal Behavior Laboratory

    Science.gov (United States)

    MacLaren, R. David; Schulte, Dianna; Kennedy, Jen

    2012-01-01

    This work describes a new field research laboratory in an undergraduate animal behavior course involving the study of whale behavior, ecology and conservation in partnership with a non-profit research organization--the Blue Ocean Society for Marine Conservation (BOS). The project involves two weeks of training and five weekend trips on whale watch…

  19. Application of ac impedance in fuel cell research and development

    Energy Technology Data Exchange (ETDEWEB)

    Selman, J R; Lin, Y P [Illinois Inst. of Tech., Chicago, IL (United States). Dept. of Chemical Engineering

    1993-10-01

    In applying ac impedance to fuel cells and their porous (gas diffusion) electrodes the emphasis lies on different fuel cell components, and their properties, according to the fuel cell type. The focus has been directed at the electrode/electrolyte interface in MCFC and PAFC, whereas in SOFC and PEMFC the ionic/electronic conductivity of the electrolyte or the characteristics of its composite with the electrocatalyst is of primary interest. The limitations of ac impedance in fuel cell application are in part due to difficulties of interpretation and in part due to experimental difficulties because of the generally fast electrode reaction kinetics. Further research directions are indicated. (author)

  20. Laboratory technology research: Abstracts of FY 1998 projects

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-11-01

    The Laboratory Technology Research (LTR) program supports high-risk, multidisciplinary research partnerships to investigate challenging scientific problems whose solutions have promising commercial potential. These partnerships capitalize on two great strengths of the country: the world-class basic research capability of the DOE Office of Science (SC) national laboratories and the unparalleled entrepreneurial spirit of American industry. Projects supported by the LTR program in FY 1998 explore the applications of basic research advances relevant to DOE`s mission over a full range of scientific disciplines. The program presently emphasizes three critical areas of mission-related research: advanced materials, intelligent processing and manufacturing research, and environmental and biomedical research. Abstracts for 85 projects are contained in this report.

  1. Current safety practices in nano-research laboratories in China.

    Science.gov (United States)

    Zhang, Can; Zhang, Jing; Wang, Guoyu

    2014-06-01

    China has become a key player in the global nanotechnology field, however, no surveys have specifically examined safety practices in the Chinese nano-laboratories in depth. This study reports results of a survey of 300 professionals who work in research laboratories that handle nanomaterials in China. We recruited participants at three major nano-research laboratories (which carry out research in diverse fields such as chemistry, material science, and biology) and the nano-chemistry session of the national meeting of the Chinese Chemical Society. Results show that almost all nano-research laboratories surveyed had general safety regulations, whereas less than one third of respondents reported having nanospecific safety rules. General safety measures were in place in most surveyed nano-research laboratories, while nanospecific protective measures existed or were implemented less frequently. Several factors reported from the scientific literature including nanotoxicology knowledge gaps, technical limitations on estimating nano-exposure, and the lack of nano-occupational safety legislation may contribute to the current state of affairs. With these factors in mind and embracing the precautionary principle, we suggest strengthening or providing nanosafety training (including raising risk awareness) and establishing nanosafety guidelines in China, to better protect personnel in the nano-workplace.

  2. 77 FR 26069 - Joint Biomedical Laboratory Research and Development and Clinical Science Research and...

    Science.gov (United States)

    2012-05-02

    ... DEPARTMENT OF VETERANS AFFAIRS Joint Biomedical Laboratory Research and Development and Clinical Science Research and Development Services Scientific Merit Review Board, Notice of Meeting Amendment The... Development and Clinical Science Research and Development Services Scientific Merit Review Board have changed...

  3. Thermal fuel research and development facilities in BNFL

    International Nuclear Information System (INIS)

    Roberts, V.A.; Vickers, J.

    1996-01-01

    BNFL is committed to providing high quality, cost effective nuclear fuel cycle services to customers on a National and International level. BNFL's services, products and expertise span the complete fuel cycle; from fuel manufacture through to fuel reprocessing, transport, waste management and decommissioning and the Company maintains its technical and commercial lead by investment in continued research and development (R and D). This paper discusses BNFL's involvement in R and D and gives an account of the current facilities available together with a description of the advanced R and D facilities constructed or planned at Springfields and Sellafield. It outlines the work being carried out to support the company fuel technology business, to (1) develop more cost effective routes to existing fuel products; (2) maximize the use of recycled uranium, plutonium and tails uranium and (3) support a successful MOX business

  4. Used fuel disposition research and development roadmap - FY10 status.

    Energy Technology Data Exchange (ETDEWEB)

    Nutt, W. M. (Nuclear Engineering Division)

    2010-10-01

    Since 1987 the U.S. has focused research and development activities relevant to the disposal of commercial used nuclear fuel and U.S. Department of Energy (DOE) owned spent nuclear fuel and high level waste on the proposed repository at Yucca Mountain, Nevada. At the same time, the U.S. successfully deployed a deep geologic disposal facility for defense-related transuranic waste in bedded salt at the Waste Isolation Pilot Plant. In 2009 the DOE established the Used Fuel Disposition Campaign (UFDC) within the Office of Nuclear Energy. The Mission of the UFDC is to identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. national laboratories have participated on these programs and has conducted research and development related to these issues to a limited extent. However, a comprehensive research and development (R&D) program investigating a variety of geologic media has not been a part of the U.S. waste management program since the mid 1980s. Such a comprehensive R&D program is being developed in the UFDC with a goal of meeting the UFDC Grand Challenge to provide a sound technical basis for absolute confidence in the safety and security of long-term storage, transportation, and disposal of used nuclear fuel and wastes from the nuclear energy enterprise. The DOE has decided to no longer pursue the development of a repository at Yucca Mountain, Nevada. Since a repository site will ultimately have to be selected, sited, characterized, designed, and licensed, other disposal options must now be considered. In addition to the unsaturated volcanic tuff evaluated at Yucca Mountain, several different geologic media are under investigation internationally and preliminary assessments indicate that disposal of used nuclear fuel and high level waste in these media is feasible. Considerable progress has been made in

  5. Used fuel disposition research and development roadmap - FY10 status

    International Nuclear Information System (INIS)

    Nutt, W.M.

    2010-01-01

    Since 1987 the U.S. has focused research and development activities relevant to the disposal of commercial used nuclear fuel and U.S. Department of Energy (DOE) owned spent nuclear fuel and high level waste on the proposed repository at Yucca Mountain, Nevada. At the same time, the U.S. successfully deployed a deep geologic disposal facility for defense-related transuranic waste in bedded salt at the Waste Isolation Pilot Plant. In 2009 the DOE established the Used Fuel Disposition Campaign (UFDC) within the Office of Nuclear Energy. The Mission of the UFDC is to identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. national laboratories have participated on these programs and has conducted research and development related to these issues to a limited extent. However, a comprehensive research and development (R and D) program investigating a variety of geologic media has not been a part of the U.S. waste management program since the mid 1980s. Such a comprehensive R and D program is being developed in the UFDC with a goal of meeting the UFDC Grand Challenge to provide a sound technical basis for absolute confidence in the safety and security of long-term storage, transportation, and disposal of used nuclear fuel and wastes from the nuclear energy enterprise. The DOE has decided to no longer pursue the development of a repository at Yucca Mountain, Nevada. Since a repository site will ultimately have to be selected, sited, characterized, designed, and licensed, other disposal options must now be considered. In addition to the unsaturated volcanic tuff evaluated at Yucca Mountain, several different geologic media are under investigation internationally and preliminary assessments indicate that disposal of used nuclear fuel and high level waste in these media is feasible. Considerable progress has been

  6. Annual report of Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo, fiscal year 1995

    International Nuclear Information System (INIS)

    1996-08-01

    This is an annual report prepared on research education action, operation state of research instruments and others in FY 1995 at Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo. The laboratory has four large instruments such as high speed neutron source reactor, 'Yayoi', electron linac, fundamentally experimental equipment for blanket design of nuclear fusion reactor, and heavy radiation research equipment (HIT), of which former two are used for cooperative research with universities in Japan, and the next blanket and the last HIT are also presented for cooperative researches in Faculty of Engineering and in University of Tokyo, respectively. FY 1995 was the beginning year of earnest discussion on future planning of this facility with concentrated effort. These four large research instruments are all in their active use. And, their further improvement is under preparation. In this report, the progress in FY 1995 on operation and management of the four large instruments are described at first, and on next, research actions, contents of theses for degree and graduation of students as well as research results of laboratory stuffs are summarized. These researches are constituted mainly using these large instruments in the facility, aiming at development of advanced and new field of atomic energy engineering and relates to nuclear reactor first wall engineering, nuclear reactor fuel cycle engineering, electromagnetic structure engineering, thermal-liquid engineering, mathematical information engineering, quantum beam engineering, new type reactor design and so on. (G.K.)

  7. Annual report of Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo, fiscal year 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-01

    This is an annual report prepared on research education action, operation state of research instruments and others in FY 1995 at Nuclear Engineering Research Laboratory, Faculty of Engineering, University of Tokyo. The laboratory has four large instruments such as high speed neutron source reactor, `Yayoi`, electron linac, fundamentally experimental equipment for blanket design of nuclear fusion reactor, and heavy radiation research equipment (HIT), of which former two are used for cooperative research with universities in Japan, and the next blanket and the last HIT are also presented for cooperative researches in Faculty of Engineering and in University of Tokyo, respectively. FY 1995 was the beginning year of earnest discussion on future planning of this facility with concentrated effort. These four large research instruments are all in their active use. And, their further improvement is under preparation. In this report, the progress in FY 1995 on operation and management of the four large instruments are described at first, and on next, research actions, contents of theses for degree and graduation of students as well as research results of laboratory stuffs are summarized. These researches are constituted mainly using these large instruments in the facility, aiming at development of advanced and new field of atomic energy engineering and relates to nuclear reactor first wall engineering, nuclear reactor fuel cycle engineering, electromagnetic structure engineering, thermal-liquid engineering, mathematical information engineering, quantum beam engineering, new type reactor design and so on. (G.K.)

  8. A laboratory-scale comparison of rate of spread model predictions using chaparral fuel beds – preliminary results

    Science.gov (United States)

    D.R. Weise; E. Koo; X. Zhou; S. Mahalingam

    2011-01-01

    Observed fire spread rates from 240 laboratory fires in horizontally-oriented single-species live fuel beds were compared to predictions from various implementations and modifications of the Rothermel rate of spread model and a physical fire spread model developed by Pagni and Koo. Packing ratio of the laboratory fuel beds was generally greater than that observed in...

  9. Reactivity feedbacks of a material test research reactor fueled with various low enriched uranium dispersion fuels

    International Nuclear Information System (INIS)

    Muhammad, Farhan; Majid, Asad

    2009-01-01

    The reactivity feedbacks of a material test research reactor using various low enriched uranium fuels, having same uranium density were calculated. For this purpose, the original aluminide fuel (UAl x -Al) containing 4.40 gU/cm 3 of an MTR was replaced with silicide (U 3 Si-Al and U 3 Si 2 -Al) and oxide (U 3 O 8 -Al) dispersion fuels having the same uranium density as of the original fuel. Calculations were carried out to find the fuel temperature reactivity feedback, moderator temperature reactivity feedback, moderator density reactivity feedback and moderator void reactivity feedback. Nuclear reactor analysis codes including WIMS-D4 and CITATION were employed to carry out these calculations. It was observed that the magnitudes all the respective reactivity feedbacks from 38 deg. C to 50 deg. C and 100 deg. C, at the beginning of life, of all the fuels were very close to each other. The fuel temperature reactivity feedback of the U 3 O 8 -Al was about 2% more than the original UAl x -Al fuel. The magnitudes of the moderator temperature, moderator density and moderator void reactivity feedbacks of all the fuels, showed very minor variations from the original aluminide fuel.

  10. Situation of test and research reactors' spent fuels

    International Nuclear Information System (INIS)

    Shimizu, Kenichi; Uchiyama, Junzo; Sato, Hiroshi

    1996-01-01

    The U.S. DOE decided a renewal Off-Site Fuel Policy for stopping to spread a highly enriched uranium which was originally enriched at the U.S., the policy declared that to receive all HEU spent fuels from Test and Research reactors in all the world. In Japan, under bilateral agreement of cooperation between the government of the United States and the government of Japan concerning peaceful uses of nuclear energy, the highly enriched uranium of Test and Research Reactors' fuels was purchased from the U.S. and the fuels had been manufactured in Japan, America, Germany and France. On the other hand, a former president of the U.S. J. Carter proposed that to convert the fuels from HEU to LEU concerning a nonproliferation of nuclear materials in 1978, and Japan absolutely supported this policy. Under this condition, the U.S. stopped to receive the spent fuels from the other countries concerning legal action to the Off-Site Fuels Policy. As a result, the spent fuels are increasing, and to cross to each reactor's storage capacity, and if this policy start, a faced crisis of Test and Research Reactors will be avoided. (author)

  11. Fuel Cell Demonstration Project - 200 kW - Phosphoric Acid Fuel Cell Power Plant Located at the National Transportation Research Center: FINAL REPORT

    Energy Technology Data Exchange (ETDEWEB)

    Berry, JB

    2005-05-06

    Oak Ridge National Laboratory (ORNL) researches and develops distributed generation technology for the Department of Energy, Energy Efficiency and Renewable Energy Distributed Energy Program. This report describes installation and operation of one such distributed generation system, a United Technology Corporation fuel cell located at the National Transportation Research Center in Knoxville, Tennessee. Data collected from June 2003 to June of 2004, provides valuable insight regarding fuel cell-grid compatibility and the cost-benefit of the fuel cell operation. The NTRC fuel cell included a high-heat recovery option so that use of thermal energy improves project economics and improves system efficiency to 59% year round. During the year the fuel cell supplied a total of 834MWh to the NTRC and provided 300MBtu of hot water. Installation of the NTRC fuel cell was funded by the Distributed Energy Program with partial funding from the Department of Defense's Climate Change Fuel Cell Buy Down Program, administered by the National Energy Technology Laboratory. On-going operational expenses are funded by ORNL's utility budget and are paid from operational cost savings. Technical information and the benefit-cost of the fuel cell are both evaluated in this report and sister reports.

  12. 77 FR 64598 - Joint Biomedical Laboratory Research and Development and Clinical Science Research and...

    Science.gov (United States)

    2012-10-22

    ... DEPARTMENT OF VETERANS AFFAIRS Joint Biomedical Laboratory Research and Development and Clinical...) that the panels of the Joint Biomedical Laboratory Research and Development and Clinical Science... areas of biomedical, behavioral and clinical science research. The panel meetings will be open to the...

  13. A Research-Based Laboratory Course Designed to Strengthen the Research-Teaching Nexus

    Science.gov (United States)

    Parra, Karlett J.; Osgood, Marcy P.; Pappas, Donald L., Jr.

    2010-01-01

    We describe a 10-week laboratory course of guided research experiments thematically linked by topic, which had an ultimate goal of strengthening the undergraduate research-teaching nexus. This undergraduate laboratory course is a direct extension of faculty research interests. From DNA isolation, characterization, and mutagenesis, to protein…

  14. Engineered safeguards system activities at Sandia Laboratories for back-end fuel cycle facilities

    International Nuclear Information System (INIS)

    Sellers, T.A.; Fienning, W.C.; Winblad, A.E.

    1978-01-01

    Sandia Laboratories have been developing concepts for safeguards systems to protect facilities in the back-end of the nuclear fuel cycle against potential threats of sabotage and theft of special nuclear material (SNM). Conceptual designs for Engineered Safeguards Systems (ESSs) have been developed for a Fuel Reprocessing Facility (including chemical separations, plutonium conversion, and waste solidification), a Mixed-Oxide Fuel Fabrication Facility, and a Plutonium Transport Vehicle. Performance criteria for the various elements of these systems and a candidate systematic design approach have been defined. In addition, a conceptual layout for a large-scale Fuel-Cycle Plutonium Storage Facility has been completed. Work is continuing to develop safeguards systems for spent fuel facilities, light-water reactors, alternative fuel cycles, and improved transportation systems. Additional emphasis will be placed on the problems associated with national diversion of special nuclear material. The impact on safeguards element performance criteria for surveillance and containment to protect against national diversion in various alternative fuel cycle complexes is also being investigated

  15. Research Establishment progress report 1978 - uranium fuel cycle

    International Nuclear Information System (INIS)

    1978-12-01

    A report of research programs continuing in the following areas is presented: mining and treatment of uranium ores, uranium enrichment, waste treatment, reprocessing and the uranium fuel cycle. Staff responsible for each project are indicated

  16. Research Collaborations Between Universities and Department of Defense Laboratories

    Science.gov (United States)

    2014-07-31

    Council – Resident Research Associateship (USAF/NRC-RRA) Program,” last accessed March 10, 2013, http://www.wpafb.af.mil/ library /factsheets...as CRAs and CTAs, could enable collaboration through university consortia designed to support DOD laboratory research. Such alliances would have the...university consortia , may be able to leverage partnerships that meet their collaborative research needs. 5. Increased Patent Filing Fees when Partnering

  17. Annual report of Nuclear Engineering Research Laboratory, University of Tokyo in fiscal 1990

    International Nuclear Information System (INIS)

    1991-01-01

    In this annual report, the activities of research and education and the state of operation of the research facilities in this Laboratory in fiscal year 1990 are summarized. There are four large research facilities in this Laboratory, that is, the fast neutron source reactor 'Yayoi', the electron beam linear accelerator, the nuclear fusion reactor blanket experiment device and the heavy ion irradiation research facility. Those are used to execute research and education in the wide fields of atomic energy engineering, and put to the common utilization by universities in whole Japan. The results of the research with these facilities have been reported in the separate reports. The research aims at developing the most advanced and new fields in nuclear reactor engineering, and includes the engineering of the first wall and the fuel cycle for nuclear fusion reactors, electromagnetic structure engineering, AI and robotics, quantum beam engineering, the design of new type reactors, the basic process of radiochemistry and so on. The report on the course of the large scale facilities, research activities, the publication of research, education and the events in the Laboratory in the year are described. (K.I.)

  18. Bioenergy Research Programme. Yearbook 1994. Production of wood fuels

    International Nuclear Information System (INIS)

    Alakangas, E.

    1995-01-01

    BIOENERGIA Research Programme is one of energy technology programmes of the Finnish Ministry of Trade and Industry (in 1995 TEKES, Technology Development Center). The aim of Bioenergy Research Programme is to increase the use of economically profitable and environmentally sound bioenergy by improving the competitiveness of present peat and wood fuels. Research and development projects will also develop new economically competitive biofuels and new equipment and methods for production, handling and using of biofuels. The funding for 1994 was nearly 50 million FIM and projects numbered 60. The main goal of the production of wood fuels research area is to develop new production methods in order to decrease the production costs to the level of imported fuels. The total potential of the wood fuel use should be at least 1.0 million toe/a (5.5 million m 3 ). There were 27 projects in 1994 for research on wood fuel production. This part of the yearbook 1994 presents the main results of these projects. The wood reserves do not limit the obtainability of the target. Research and development work has, however, directed to development of equipment and research on wood fuels production chains. Many devices, designed for both separate and integrated production of wood fuels became ready or were becoming ready for prototyping, to be used for production tests. Results of the biomass harvesting and properties research were obtained for utilization in 1994. According to the results it is possible to obtain the desired targets both in integrated and separated production of wood fuels. (author)

  19. Argonne National Laboratory Annual Report of Laboratory Directed Research and Development Program Activities for FY 1994

    Energy Technology Data Exchange (ETDEWEB)

    None

    1995-02-25

    The purposes of Argonne's Laboratory Directed Research and Development (LDRD) Program are to encourage the development of novel concepts, enhance the Laboratory's R and D capabilities, and further the development of its strategic initiatives. Projects are selected from proposals for creative and innovative R and D studies which are not yet eligible for timely support through normal programmatic channels. Among the aims of the projects supported by the Program are establishment of engineering proof-of-principle; assessment of design feasibility for prospective facilities; development of an instrumental prototype, method, or system; or discovery in fundamental science. Several of these projects are closely associated with major strategic thrusts of the Laboratory as described in Argonne's Five-Year Institutional Plan, although the scientific implications of the achieved results extend well beyond Laboratory plans and objectives. The projects supported by the Program are distributed across the major programmatic areas at Argonne as indicated in the Laboratory's LDRD Plan for FY 1994. Project summaries of research in the following areas are included: (1) Advanced Accelerator and Detector Technology; (2) X-ray Techniques for Research in Biological and Physical Science; (3) Nuclear Technology; (4) Materials Science and Technology; (5) Computational Science and Technology; (6) Biological Sciences; (7) Environmental Sciences: (8) Environmental Control and Waste Management Technology; and (9) Novel Concepts in Other Areas.

  20. 2015 Fermilab Laboratory Directed Research & Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Wester, W., editor

    2015-05-26

    Fermilab is executing Laboratory Directed Research and Development (LDRD) as outlined by order DOE O 413.2B in order to enhance and realize the mission of the laboratory in a manner that also supports the laboratory’s strategic objectives and the mission of the Department of Energy. LDRD funds enable scientific creativity, allow for exploration of “high risk, high payoff” research, and allow for the demonstration of new ideas, technical concepts, and devices. LDRD also has an objective of maintaining and enhancing the scientific and technical vitality of Fermilab.

  1. 2014 Fermilab Laboratory Directed Research & Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Wester, W., editor

    2016-05-26

    Fermilab is executing Laboratory Directed Research and Development (LDRD) as outlined by order DOE O 413.2B in order to enhance and realize the mission of the laboratory in a manner that also supports the laboratory’s strategic objectives and the mission of the Department of Energy. LDRD funds enable scientific creativity, allow for exploration of “high risk, high payoff” research, and allow for the demonstration of new ideas, technical concepts, and devices. LDRD also has an objective of maintaining and enhancing the scientific and technical vitality of Fermilab.

  2. The waste management at research laboratories - problems and solutions

    International Nuclear Information System (INIS)

    Dellamano, Jose Claudio; Vicente, Roberto

    2011-01-01

    The radioactive management in radioactive installations must be planned and controlled. However, in the case of research laboratories, that management is compromised due to the common use of materials and installations, the lack of trained personnel and the nonexistence of clear and objective orientations by the regulator organism. Such failures cause an increasing of generated radioactive wastes and the imprecision or nonexistence of record of radioactive substances, occasioning a financial wastage, and the cancelling of licences for use of radioactive substances. This paper discusses and proposes solutions for the problems found at radioactive waste management in research laboratories

  3. Environmental survey at Lucas Heights Research Laboratories, 1989

    International Nuclear Information System (INIS)

    Hoffman, E.L.; Arthur, J.

    1990-09-01

    Results are presented of an environmental survey conducted in the neighbourhood of the Lucas Heights Research Laboratories during 1989. No radioactivity which could have originated from these laboratories was found in samples collected from possible human food chains. All low-level liquid and gaseous waste discharges were within authorised limits. The maximum possible annual dose to the general public from airborne waste during this period is estimated to be less than 0.01 millisieverts, which is one per cent of the limit for long-term exposure that is recommended by the National Health and Medical Research Council. 9 refs., 17 tabs., 2 figs

  4. Environmental survey at Lucas Heights Research Laboratories, 1990

    International Nuclear Information System (INIS)

    Hoffmann, E.L.

    1991-10-01

    Results are presented of an environmental survey conducted in the neighbourhood of the Lucas Heights Research Laboratories during 1990. No radioactivity which could have originated from these laboratories was found in samples collected from possible human food chains. All low-level liquid and gaseous waste discharges were within authorised limits. The maximum possible annual dose to the general public from airborne waste during this period is estimated to be less than 0.01 millisieverts, which is one per cent of the limit for long-term exposure that is recommended by the National Health and Medical Research Council. 11 refs., 16 tabs., 2 figs

  5. Environmental survey at Lucas Heights Research Laboratories, 1987

    International Nuclear Information System (INIS)

    Giles, M.S.; Foy, J.J.; Hoffmann, E.L.

    1989-12-01

    Results are presented of an environmental survey conducted in the neighbourhood of the Lucas Heights Research Laboratories during 1987. No radioactivity which could have originated from these laboratories was found in samples collected from possible human food chains. All low-level liquid and gaseous waste discharges were within authorized limits. The maximum possible annual dose to the general public from airborne waste during this period is estimated to be less than 0.01 millisieverts, which is one per cent of the limit for long-term exposure that is recommended by the National Health and Medical Research Council. 9 refs., 18 tabs., 2 figs

  6. Environmental survey at Lucas Heights Research Laboratories, 1984

    International Nuclear Information System (INIS)

    Giles, M.S.; Dudaitis, A.

    1986-12-01

    Results are presented of the environmental survey conducted in the neighbourhood of the Lucas Heights Research Laboratories during 1984. These results are satisfactory. No radioactivity which could have originated from these laboratories was found in samples collected from possible human food chains. All low-level liquid and gaseous waste discharges were within authorised limits. The maximum possible annual dose to the general public from airborne waste discharges during this period is estimated to be less than 0.01 millisieverts, which is one per cent of the limit for long-term exposure that is recommended by the National Health and Medical Research Council

  7. Environmental survey at the Lucas Heights Research Laboratories. 1983

    International Nuclear Information System (INIS)

    Giles, M.S.; Dudaitis, A.

    1985-12-01

    Results are presented of the environmental survey conducted in the neighbourhood of the Lucas Heights Research Laboratories during 1983. These results are satisfactory. No radioactivity which could have originated from these laboratories was found in samples collected from possible human food chains. All low-level liquid and gaseous waste discharges were within authorised limits. The maximum possible annual dose to the general public from airborne waste discharges during this period is estimated to be less than 0.01 millisieverts, which is 1 per cent of the limit for long-term exposure that is recommended by the National Health and Medical Research Council

  8. Los Alamos National Laboratory case studies on decommissioning of research reactors and a small nuclear facility

    International Nuclear Information System (INIS)

    Salazar, M.D.

    1998-01-01

    Approximately 200 contaminated surplus structures require decommissioning at Los Alamos National Laboratory. During the last 10 years, 50 of these structures have undergone decommissioning. These facilities vary from experimental research reactors to process/research facilities contaminated with plutonium-enriched uranium, tritium, and high explosives. Three case studies are presented: (1) a filter building contaminated with transuranic radionuclides; (2) a historical water boiler that operated with a uranyl-nitrate solution; and (3) the ultra-high-temperature reactor experiment, which used enriched uranium as fuel

  9. Los Alamos National Laboratory case studies on decommissioning of research reactors and a small nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Salazar, M.D.

    1998-12-01

    Approximately 200 contaminated surplus structures require decommissioning at Los Alamos National Laboratory. During the last 10 years, 50 of these structures have undergone decommissioning. These facilities vary from experimental research reactors to process/research facilities contaminated with plutonium-enriched uranium, tritium, and high explosives. Three case studies are presented: (1) a filter building contaminated with transuranic radionuclides; (2) a historical water boiler that operated with a uranyl-nitrate solution; and (3) the ultra-high-temperature reactor experiment, which used enriched uranium as fuel.

  10. 2015 Fermilab Laboratory Directed Research & Development Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    Wester, W. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States)

    2016-05-26

    The Fermi National Accelerator Laboratory (FNAL) is conducting a Laboratory Directed Research and Development (LDRD) program. Fiscal year 2015 represents the first full year of LDRD at Fermilab and includes seven projects approved mid-year in FY14 and six projects approved in FY15. One of the seven original projects has been completed just after the beginning of FY15. The implementation of LDRD at Fermilab is captured in the approved Fermilab 2015 LDRD Annual Program Plan. In FY15, the LDRD program represents 0.64% of Laboratory funding. The scope of the LDRD program at Fermilab will be established over the next couple of years where a portfolio of about 20 on-going projects representing approximately between 1% and 1.5% of the Laboratory funding is anticipated. This Annual Report focuses on the status of the current projects and provides an overview of the current status of LDRD at Fermilab.

  11. Smart Electronic Laboratory Notebooks for the NIST Research Environment.

    Science.gov (United States)

    Gates, Richard S; McLean, Mark J; Osborn, William A

    2015-01-01

    Laboratory notebooks have been a staple of scientific research for centuries for organizing and documenting ideas and experiments. Modern laboratories are increasingly reliant on electronic data collection and analysis, so it seems inevitable that the digital revolution should come to the ordinary laboratory notebook. The most important aspect of this transition is to make the shift as comfortable and intuitive as possible, so that the creative process that is the hallmark of scientific investigation and engineering achievement is maintained, and ideally enhanced. The smart electronic laboratory notebooks described in this paper represent a paradigm shift from the old pen and paper style notebooks and provide a host of powerful operational and documentation capabilities in an intuitive format that is available anywhere at any time.

  12. Laboratory Directed Research and Development Program FY 2007 Annual Report

    International Nuclear Information System (INIS)

    Sjoreen, Terrence P.

    2008-01-01

    The Oak Ridge National LaboratoryLaboratory Directed Research and Development (LDRD) program reports its status to the U.S. Department of Energy (DOE) in March of each year. The program operates under the authority of DOE Order 413.2B, 'Laboratory Directed Research and Development' (April 19, 2006), which establishes DOE's requirements for the program while providing the Laboratory Director broad flexibility for program implementation. LDRD funds are obtained through a charge to all Laboratory programs. This report includes summaries for all ORNL LDRD research activities supported during FY 2007. The associated FY 2007 ORNL LDRD Self-Assessment (ORNL/PPA-2008/2) provides financial data and an internal evaluation of the program's management process. ORNL is a DOE multiprogram science, technology, and energy laboratory with distinctive capabilities in materials science and engineering, neutron science and technology, energy production and end-use technologies, biological and environmental science, and scientific computing. With these capabilities ORNL conducts basic and applied research and development (R and D) to support DOE's overarching mission to advance the national, economic, and energy security of the United States and promote scientific and technological innovation in support of that mission. As a national resource, the Laboratory also applies its capabilities and skills to specific needs of other federal agencies and customers through the DOE Work for Others (WFO) program. Information about the Laboratory and its programs is available on the Internet at http://www.ornl.gov/. LDRD is a relatively small but vital DOE program that allows ORNL, as well as other DOE laboratories, to select a limited number of R and D projects for the purpose of: (1) maintaining the scientific and technical vitality of the Laboratory; (2) enhancing the Laboratory's ability to address future DOE missions; (3) fostering creativity and stimulating exploration of forefront science

  13. Laboratory Directed Research and Development Program FY 2005 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    Sjoreen, Terrence P [ORNL

    2006-04-01

    The Oak Ridge National Laboratory (ORNL) Laboratory Directed Research and Development (LDRD) Program reports its status to the U.S. Department of Energy (DOE) in March of each year. The program operates under the authority of DOE Order 413.2A, 'Laboratory Directed Research and Development' (January 8, 2001), which establishes DOE's requirements for the program while providing the Laboratory Director broad flexibility for program implementation. LDRD funds are obtained through a charge to all Laboratory programs. This report describes all ORNL LDRD research activities supported during FY 2005 and includes final reports for completed projects and shorter progress reports for projects that were active, but not completed, during this period. The FY 2005 ORNL LDRD Self-Assessment (ORNL/PPA-2006/2) provides financial data about the FY 2005 projects and an internal evaluation of the program's management process. ORNL is a DOE multiprogram science, technology, and energy laboratory with distinctive capabilities in materials science and engineering, neutron science and technology, energy production and end-use technologies, biological and environmental science, and scientific computing. With these capabilities ORNL conducts basic and applied research and development (R&D) to support DOE's overarching national security mission, which encompasses science, energy resources, environmental quality, and national nuclear security. As a national resource, the Laboratory also applies its capabilities and skills to the specific needs of other federal agencies and customers through the DOE Work For Others (WFO) program. Information about the Laboratory and its programs is available on the Internet at . LDRD is a relatively small but vital DOE program that allows ORNL, as well as other multiprogram DOE laboratories, to select a limited number of R&D projects for the purpose of: (1) maintaining the scientific and technical vitality of the

  14. Laboratory Directed Research and Development Program FY 2004 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    Sjoreen, Terrence P [ORNL

    2005-04-01

    The Oak Ridge National Laboratory (ORNL) Laboratory Directed Research and Development (LDRD) Program reports its status to the U.S. Department of Energy (DOE) in March of each year. The program operates under the authority of DOE Order 413.2A, 'Laboratory Directed Research and Development' (January 8, 2001), which establishes DOE's requirements for the program while providing the Laboratory Director broad flexibility for program implementation. LDRD funds are obtained through a charge to all Laboratory programs. This report describes all ORNL LDRD research activities supported during FY 2004 and includes final reports for completed projects and shorter progress reports for projects that were active, but not completed, during this period. The FY 2004 ORNL LDRD Self-Assessment (ORNL/PPA-2005/2) provides financial data about the FY 2004 projects and an internal evaluation of the program's management process. ORNL is a DOE multiprogram science, technology, and energy laboratory with distinctive capabilities in materials science and engineering, neutron science and technology, energy production and end-use technologies, biological and environmental science, and scientific computing. With these capabilities ORNL conducts basic and applied research and development (R&D) to support DOE's overarching national security mission, which encompasses science, energy resources, environmental quality, and national nuclear security. As a national resource, the Laboratory also applies its capabilities and skills to the specific needs of other federal agencies and customers through the DOE Work For Others (WFO) program. Information about the Laboratory and its programs is available on the Internet at . LDRD is a relatively small but vital DOE program that allows ORNL, as well as other multiprogram DOE laboratories, to select a limited number of R&D projects for the purpose of: (1) maintaining the scientific and technical vitality of the

  15. Laboratory Directed Research and Development Program FY 2007 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    Sjoreen, Terrence P [ORNL

    2008-04-01

    The Oak Ridge National Laboratory (ORNL) Laboratory Directed Research and Development (LDRD) program reports its status to the U.S. Department of Energy (DOE) in March of each year. The program operates under the authority of DOE Order 413.2B, 'Laboratory Directed Research and Development' (April 19, 2006), which establishes DOE's requirements for the program while providing the Laboratory Director broad flexibility for program implementation. LDRD funds are obtained through a charge to all Laboratory programs. This report includes summaries for all ORNL LDRD research activities supported during FY 2007. The associated FY 2007 ORNL LDRD Self-Assessment (ORNL/PPA-2008/2) provides financial data and an internal evaluation of the program's management process. ORNL is a DOE multiprogram science, technology, and energy laboratory with distinctive capabilities in materials science and engineering, neutron science and technology, energy production and end-use technologies, biological and environmental science, and scientific computing. With these capabilities ORNL conducts basic and applied research and development (R&D) to support DOE's overarching mission to advance the national, economic, and energy security of the United States and promote scientific and technological innovation in support of that mission. As a national resource, the Laboratory also applies its capabilities and skills to specific needs of other federal agencies and customers through the DOE Work for Others (WFO) program. Information about the Laboratory and its programs is available on the Internet at http://www.ornl.gov/. LDRD is a relatively small but vital DOE program that allows ORNL, as well as other DOE laboratories, to select a limited number of R&D projects for the purpose of: (1) maintaining the scientific and technical vitality of the Laboratory; (2) enhancing the Laboratory's ability to address future DOE missions; (3) fostering creativity and stimulating

  16. Protection of spent aluminum-clad research reactor fuels during extended wet storage

    International Nuclear Information System (INIS)

    Fernandes, Stela M.C.; Correa, Olandir V.; Souza, Jose A.; Ramanathan, Lalgudi V.; Antunes, Renato A.

    2013-01-01

    Aluminum-clad spent nuclear fuel from research reactors (RR) is stored in light water filled pools or basins worldwide. Many incidences of pitting corrosion of the fuel cladding has been reported and attributed to synergism in the effect of certain water parameters. Protection of spent Al-clad RR fuel with a conversion coating was proposed in 2008. Preliminary results revealed increased pitting corrosion resistance of cerium oxide coated aluminum alloys AA 1050 and AA 6061, used as RR fuel plate cladding. Further development of conversion coatings for Al alloys was carried out and this paper presents: (a) the preparation and characterization of hydrotalcite (HTC) coatings; (b) the results of laboratory tests in which the corrosion behavior of coated Al alloys in NaCl solutions was determined; (c) the results of field tests in which un-coated, boehmite coated, HTC coated and cerium modified boehmite / HTC coated AA 1050 and AA 6061 coupons were exposed to the IEA-R1 reactor spent fuel basin for extended periods. In these field tests the coupons coated with HTC from a high temperature (HT) bath and subsequently modified with Ce were the most resistant to pitting corrosion. In laboratory tests also, HT- hydrotalcite + Ce coated specimens were the most corrosion resistant in 0.01 M NaCl. The role of cerium in increasing the corrosion resistance imparted by the different conversion coatings of spent Al-clad RR fuel elements is presented. (author)

  17. Russian research reactor fuel return program starts shipping fuel to Russia

    International Nuclear Information System (INIS)

    Dedik, T.; Bolshinsky, I.; Krass, A.

    2003-01-01

    For almost four years the United States (U.S), the Russian Federation (R.F.), and the International Atomic Energy Agency (IAEA) have been discussing an initiative to return Soviet/Russian-origin research reactor fuel to the Russian Federation. In a series of bilateral and trilateral meetings in Vienna and Moscow, considerable progress has been made toward defining the Russian Research Reactor Fuel Return Program as well as obtaining the necessary technical data to facilitate the return. More than 20 research reactors in 17 countries that have Soviet- or Russian-supplied fuel have identified. Most of these reactors have stocks of both fresh and irradiated HEU fuel that must be carefully stored and managed for many years to come. On September 21, 2003 the Russian Research Reactor Fuel Return program shipped 14 kg of fresh Russian-origin HEU fuel from Romania to the nuclear fuel fabrication facility in Russia, which represented the beginning of the practical implementation of the program. (author)

  18. Laboratory directed research and development FY98 annual report; TOPICAL

    International Nuclear Information System (INIS)

    Al-Ayat, R; Holzrichter, J

    1999-01-01

    In 1984, Congress and the Department of Energy (DOE) established the Laboratory Directed Research and Development (LDRD) Program to enable the director of a national laboratory to foster and expedite innovative research and development (R and D) in mission areas. The Lawrence Livermore National Laboratory (LLNL) continually examines these mission areas through strategic planning and shapes the LDRD Program to meet its long-term vision. The goal of the LDRD Program is to spur development of new scientific and technical capabilities that enable LLNL to respond to the challenges within its evolving mission areas. In addition, the LDRD Program provides LLNL with the flexibility to nurture and enrich essential scientific and technical competencies and enables the Laboratory to attract the most qualified scientists and engineers. The FY98 LDRD portfolio described in this annual report has been carefully structured to continue the tradition of vigorously supporting DOE and LLNL strategic vision and evolving mission areas. The projects selected for LDRD funding undergo stringent review and selection processes, which emphasize strategic relevance and require technical peer reviews of proposals by external and internal experts. These FY98 projects emphasize the Laboratory's national security needs: stewardship of the U.S. nuclear weapons stockpile, responsibility for the counter- and nonproliferation of weapons of mass destruction, development of high-performance computing, and support of DOE environmental research and waste management programs

  19. Facilities for post-irradiation examination of experimental fuel elements at Chalk River Nuclear Laboratories

    International Nuclear Information System (INIS)

    Mizzan, E.; Chenier, R.J.

    1979-10-01

    Expansion of post-irradiation facilities at the Chalk River Nuclear Laboratories and steady improvement in hot-cell techniques and equipment are providing more support to Canada's reactor fuel development program. The hot-cell facility primarily used for examination of experimental fuels averages a quarterly throughput of 40 elements and 110 metallographic specimens. New developments in ultrasonic testing, metallographic sample preparation, active storage, active waste filtration, and fissile accountability are coming into use to increase the efficiency and safety of hot-cell operations. (author)

  20. Laboratory characterization of PM emissions from combustion of wildland biomass fuels

    Energy Technology Data Exchange (ETDEWEB)

    Hosseini, SeyedEhsan; Urbanski, Shawn; Dixit, P.; Qi, L.; Burling, Ian R.; Yokelson, Robert; Johnson, Timothy J.; Shrivastava, ManishKumar B.; Jung, H.; Weise, David; Miller, J. Wayne; Cocker, David R.

    2013-09-09

    Particle emissions from open burning of southwestern (SW) and southeastern (SE) U.S. 17 fuel types during 77 controlled laboratory burns are presented. The fuels include SW 18 vegetation types: ceanothus, chamise/scrub oak, coastal sage scrub, California sagebrush, 19 manzanita, maritime chaparral, masticated mesquite, oak savanna, and oak woodland as 20 well as SE vegetation types: 1-year, 2-year rough, pocosin, chipped understory, 21 understory hardwood, and pine litter. The SW fuels burned at a higher Modified 22 Combustion Efficiency (MCE) than the SE fuels resulting in lower particulate matter 23 (PM) mass emission factor (EF). Particle size distributions for six fuels and particle 24 number emission or all fuels are reported. Excellent mass closure (slope = 1.00, r2=0.94) 25 between ions, metals, and carbon with total weight was obtained. Organic carbon 26 emission factors inversely correlated (= 0.72) with MCE, while elemental carbon (EC) 27 had little correlation with MCE (=0.10). The EC/total carbon (TC) ratio sharply 28 increased with MCE for MCEs exceeding 0.94. The average levoglucosan and total Poly 29 Aromatic Hydrocarbons (PAH) emissions factors ranged from 25-1272 mg/kg fuel and 30 1790-11300 μg/kg fuel, respectively. No correlation between MCE and emissions of 31 PAHs/levoglucosan was found. Additionally, PAH diagnostic ratios were observed to be 32 poor indicators of biomass burning. Large fuel-type and regional dependency was 33 observed in the emission rates of ammonium, nitrate, fluoride, chloride, sodium, and

  1. Laboratory directed research and development annual report. Fiscal year 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-02-01

    The Department of Energy Order DOE 5000.4A establishes DOE`s policy and guidelines regarding Laboratory Directed Research and Development (LDRD) at its multiprogram laboratories. This report represents Pacific Northwest Laboratory`s (PNL`s) LDRD report for FY 1994. During FY 1994, 161 LDRD projects were selected for support through PNL`s LDRD project selection process. Total funding allocated to these projects was $13.7 million. Consistent with the Mission Statement and Strategic Plan provided in PNL`s Institutional Plan, the LDRD investments are focused on developing new and innovative approaches in research related to our {open_quotes}core competencies.{close_quotes} Currently, PNL`s core competencies have been identified as integrated environmental research; process science and engineering; energy systems development. In this report, the individual summaries of LDRD projects (presented in Section 1.0) are organized according to these core competencies. The largest proportion of Laboratory-level LDRD funds is allocated to the core competency of integrated environmental research. Projects within the three core competency areas were approximately 91.4 % of total LDRD project funding at PNL in FY 1994. A significant proportion of PNL`s LDRD funds are also allocated to projects within the various research centers that are proposed by individual researchers or small research teams. Funding allocated to each of these projects is typically $35K or less. The projects described in this report represent PNL`s investment in its future and are vital to maintaining the ability to develop creative solutions for the scientific and technical challenges faced by DOE and the nation. The report provides an overview of PNL`s LDRD program, the management process used for the program, and project summaries for each LDRD project.

  2. IAEA activities related to research reactor fuel conversion and spent fuel return programs

    International Nuclear Information System (INIS)

    Goldman, Ira N.; Adelfang, Pablo; Ritchie, Iain G.

    2005-01-01

    The IAEA has been involved for more than twenty years in supporting international nuclear non-proliferation efforts associated with reducing the amount of highly enriched uranium (HEU) in international commerce. IAEA projects and activities have directly supported the Reduced Enrichment for Research and Test Reactors (RERTR) programme, as well as directly associated efforts to return research reactor fuel to the country where it was originally enriched. IAEA efforts have included the development and maintenance of several data bases with information related to research reactors and research reactor spent fuel inventories that have been essential in planning and managing both RERTR and spent fuel return programmes. Other IAEA regular budget programs have supported research reactor fuel conversion from HEU to low enriched uranium (LEU), and in addressing issues common to many member states with spent fuel management problems and concerns. The paper briefly describes IAEA involvement since the early 1980's in these areas, including regular budget and Technical Co-operation programme activities, and focuses on efforts in the past five years to continue to support and accelerate U.S. and Russian research reactor spent fuel return programmes. (author)

  3. IAEA activities related to research reactor fuel conversion and spent fuel return programmes

    International Nuclear Information System (INIS)

    Ritchie, I.G.; Adelfang, P.; Goldman, I.N.

    2004-01-01

    Full text: The IAEA has been involved for more than twenty years in supporting international nuclear non-proliferation efforts associated with reducing the amount of highly enriched uranium (HEU) in international commerce. IAEA projects and activities have directly supported the Reduced Enrichment for Research and Test Reactors (RERTR) programme, as well as directly associated efforts to return research reactor fuel to the country of origin where it was originally enriched. IAEA efforts have included the development and maintenance of several data bases with information related to research reactors and research reactor spent fuel inventories that have been essential in planning and managing both RERTR and spent fuel return programmes. Other IAEA regular budget programmes have supported research reactor fuel conversion from HEU to low enriched uranium, and in addressing issues common to many member states with spent fuel management problems and concerns. The paper briefly describes IAEA involvement since the early 1980's in these areas, including regular budget and Technical Co-operation programme activities, and focuses on efforts in the past five years to continue to support and accelerate U.S. and Russian research reactor spent fuel return programmes. It is hoped that an announcement of the extension of the U.S. Acceptance Programme, which is expected in the very near future, will facilitate the life extensions of many productive TRIGA reactors around the world. (author)

  4. Frederick National Laboratory Rallies to Meet Demand for Zika Vaccine | Frederick National Laboratory for Cancer Research

    Science.gov (United States)

    The Frederick National Laboratory for Cancer Research is producing another round of Zika vaccine for ongoing studies to determine the best delivery method and dosage. This will lay the groundwork for additional tests to see if the vaccine prevents i

  5. Laboratory Directed Research and Development Program Activities for FY 2008.

    Energy Technology Data Exchange (ETDEWEB)

    Looney,J.P.; Fox, K.

    2009-04-01

    Brookhaven National Laboratory (BNL) is a multidisciplinary laboratory that maintains a primary mission focus the physical sciences, energy sciences, and life sciences, with additional expertise in environmental sciences, energy technologies, and national security. It is managed by Brookhaven Science Associates, LLC, (BSA) under contract with the U. S. Department of Energy (DOE). BNL's Fiscal year 2008 budget was $531.6 million. There are about 2,800 employees, and another 4,300 guest scientists and students who come each year to use the Laboratory's facilities and work with the staff. The BNL Laboratory Directed Research and Development (LDRD) Program reports its status to the U.S. Department of Energy (DOE) annually in March, as required by DOE Order 413.2B, 'Laboratory Directed Research and Development,' April 19, 2006, and the Roles, Responsibilities, and Guidelines for Laboratory Directed Research and Developlnent at the Department of Energy/National Nuclear Security Administration Laboratories dated June 13, 2006. Accordingly, this is our Annual Report in which we describe the Purpose, Approach, Technical Progress and Results, and Specific Accomplishments of all LDRD projects that received funding during Fiscal Year 2008. BNL expended $12 million during Fiscal Year 2008 in support of 69 projects. The program has two categories, the annual Open Call LDRDs and Strategic LDRDs, which combine to meet the overall objectives of the LDRD Program. Proposals are solicited annually for review and approval concurrent with the next fiscal year, October 1. For the open call for proposals, an LDRD Selection Committee, comprised of the Associate Laboratory Directors (ALDs) for the Scientific Directorates, an equal number of scientists recommended by the Brookhaven Council, plus the Assistant Laboratory Director for Policy and Strategic Planning, review the proposals submitted in response to the solicitation. The Open Can LDRD category emphasizes innovative research concepts

  6. Argonne National Laboratory: Laboratory Directed Research and Development FY 1993 program activities. Annual report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1993-12-23

    The purposes of Argonne`s Laboratory Directed Research and Development (LDRD) Program are to encourage the development of novel concepts, enhance the Laboratory`s R&D capabilities, and further the development of its strategic initiatives. Projects are selected from proposals for creative and innovative R&D studies which are not yet eligible for timely support through normal programmatic channels. Among the aims of the projects supported by the Program are establishment of engineering ``proof-of-principle`` assessment of design feasibility for prospective facilities; development of an instrumental prototype, method, or system; or discovery in fundamental science. Several of these projects are closely associated with major strategic thrusts of the Laboratory as described in Argonne`s Five Year Institutional Plan, although the scientific implications of the achieved results extend well beyond Laboratory plans and objectives. The projects supported by the Program are distributed across the major programmatic areas at Argonne as indicated in the Laboratory LDRD Plan for FY 1993.

  7. Laboratory Directed Research and Development FY 1998 Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    John Vigil; Kyle Wheeler

    1999-04-01

    This is the FY 1998 Progress Report for the Laboratory Directed Research and Development (LDRD) Program at Los Alamos National Laboratory. It gives an overview of the LDRD Program, summarizes work done on individual research projects, relates the projects to major Laboratory program sponsors, and provides an index to the principle investigators. Project summaries are grouped by their LDRD component: Competency Development, Program Development, and Individual Projects. Within each component, they are further grouped into nine technical categories: (1) materials science, (2) chemistry, (3) mathematics and computational science, (4) atomic, molecular, optical, and plasma physics, fluids, and particle beams, (5) engineering science, (6) instrumentation and diagnostics, (7) geoscience, space science, and astrophysics, (8) nuclear and particle physics, and (9) bioscience.

  8. The Los Alamos Scientific Laboratory - An Isolated Nuclear Research Establishment

    Energy Technology Data Exchange (ETDEWEB)

    Bradbury, Norris E. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Meade, Roger Allen [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-09-23

    Early in his twenty-five year career as the Director of the Los Alamos Scientific Laboratory, Norris Bradbury wrote at length about the atomic bomb and the many implications the bomb might have on the world. His themes were both technical and philosophical. In 1963, after nearly twenty years of leading the nation’s first nuclear weapons laboratory, Bradbury took the opportunity to broaden his writing. In a paper delivered to the International Atomic Energy Agency’s symposium on the “Criteria in the Selection of Sites for the Construction of Reactors and Nuclear Research Centers,” Bradbury took the opportunity to talk about the business of nuclear research and the human component of operating a scientific laboratory. This report is the transcript of his talk.

  9. Laboratory directed research and development: FY 1997 progress report

    Energy Technology Data Exchange (ETDEWEB)

    Vigil, J.; Prono, J. [comps.

    1998-05-01

    This is the FY 1997 Progress Report for the Laboratory Directed Research and Development (LDRD) program at Los Alamos National Laboratory. It gives an overview of the LDRD program, summarizes work done on individual research projects, relates the projects to major Laboratory program sponsors, and provides an index to the principal investigators. Project summaries are grouped by their LDRD component: Competency Development, Program Development, and Individual Projects. Within each component, they are further grouped into nine technical categories: (1) materials science, (2) chemistry, (3) mathematics and computational science, (4) atomic and molecular physics and plasmas, fluids, and particle beams, (5) engineering science, (6) instrumentation and diagnostics, (7) geoscience, space science, and astrophysics, (8) nuclear and particle physics, and (9) bioscience.

  10. National Renewable Energy Laboratory (NREL) 2006 Research Review

    Energy Technology Data Exchange (ETDEWEB)

    2007-07-01

    This 2006 issue of the NREL Research Review again reveals just how vital and diverse our research portfolio has become. Our feature story looks at how our move to embrace the tenants of "translational research" is strengthening our ability to meet the nation's energy goals. By closing the gap between basic science and applied research and development (R&D)--and focusing a bright light on the valuable end uses of our work--translational research promises to shorten the time it takes to push new technology off the lab bench and into the marketplace. This issue also examines our research into fuels of the future and our computer modeling of wind power deployment, both of which point out the real-world benefits of our work.

  11. Review of Heavy-Duty Engine Combustion Research at Sandia National Laboratories

    International Nuclear Information System (INIS)

    Robert W. Carling; Gurpreet Singh

    2000-01-01

    The objectives of this paper are to describe the research efforts in diesel engine combustion at Sandia National Laboratories' Combustion Research Facility and to provide recent experimental results. We have four diesel engine experiments supported by the Department of Energy, Office of Heavy Vehicle Technologies: a one-cylinder version of a Cummins heavy-duty engine, a diesel simulation facility, a one-cylinder Caterpillar engine to evaluate combustion of alternative fuels, and a homogeneous-charge, compression-ignition (HCCI) engine facility is under development. Recent experimental results to be discussed are: the effects of injection timing and diluent addition on late-combustion soot burnout, diesel-spray ignition and premixed-burn behavior, a comparison of the combustion characteristics of M85 (a mixture of 85% methanol and 15% gasoline) and DF2 (No.2 diesel reference fuel), and a description of our HCCI experimental program and modeling work

  12. Assessment of Research Needs for Advanced Fuel Cells

    Energy Technology Data Exchange (ETDEWEB)

    Penner, S.S.

    1985-11-01

    The DOE Advanced Fuel Cell Working Group (AFCWG) was formed and asked to perform a scientific evaluation of the current status of fuel cells, with emphasis on identification of long-range research that may have a significant impact on the practical utilization of fuel cells in a variety of applications. The AFCWG held six meetings at locations throughout the country where fuel cell research and development are in progress, for presentations by experts on the status of fuel cell research and development efforts, as well as for inputs on research needs. Subsequent discussions by the AFCWG have resulted in the identification of priority research areas that should be explored over the long term in order to advance the design and performance of fuel cells of all types. Surveys describing the salient features of individual fuel cell types are presented in Chapters 2 to 6 and include elaborations of long-term research needs relating to the expeditious introduction of improved fuel cells. The Introduction and the Summary (Chapter 1) were prepared by AFCWG. They were repeatedly revised in response to comments and criticism. The present version represents the closest approach to a consensus that we were able to reach, which should not be interpreted to mean that each member of AFCWG endorses every statement and every unexpressed deletion. The Introduction and Summary always represent a majority view and, occasionally, a unanimous judgment. Chapters 2 to 6 provide background information and carry the names of identified authors. The identified authors of Chapters 2 to 6, rather than AFCWG as a whole, bear full responsibility for the scientific and technical contents of these chapters.

  13. International collaboration, the route to fuel cycle research and development

    International Nuclear Information System (INIS)

    Tinsley, T.; Mathers, D.; Rayment, F.

    2013-01-01

    In hindsight, involvement with European Framework projects such as GoFastR (Gas-cooled Fast Reactors) and ACSEPT (Actinide Recycling by Separation and Transmutation) was a crucial and, at the time, an innovative step in maintaining the UK skills base during a period of major changes in the UK nuclear industry. It has undoubtedly delivered the objectives intended in terms of maintenance of the key skills, developing and training new staff, regenerating facilities and building strong links with the European nuclear research community. Over the last 2-3 years NNL's participation in European projects has moved forward such that NNL (National Nuclear Laboratory) is an integral partner of several major projects, fully engaged with delivering the core objectives of the projects and intent on forging deep collaborations with key organisations across Europe. With the renewed interest in nuclear energy and future fuel cycle options in the UK, NNL is now well positioned to contribute at an even deeper level in European level programmes

  14. International collaboration, the route to fuel cycle research and development

    Energy Technology Data Exchange (ETDEWEB)

    Tinsley, T.; Mathers, D.; Rayment, F. [National Nuclear Laboratory, Central Laboratory, Sellafield, Seascale, Cumbria, CA20 1PG (United Kingdom)

    2013-07-01

    In hindsight, involvement with European Framework projects such as GoFastR (Gas-cooled Fast Reactors) and ACSEPT (Actinide Recycling by Separation and Transmutation) was a crucial and, at the time, an innovative step in maintaining the UK skills base during a period of major changes in the UK nuclear industry. It has undoubtedly delivered the objectives intended in terms of maintenance of the key skills, developing and training new staff, regenerating facilities and building strong links with the European nuclear research community. Over the last 2-3 years NNL's participation in European projects has moved forward such that NNL (National Nuclear Laboratory) is an integral partner of several major projects, fully engaged with delivering the core objectives of the projects and intent on forging deep collaborations with key organisations across Europe. With the renewed interest in nuclear energy and future fuel cycle options in the UK, NNL is now well positioned to contribute at an even deeper level in European level programmes.

  15. Laboratory Directed Research and Development FY2008 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    Kammeraad, J E; Jackson, K J; Sketchley, J A; Kotta, P R

    2009-03-24

    The Laboratory Directed Research and Development (LDRD) Program, authorized by Congress in 1991 and administered by the Institutional Science and Technology Office at Lawrence Livermore, is our primary means for pursuing innovative, long-term, high-risk, and potentially high-payoff research that supports the full spectrum of national security interests encompassed by the missions of the Laboratory, the Department of Energy, and National Nuclear Security Administration. The accomplishments described in this annual report demonstrate the strong alignment of the LDRD portfolio with these missions and contribute to the Laboratory's success in meeting its goals. The LDRD budget of $91.5 million for fiscal year 2008 sponsored 176 projects. These projects were selected through an extensive peer-review process to ensure the highest scientific quality and mission relevance. Each year, the number of deserving proposals far exceeds the funding available, making the selection a tough one indeed. Our ongoing investments in LDRD have reaped long-term rewards for the Laboratory and the nation. Many Laboratory programs trace their roots to research thrusts that began several years ago under LDRD sponsorship. In addition, many LDRD projects contribute to more than one mission area, leveraging the Laboratory's multidisciplinary team approach to science and technology. Safeguarding the nation from terrorist activity and the proliferation of weapons of mass destruction will be an enduring mission of this Laboratory, for which LDRD will continue to play a vital role. The LDRD Program is a success story. Our projects continue to win national recognition for excellence through prestigious awards, papers published in peer-reviewed journals, and patents granted. With its reputation for sponsoring innovative projects, the LDRD Program is also a major vehicle for attracting and retaining the best and the brightest technical staff and for establishing collaborations with

  16. Laboratory Directed Research and Development FY2008 Annual Report

    International Nuclear Information System (INIS)

    Kammeraad, J.E.; Jackson, K.J.; Sketchley, J.A.; Kotta, P.R.

    2009-01-01

    The Laboratory Directed Research and Development (LDRD) Program, authorized by Congress in 1991 and administered by the Institutional Science and Technology Office at Lawrence Livermore, is our primary means for pursuing innovative, long-term, high-risk, and potentially high-payoff research that supports the full spectrum of national security interests encompassed by the missions of the Laboratory, the Department of Energy, and National Nuclear Security Administration. The accomplishments described in this annual report demonstrate the strong alignment of the LDRD portfolio with these missions and contribute to the Laboratory's success in meeting its goals. The LDRD budget of $91.5 million for fiscal year 2008 sponsored 176 projects. These projects were selected through an extensive peer-review process to ensure the highest scientific quality and mission relevance. Each year, the number of deserving proposals far exceeds the funding available, making the selection a tough one indeed. Our ongoing investments in LDRD have reaped long-term rewards for the Laboratory and the nation. Many Laboratory programs trace their roots to research thrusts that began several years ago under LDRD sponsorship. In addition, many LDRD projects contribute to more than one mission area, leveraging the Laboratory's multidisciplinary team approach to science and technology. Safeguarding the nation from terrorist activity and the proliferation of weapons of mass destruction will be an enduring mission of this Laboratory, for which LDRD will continue to play a vital role. The LDRD Program is a success story. Our projects continue to win national recognition for excellence through prestigious awards, papers published in peer-reviewed journals, and patents granted. With its reputation for sponsoring innovative projects, the LDRD Program is also a major vehicle for attracting and retaining the best and the brightest technical staff and for establishing collaborations with universities

  17. Laboratory directed research development annual report. Fiscal year 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    This document comprises Pacific Northwest National Laboratory`s report for Fiscal Year 1996 on research and development programs. The document contains 161 project summaries in 16 areas of research and development. The 16 areas of research and development reported on are: atmospheric sciences, biotechnology, chemical instrumentation and analysis, computer and information science, ecological science, electronics and sensors, health protection and dosimetry, hydrological and geologic sciences, marine sciences, materials science and engineering, molecular science, process science and engineering, risk and safety analysis, socio-technical systems analysis, statistics and applied mathematics, and thermal and energy systems. In addition, this report provides an overview of the research and development program, program management, program funding, and Fiscal Year 1997 projects.

  18. Fermilab a laboratory at the frontier of research

    CERN Document Server

    Gillies, James D

    2002-01-01

    Since its foundation in 1967, creeping urbanization has taken away some of Fermilab's remoteness, but the famous buffalo still roam, and farm buildings evocative of frontier America dot the landscape - appropriately for a laboratory at the high-energy frontier of modern research. Topics discussed are the Tevatron, detector upgrades, the neutrino programme, Fermilab and the LHC and the non-accelerator programme.

  19. Overview of environmental research at the Savannah River Laboratory

    International Nuclear Information System (INIS)

    Harvey, R.S.

    1977-01-01

    Research in the environmental sciences by the Savannah River Laboratory (SRL) has the general objective of improving our understanding of transport through ecosystems and functional processes within ecosystems. With increased understanding, the basis for environmental assessments can be improved for releases from the Savannah River Plant or from the power industry of the southeastern United States

  20. LBNL Laboratory Directed Research and Development Program FY2016

    Energy Technology Data Exchange (ETDEWEB)

    Ho, D.

    2017-03-01

    The Berkeley Lab Laboratory Directed Research and Development Program FY2016 report is compiled from annual reports submitted by principal investigators following the close of the fiscal year. This report describes the supported projects and summarizes their accomplishments. It constitutes a part of the LDRD program planning and documentation process that includes an annual planning cycle, project selection, implementation and review.

  1. Sequim Marine Research Laboratory routine environmental measurements during CY-1978

    International Nuclear Information System (INIS)

    Houston, J.R.; Blumer, P.J.

    1979-03-01

    Environmental data collected during 1978 in the vicinity of the Marine Research Laboratory show continued compliance with all applicable state and federal regulations and furthermore show no detectable change from conditions that existed in previous years. Samples collected for radiological analysis included soil, drinking water, bay water, clams, and seaweed. Radiation dose rates at 1 meter aboveground were also measured

  2. Magnetic mirror fusion research at the Lawrence Livermore Laboratory

    International Nuclear Information System (INIS)

    Post, R.F.

    1979-01-01

    An overall view is given of progress and plans for pressing forward with mirror research at Livermore. No detail is given on any one subject, and many interesting investigations being carried out at University laboratories in the U.S. that augment and support efforts at Livermore are omitted

  3. Laboratory directed research and development program FY 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-03-01

    This report compiles the annual reports of Laboratory Directed Research and Development projects supported by the Berkeley Lab. Projects are arranged under the following topical sections: (1) Accelerator and fusion research division; (2) Chemical sciences division; (3) Computing Sciences; (4) Earth sciences division; (5) Environmental energy technologies division; (6) life sciences division; (7) Materials sciences division; (8) Nuclear science division; (9) Physics division; (10) Structural biology division; and (11) Cross-divisional. A total of 66 projects are summarized.

  4. Laboratory directed research and development program FY 1997

    International Nuclear Information System (INIS)

    1998-03-01

    This report compiles the annual reports of Laboratory Directed Research and Development projects supported by the Berkeley Lab. Projects are arranged under the following topical sections: (1) Accelerator and fusion research division; (2) Chemical sciences division; (3) Computing Sciences; (4) Earth sciences division; (5) Environmental energy technologies division; (6) life sciences division; (7) Materials sciences division; (8) Nuclear science division; (9) Physics division; (10) Structural biology division; and (11) Cross-divisional. A total of 66 projects are summarized

  5. Catalog of research projects at Lawrence Berkeley Laboratory, 1985

    International Nuclear Information System (INIS)

    1985-01-01

    This Catalog has been created to aid in the transfer of technology from the Lawrence Berkeley Laboratory to potential users in industry, government, universities, and the public. The projects are listed for the following LBL groups: Accelerator and Fusion Research Division, Applied Science Division, Biology and Medicine Division, Center for Advanced Materials, Chemical Biodynamics Division, Computing Division, Earth Sciences Division, Engineering and Technical Services Division, Materials and Molecular Research Division, Nuclear Science Division, and Physics Division

  6. Naval Arctic Research Laboratory (NARL) Subsurface Containment Berm Investigation

    Science.gov (United States)

    2015-10-01

    Degree-Days CRREL Cold Regions Research and Engineering Laboratory ERDC U.S. Army Engineer Research and Development Center FWENC Foster Wheeler ...contract with the Navy, Foster Wheeler Environmental Corporation (FWENC) constructed a subsurface containment berm at the airfield of the Naval...659J91.61 ncURE 3- 3 NAVAl.. AACnC R(Sf.ARCH l,.ASORATORY POINT 9ARROW. AlASKA AS-BUILT CONTAINMENT BERM EXTENSION AND MONITORING WELLS FOSTER W

  7. Catalog of research projects at Lawrence Berkeley Laboratory, 1985

    Energy Technology Data Exchange (ETDEWEB)

    1985-01-01

    This Catalog has been created to aid in the transfer of technology from the Lawrence Berkeley Laboratory to potential users in industry, government, universities, and the public. The projects are listed for the following LBL groups: Accelerator and Fusion Research Division, Applied Science Division, Biology and Medicine Division, Center for Advanced Materials, Chemical Biodynamics Division, Computing Division, Earth Sciences Division, Engineering and Technical Services Division, Materials and Molecular Research Division, Nuclear Science Division, and Physics Division.

  8. Pump and valve research at the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Haynes, H.D.

    1992-01-01

    Over the last several years, the Oak Ridge National Laboratory (ORNL) has carried out several aging assessments on pumps and valves under the NRC's Nuclear Plant Aging Research (NPAR) Program. In addition, ORNL has established an Advanced Diagnostic Engineering Research and Development Center (ADEC) in order to play a key role in the field of diagnostic engineering. Initial ADEC research projects have addressed problems that were identified, at least in part, by the NPAR and other NRC-sponsored programs. This paper summarizes the pump and valve related research that has been done at ORNL and describes in more detail several diagnostic techniques developed at ORNL which are new commercially available

  9. Laboratory Directed Research and Development LDRD-FY-2011

    Energy Technology Data Exchange (ETDEWEB)

    Dena Tomchak

    2012-03-01

    This report provides a summary of the research conducted at the Idaho National Laboratory (INL) during Fiscal Year (FY) 2011. This report demonstrates the types of cutting edge research the INL is performing to help ensure the nation's energy security. The research conducted under this program is aligned with our strategic direction, benefits the Department of Energy (DOE) and is in compliance with DOE order 413.2B. This report summarizes the diverse research and development portfolio with emphasis on the DOE Office of Nuclear Energy (DOE-NE) mission, encompassing both advanced nuclear science and technology and underlying technologies.

  10. Basic research on cermet nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Ohashi, Hiroshi; Sto, Seichi [Hokkaido Univ., Sapporo (Japan). Faculty of Engineering; Takano, Masahide; Minato, Kazuo; Fukuda, Kosaku

    1998-01-01

    Production of cermet nuclear fuel having fine uranium dioxide (UO{sub 2}) particles dispersed in matrix metal requires basic property data on the compatibility of matrix metal with fission product compounds. It is thermodynamically suggested that, as burnup increases, cesium in oxide fuel reacts with the fuel, other fission products or cladding pipe and produces cesium uranates, cesium molybdate, or cesium chromate in stainless steel cladding pipe. Attempt was made to measure the thermal expansion coefficient and thermal conductivity of cesium uranates (Cs{sub 2}UO{sub 4} and Cs{sub 2}U{sub 2}O{sub 7}), cesium molybdate (Cs{sub 2}MoO{sub 4}) and cesium chromate (Cs{sub 2}CrO{sub 4}). Thermal expansion was measured by X-ray diffraction and determined by Cohen`s method. Thermal conductivity was obtained by measuring thermal diffusion by laser flash method. The thermal expansion of Cs{sub 2}UO{sub 4} and Cs{sub 2}U{sub 2}O{sub 7} is as low as 1.2% for the former and 1.0% for the latter, up to 1000K. The thermal expansion of Cs{sub 2}MoO{sub 4} is as high as that of Cs{sub 2}CrO{sub 4}, 2.1% for the former and 2.5% for the latter at temperatures from room temperature to 873K. Average thermal expansion in this temperature range is 4.4 x 10{sup -5} K{sup -1} for Cs{sub 2}MoO{sub 4} and 4.2 x 10{sup -5} K{sup -1}. The thermal expansion of Cs{sub 2}CrO{sub 4} is four times higher than that of UO{sub 2} and five times higher than that of Cr{sub 2}O{sub 3}. The thermal conductivity of Cs{sub 2}UO{sub 4} is nearly equal to that of Cs{sub 2}U{sub 2}O{sub 7} in absolute value and temperature dependency. Cs{sub 2}U{sub 2}O{sub 7}, having different thermal conductivity between {alpha} and {beta} phases, shows higher conductivity with {beta} than with {alpha}, about 1/4 of that of UO{sub 2} at 1000K. The thermal conductivity of Cs{sub 2}CrO{sub 4} is nearly equal to that of Cs{sub 2}MoO{sub 4} in absolute value and temperature dependency. (N.H.)

  11. Report of short term research group on environment safety in nuclear fuel cycle, 1983

    International Nuclear Information System (INIS)

    1984-01-01

    The research group on environment safety in nuclear fuel cycle was organized in fiscal 1979 as the research group in the range of the common utilization of Yayoi, and this is the third year since it developed into the short term research group in the Nuclear Engineering Research Laboratory. The results obtained so far were summarized in three reports, UTNL-R110, 134 and 147. In this fiscal year, ''The chemistry of reprocessing'' is the subtheme, and this short term research is to be carried out. The meeting is held on March 23 and 24, 1984, in this Laboratory, and the following reports are presented. The conference on institutional stability and the disposal of nuclear and chemically toxic wastes held at MIT, the social scientific analysis of nuclear power development, the present status of reprocessing research in foreign countries, the problems based on the operation experience of actual plants, the chemistry of fuel dissolution, the chemistry of solvent extraction, reprocessing offgas treatment and problems, the chemistry of fixing Kr and I in zeolite, waste treatment in the Tokai Reprocessing Plant of Power Reactor and Nuclear Fuel Development Corp., the chemistry of actinoids, denitration process and the chemistry of MOX production, and future reprocessing research. (Kako, I.)

  12. Handling of spent fuel from research reactors in Japan

    International Nuclear Information System (INIS)

    Kanda, K.

    1997-01-01

    In Japan eleven research reactors are in operation. After the 19th International Meeting on Reduced Enrichment for Research Reactors and Test Reactors (RERTR) on October 6-10, 1996, Seoul, Korea, the Five Agency Committee on Highly Enriched Uranium, which consists of Science and Technology Agency, the Ministry of Education, Science and Culture, the Ministry of Foreign Affairs, Japan Atomic Energy Research Institute (JAERI) and Kyoto University Research Reactor Institute (KURRI) met on November 7,1996, to discuss the handling of spent fuel from research reactors in Japan. Advantages and disadvantages to return spent fuel to the USA in comparison to Europe were discussed. So far, a number of spent fuel elements in JAERI and KURRI are to be returned to the US. The first shipment to the US is planned for 60 HEU elements from JMTR in 1997. The shipment from KURRI is planned to start in 1999. (author)

  13. Laboratory Directed Research and Development Program Activities for FY 2007.

    Energy Technology Data Exchange (ETDEWEB)

    Newman,L.

    2007-12-31

    Brookhaven National Laboratory (BNL) is a multidisciplinary laboratory that carries out basic and applied research in the physical, biomedical, and environmental sciences, and in selected energy technologies. It is managed by Brookhaven Science Associates, LLC, (BSA) under contract with the U. S. Department of Energy (DOE). BNL's Fiscal year 2007 budget was $515 million. There are about 2,600 employees, and another 4,500 guest scientists and students who come each year to use the Laboratory's facilities and work with the staff. The BNL Laboratory Directed Research and Development (LDRD) Program reports its status to the U.S. Department of Energy (DOE) annually in March, as required by DOE Order 413.2B, 'Laboratory Directed Research and Development', April 19, 2006, and the Roles, Responsibilities, and Guidelines for Laboratory Directed Research and Development at the Department of Energy/National Nuclear Security Administration Laboratories dated June 13, 2006. In accordance this is our Annual Report in which we describe the Purpose, Approach, Technical Progress and Results, and Specific Accomplishments of all LDRD projects that received funding during Fiscal Year 2007. The goals and objectives of BNL's LDRD Program can be inferred from the Program's stated purposes. These are to (1) encourage and support the development of new ideas and technology, (2) promote the early exploration and exploitation of creative and innovative concepts, and (3) develop new 'fundable' R&D projects and programs. The emphasis is clearly articulated by BNL to be on supporting exploratory research 'which could lead to new programs, projects, and directions' for the Laboratory. We explicitly indicate that research conducted under the LDRD Program should be highly innovative, and an element of high risk as to success is acceptable. In the solicitation for new proposals for Fiscal Year 2007 we especially requested innovative new projects in

  14. Calculation of fuel burn-up and fuel reloading for the Dalat Nuclear Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lan, Nguyen Phuoc; Huy, Ngo Quang [Centre for Nuclear Technique Application, Ho Chi Minh City (Viet Nam); Thong, Ha Van; Binh, Do Quang [Nuclear Research Inst., Da Lat (Viet Nam)

    1994-10-01

    Calculation of fuel burnup and fuel reloading for the Dalat Nuclear Research Reactor was carried out by using a new programme named HEXA-BURNUP, realized in a PC. The programme is used to calculate the following parameters of the Dalat reactor: a/Critical configurations of the core loaded with 69, 72, 74, 86, 88, 89 and 92 fuel elements. The effective multiplication coefficients equal 1 within the error ranges of less than 0.38%. b/ The thermal neutron flux distribution in the reactor. The calculated results agree with the experimental data measured at 11 typical positions. c/The average fuel burn-up for the period from Feb. 1984 to Sep. 1992. The difference between calculation and experiment is only about 1.9%. 10 fuel reloading versions are calculated, from which an optimal version is proposed. (author). 9 refs., 4 figs., 5 tabs.

  15. Reactor safety research and development in Chalk River Laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Nitheanandan, T. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

    2014-07-01

    Atomic Energy of Canada Limited's Chalk River Laboratories provides three different services to stakeholders and customers. The first service provided by the laboratory is the implementation of Research and Development (R&D) programs to provide the underlying technological basis of safe nuclear power reactor designs. A significant portion of the Canadian R&D capability in reactor safety resides at Atomic Energy of Canada Limited's Chalk River Laboratories, and this capability was instrumental in providing the science and technology required to aid in the safety design of CANDU power reactors. The second role of the laboratory has been in supporting nuclear facility licensees to ensure the continued safe operation of nuclear facilities, and to develop safety cases to justify continued operation. The licensing of plant life extension is a key industry objective, requiring extensive research on degradation mechanisms, such that safety cases are based on the original safety design data and valid and realistic assumptions regarding the effect of ageing and management of plant life. Recently, Chalk River Laboratories has been engaged in a third role in research to provide the technical basis and improved understanding for decision making by regulatory bodies. The state-of-the-art test facilities in Chalk River Laboratories have been contributing to the R&D needs of all three roles, not only in Canada but also in the international community, thorough Canada's participation in cooperative programs lead by International Atomic Energy Agency and the OECD's Nuclear Energy Agency. (author)

  16. Laboratory bioremediation of diesel fuel contaminated soil using indigenous cultures and surfactants

    International Nuclear Information System (INIS)

    Mas, Z.; Morin, P.; Walter, D.

    1998-01-01

    To help verify soil and groundwater remediation techniques, an Environmental Testing Facility (ETF) was built in Argentia, Newfoundland. A laboratory program has been developed and the influence of various parameters such as temperature, pH, nutrients and bacterial seeding on the biodegradation of diesel fuel-contaminated soils by indigenous microorganisms has been evaluated. Two non-toxic surfactants, Triton X-100 and Tween-60, have also been tested to determine their leaching potential for possible use in hydrocarbon removal, alone, or in combination with bioremediation. The addition of Triton X-100 showed no significant effect on the biotreatment of diesel fuel, but improved markedly diesel fuel leaching by percolation, indicating good potential for global remediation of the test soil by a combination of leaching and biodegradation. Tween-60 appears to inhibit biological activity, causing the efficiency of bacterial growth to drop from 50 per cent to 35 per cent. 8 refs., 4 tabs., 6 figs

  17. Report of 5th new nuclear fuel research meeting, Yayoi Research Group. Trend of advanced basic research in nuclear fuel technical development

    International Nuclear Information System (INIS)

    1994-03-01

    Theme of this meeting is 'Trend of advanced basic research in nuclear fuel technical development', and it was attempted to balance both sides of the basic research and the development. At the meeting, lectures were given on the chemical form of FPs in oxide fuel pins, the absorption of hydrogen of fuel cladding tubes, the application of hydride fuel to thorium cycle, the thermal properties of fuel cladding tubes, the preparation of NpN and heat conductivity, the high temperature chemical reprocessing of nitride fuel, the research on the annihilation treatment of minor actinide in fast reactors, the separation of TRU by dry process and the annihilation using a metallic fuel FBR. In this report, the summaries of the lectures are collected, and also the program of the meeting and the list of attendants are shown. (K.I.)

  18. Savannah River Laboratory data banks for risk assessment of fuel reprocessing plants

    International Nuclear Information System (INIS)

    Durant, W.S.

    1981-10-01

    The Savannah River Laboratory maintains a series of computerized data banks primarily as an aid in probabilistic risk assessment studies in the fuel reprocessing facilities. These include component failure rates, generic incidents, and reports of specific deviations from normal operating conditions. In addition to providing data for probability studies, these banks, have served as a valuable aid in trend analysis, equipment histories, process hazards analysis, consequence assessments, incident audit, process problem solving, and training

  19. Laboratory-Directed Research and Development 2016 Summary Annual Report

    International Nuclear Information System (INIS)

    Pillai, Rekha Sukamar; Jacobson, Julie Ann

    2017-01-01

    The Laboratory-Directed Research and Development (LDRD) Program at Idaho National Laboratory (INL) reports its status to the U.S. Department of Energy (DOE) by March of each year. The program operates under the authority of DOE Order 413.2C, 'Laboratory Directed Research and Development' (April 19, 2006), which establishes DOE's requirements for the program while providing the laboratory director broad flexibility for program implementation. LDRD funds are obtained through a charge to all INL programs. This report includes summaries of all INL LDRD research activities supported during Fiscal Year (FY) 2016. INL is the lead laboratory for the DOE Office of Nuclear Energy (DOE-NE). The INL mission is to discover, demonstrate, and secure innovative nuclear energy solutions, other clean energy options, and critical infrastructure with a vision to change the world's energy future and secure our critical infrastructure. Operating since 1949, INL is the nation's leading research, development, and demonstration center for nuclear energy, including nuclear nonproliferation and physical and cyber-based protection of energy systems and critical infrastructure, as well as integrated energy systems research, development, demonstration, and deployment. INL has been managed and operated by Battelle Energy Alliance, LLC (a wholly owned company of Battelle) for DOE since 2005. Battelle Energy Alliance, LLC, is a partnership between Battelle, BWX Technologies, Inc., AECOM, the Electric Power Research Institute, the National University Consortium (Massachusetts Institute of Technology, Ohio State University, North Carolina State University, University of New Mexico, and Oregon State University), and the Idaho university collaborators (i.e., University of Idaho, Idaho State University, and Boise State University). Since its creation, INL's research and development (R&D) portfolio has broadened with targeted programs supporting national missions to advance nuclear energy, enable clean

  20. Laboratory-Directed Research and Development 2016 Summary Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    Pillai, Rekha Sukamar [Idaho National Lab. (INL), Idaho Falls, ID (United States); Jacobson, Julie Ann [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2017-01-01

    The Laboratory-Directed Research and Development (LDRD) Program at Idaho National Laboratory (INL) reports its status to the U.S. Department of Energy (DOE) by March of each year. The program operates under the authority of DOE Order 413.2C, “Laboratory Directed Research and Development” (April 19, 2006), which establishes DOE’s requirements for the program while providing the laboratory director broad flexibility for program implementation. LDRD funds are obtained through a charge to all INL programs. This report includes summaries of all INL LDRD research activities supported during Fiscal Year (FY) 2016. INL is the lead laboratory for the DOE Office of Nuclear Energy (DOE-NE). The INL mission is to discover, demonstrate, and secure innovative nuclear energy solutions, other clean energy options, and critical infrastructure with a vision to change the world’s energy future and secure our critical infrastructure. Operating since 1949, INL is the nation’s leading research, development, and demonstration center for nuclear energy, including nuclear nonproliferation and physical and cyber-based protection of energy systems and critical infrastructure, as well as integrated energy systems research, development, demonstration, and deployment. INL has been managed and operated by Battelle Energy Alliance, LLC (a wholly owned company of Battelle) for DOE since 2005. Battelle Energy Alliance, LLC, is a partnership between Battelle, BWX Technologies, Inc., AECOM, the Electric Power Research Institute, the National University Consortium (Massachusetts Institute of Technology, Ohio State University, North Carolina State University, University of New Mexico, and Oregon State University), and the Idaho university collaborators (i.e., University of Idaho, Idaho State University, and Boise State University). Since its creation, INL’s research and development (R&D) portfolio has broadened with targeted programs supporting national missions to advance nuclear energy

  1. The University of Missouri Research Reactor, its fuel and productivity

    International Nuclear Information System (INIS)

    Brugger, R.M.; Schlapper, G.A.; Alger, D.M.

    1993-01-01

    This paper describes the University of Missouri Research Reactor (MURR) and presents a summary of contributions to education, research, and service. These efforts have helped offset the impact on the U.S. economy of research from other countries. Special emphasis is placed on fuel design developments that have allowed MuRR to keep the cost megawatt day (MWD) of fuel essentially constant. Also noted is the fact that the United States has missed some research opportunities because of a hold-the-line attitude. The slipping position of U.S. research reactors is compared with the rest of the world. As will be further outlined in the text, the MURR cannot (with available technology) decrease its U-235 enrichment level and maintain present research capabilities and fuel cycle costs. Data is presented to show how MURR, if permitted to use advanced fuel technology, could reduce fuel fabrication costs and onsite U-235 inventory. In addition it is shown that MURR could increase its capabilities provided that arbitrary institutional limits are removed

  2. The University of Missouri Research Reactor, its fuel and productivity

    International Nuclear Information System (INIS)

    Brugger, Robert M.; Schlapper, Gerald A.; Alger, Don M.

    1993-01-01

    This paper describes the University of Missouri Research Reactor (MURR) and presents a summary of contributions to education, research, and service. These efforts have helped offset the impact on the U. S. economy of research from other countries. Special emphasis is placed on fuel design developments that have allowed MURR to keep the cost megawatt day (MWD) of fuel essentially constant. Also noted is the fact that the United States has missed some research opportunities because of a hold-the-line attitude. The slipping position of U.S. research reactors is compared with the rest of the world. As will be further outlined in the text, the MURR cannot (with available technology) decrease its U-235 enrichment level and maintain present research capabilities and fuel cycle costs. Data is presented to show how MURR if permitted to use advanced fuel technology, could reduce fuel fabrication costs and onsite U-235 inventory. In addition it is shown that MURR could increase its capabilities provided that arbitrary institutional limits are removed

  3. Laboratory Directed Research and Development Program. FY 1993

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    This report is compiled from annual reports submitted by principal investigators following the close of fiscal year 1993. This report describes the projects supported and summarizes their accomplishments. The program advances the Laboratory`s core competencies, foundations, scientific capability, and permits exploration of exciting new opportunities. Reports are given from the following divisions: Accelerator and Fusion Research, Chemical Sciences, Earth Sciences, Energy and Environment, Engineering, Environment -- Health and Safety, Information and Computing Sciences, Life Sciences, Materials Sciences, Nuclear Science, Physics, and Structural Biology. (GHH)

  4. A 50-year research journey. From laboratory to clinic.

    Science.gov (United States)

    Ross, John

    2009-01-01

    Prior important research is not always cited, exemplified by Oswald Avery's pioneering discovery that DNA is the genetic transforming factor; it was not cited by Watson and Crick 10 years later. My first laboratory research (National Institutes of Health 1950s) resulted in the clinical development of transseptal left heart catheterization. Laboratory studies on cardiac muscle mechanics in normal and failing hearts led to the concept of afterload mismatch with limited preload reserve. At the University of California, San Diego in La Jolla (1968) laboratory experiments on coronary artery reperfusion after sustained coronary occlusion showed salvage of myocardial tissue, a potential treatment for acute myocardial infarction proven in clinical trials of thrombolysis 14 years later. Among 60 trainees who worked with me in La Jolla, one-third were Japanese and some of their important laboratory experiments are briefly recounted, beginning with Sasayama, Tomoike and Shirato in the 1970 s. Recently, we developed a method for cardiac gene transfer, and subsequently we showed that gene therapy for the defect in cardiomyopathic hamsters halted the progression of advanced disease. Cardiovascular research and medicine are producing continuing advances in technologies for gene transfer and embryonic stem cell transplantation, targeting of small molecules, and tissue and organ engineering.

  5. Laboratory Directed Research and Development Program FY98

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, T. [ed.; Chartock, M.

    1999-02-05

    The Ernest Orlando Lawrence Berkeley National Laboratory (LBNL or Berkeley Lab) Laboratory Directed Research and Development Program FY 1998 report is compiled from annual reports submitted by principal investigators following the close of the fiscal year. This report describes the supported projects and summarizes their accomplishments. It constitutes a part of the Laboratory Directed Research and Development (LDRD) program planning and documentation process that includes an annual planning cycle, projection selection, implementation, and review. The LBNL LDRD program is a critical tool for directing the Laboratory's forefront scientific research capabilities toward vital, excellent, and emerging scientific challenges. The program provides the resources for LBNL scientists to make rapid and significant contributions to critical national science and technology problems. The LDRD program also advances LBNL's core competencies, foundations, and scientific capability, and permits exploration of exciting new opportunities. All projects are work in forefront areas of science and technology. Areas eligible for support include the following: Advanced study of hypotheses, concepts, or innovative approaches to scientific or technical problems; Experiments and analyses directed toward ''proof of principle'' or early determination of the utility of new scientific ideas, technical concepts, or devices; and Conception and preliminary technical analyses of experimental facilities or devices.

  6. Laboratory Directed Research and Development Program. Annual report

    Energy Technology Data Exchange (ETDEWEB)

    Ogeka, G.J.

    1991-12-01

    Today, new ideas and opportunities, fostering the advancement of technology, are occurring at an ever-increasing rate. It, therefore, seems appropriate that a vehicle be available which fosters the development of these new ideas and technologies, promotes the early exploration and exploitation of creative and innovative concepts, and which develops new ``fundable`` R&D projects and programs. At Brookhaven National Laboratory (BNL), one such method is through its Laboratory Directed Research and Development (LDRD) Program. This discretionary research and development tool is critical in maintaining the scientific excellence and vitality of the Laboratory. Additionally, it is a means to stimulate the scientific community, fostering new science and technology ideas, which is the major factor achieving and maintaining staff excellence, and a means to address national needs, with the overall mission of the Department of Energy (DOE) and the Brookhaven National Laboratory. The Project Summaries with their accomplishments described in this report reflect the above. Aside from leading to new fundable or promising programs and producing especially noteworthy research, they have resulted in numerous publications in various professional and scientific journals, and presentations at meetings and forums.

  7. LABORATORY DIRECTED RESEARCH AND DEVELOPMENT PROGRAM ACTIVITIES FOR FY2002.

    Energy Technology Data Exchange (ETDEWEB)

    FOX,K.J.

    2002-12-31

    Brookhaven National (BNL) Laboratory is a multidisciplinary laboratory that carries out basic and applied research in the physical, biomedical, and environmental sciences, and in selected energy technologies. It is managed by Brookhaven Science Associates, LLC, under contract with the U. S. Department of Energy. BNL's total annual budget has averaged about $450 million. There are about 3,000 employees, and another 4,500 guest scientists and students who come each year to use the Laboratory's facilities and work with the staff. The BNL Laboratory Directed Research and Development (LDRD) Program reports its status to the U.S. Department of Energy (DOE) annually in March, as required by DOE Order 4 1 3.2A, ''Laboratory Directed Research and Development,'' January 8, 2001, and the LDRD Annual Report guidance, updated February 12, 1999. The LDRD Program obtains its funds through the Laboratory overhead pool and operates under the authority of DOE Order 413.2A. The goals and objectives of BNL's LDRD Program can be inferred from the Program's stated purposes. These are to (1) encourage and support the development of new ideas and technology, (2) promote the early exploration and exploitation of creative and innovative concepts, and (3) develop new ''fundable'' R&D projects and programs. The emphasis is clearly articulated by BNL to be on supporting exploratory research ''which could lead to new programs, projects, and directions'' for the Laboratory. As one of the premier scientific laboratories of the DOE, BNL must continuously foster groundbreaking scientific research. At Brookhaven National Laboratory one such method is through its LDRD Program. This discretionary research and development tool is critical in maintaining the scientific excellence and long-term vitality of the Laboratory. Additionally, it is a means to stimulate the scientific community and foster new science and technology

  8. Status of USNRC research on fuel behavior under accident conditions

    International Nuclear Information System (INIS)

    Johnston, W.V.

    1976-01-01

    The program of the Fuel Behaviour Research is directed at providing a detailed understanding of the response of nuclear fuel assemblies to off-normal or accident conditions. This understanding is expressed in physical and analytical correlations which are incorporated into computer codes. The results of these experiments and the resulting codes are available to the licensing authorities for use in evaluating utility submissions. (orig.) [de

  9. Guidelines for euthanasia of laboratory animals used in biomedical research

    Directory of Open Access Journals (Sweden)

    Adina Baias,

    2012-06-01

    Full Text Available Laboratory animals are used in several fields of science research, especially in biology, medicine and veterinary medicine. The majority of laboratory animals used in research are experimental models that replace the human body in study regarding pharmacological or biological safety products, studies conducted for a betterunderstanding of oncologic processes, toxicology, genetic studies or even new surgical techniques. Experimental protocols include a stage in which animals are euthanized in order to remove organs and tissues,or for no unnecessary pain and suffering of animals (humane endpoints or to mark the end of research. The result of euthanasia techniques is a rapid loss of consciousness followed by cardiac arrest, respiratory arrest and disruption of brain activity. Nowadays, the accepted euthanasia techniques can use chemicals (inhalant agents like: carbon dioxide, nitrogen or argon, overdoses of injectable anesthetics or physical methods (decapitation, cervical spine dislocation, stunning, gunshot, pitching.

  10. Laboratory Directed Research and Development FY 2000 Annual Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    Los Alamos National Laboratory

    2001-05-01

    This is the FY00 Annual Progress report for the Laboratory Directed Research and Development (LDRD) Program at Los Alamos National Laboratory. It gives an overview of the LDRD Program, summarizes progress on each project conducted during FY00, characterizes the projects according to their relevance to major funding sources, and provides an index to principal investigators. Project summaries are grouped by LDRD component: Directed Research and Exploratory Research. Within each component, they are further grouped into the ten technical categories: (1) atomic, molecular, optical, and plasma physics, fluids, and beams, (2) bioscience, (3) chemistry, (4) computer science and software engineering, (5) engineering science, (6) geoscience, space science, and astrophysics, (7) instrumentation and diagnostics, (8) materials science, (9) mathematics, simulation, and modeling, and (10) nuclear and particle physics.

  11. Laboratory Directed Research and Development Program FY 2006

    Energy Technology Data Exchange (ETDEWEB)

    Hansen (Ed.), Todd

    2007-03-08

    The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab or LBNL) is a multi-program national research facility operated by the University of California for the Department of Energy (DOE). As an integral element of DOE's National Laboratory System, Berkeley Lab supports DOE's missions in fundamental science, energy resources, and environmental quality. Berkeley Lab programs advance four distinct goals for DOE and the nation: (1) To perform leading multidisciplinary research in the computing sciences, physical sciences, energy sciences, biosciences, and general sciences in a manner that ensures employee and public safety and protection of the environment. (2) To develop and operate unique national experimental facilities for qualified investigators. (3) To educate and train future generations of scientists and engineers to promote national science and education goals. (4) To transfer knowledge and technological innovations and to foster productive relationships among Berkeley Lab's research programs, universities, and industry in order to promote national economic competitiveness.

  12. FY2007 Laboratory Directed Research and Development Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    Craig, W W; Sketchley, J A; Kotta, P R

    2008-03-20

    The Laboratory Directed Research and Development (LDRD) annual report for fiscal year 2007 (FY07) provides a summary of LDRD-funded projects for the fiscal year and consists of two parts: An introduction to the LDRD Program, the LDRD portfolio-management process, program statistics for the year, and highlights of accomplishments for the year. A summary of each project, submitted by the principal investigator. Project summaries include the scope, motivation, goals, relevance to Department of Energy (DOE)/National Nuclear Security Administration (NNSA) and Lawrence Livermore National Laboratory (LLNL) mission areas, the technical progress achieved in FY07, and a list of publications that resulted from the research in FY07. Summaries are organized in sections by research category (in alphabetical order). Within each research category, the projects are listed in order of their LDRD project category: Strategic Initiative (SI), Exploratory Research (ER), Laboratory-Wide Competition (LW), and Feasibility Study (FS). Within each project category, the individual project summaries appear in order of their project tracking code, a unique identifier that consists of three elements. The first is the fiscal year the project began, the second represents the project category, and the third identifies the serial number of the proposal for that fiscal year.

  13. Mid-Term Direction of JAEA Nuclear Fuel Cycle Engineering Laboratories

    International Nuclear Information System (INIS)

    Ojima, H.; Sugiyama, T.; Tanaka, K.; Takeda, S.; Nomura, S.

    2009-01-01

    1. Introduction Nuclear Fuel Cycle Engineering Laboratories (NCL) of Japan Atomic Energy Agency (JAEA) has sufficient experience and ability through its 50 year operation to establish the next generation closed cycle. It strives to become a world-class Center Of Excellence. 2. Current activity in NCL: 1) - Recycling of MOX fuel: The Tokai Reprocessing Plant has reprocessed 29 tons of MOX fuel from the ATR Fugenh as a part of 1140 tons of cumulative spent fuel reprocessed. JAEA has supported the pre-operation of the Rokkasho Reprocessing Plant. An innovative MOX pellet fabrication process has been developed in the Plutonium Fuel Development Center, and a part of products obtained by the development are used as a fuel for core confirmation test for re-startup of the FBR Monjuh. Characterization of MOX containing Am and Np has been studied and a new data such as melting point and thermal conductivity were reported. In the Chemical Processing Facility, a hot lab., an advanced aqueous reprocessing technology has been tested for TRU recovery, economical improvement, etc., using irradiated MOX fuel from the FR Joyoh. 2) - Supporting Activity: JAEA has improved the effectiveness and efficiency of existing safeguards activities. The Integrated Safeguards approach for all facilities in NCL has been implemented since August, 2008, as a pioneer and a good example in the world. To reduce anxiety among local residents, NCL has explained its operation plans and exchanged information and opinions with them concerning potential risks to health and environment. Recently, stake-holder participation in the management of NCL was started from the view point of Corporate Social Responsibility. In April, 2008, the agreement was signed with Idaho National Laboratory for cooperation of personnel training in fuel cycle area. 3. Mid-Term Direction: In Japan, feasibility and direction of the transition period from the LWR era to the FBR era should be discussed for the next several years. Study

  14. Mid-Term Direction of JAEA Nuclear Fuel Cycle Engineering Laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Ojima, H.; Sugiyama, T.; Tanaka, K.; Takeda, S.; Nomura, S. [Tokai-mura, Ibaraki-ken 319-1194 (Japan)

    2009-06-15

    1. Introduction Nuclear Fuel Cycle Engineering Laboratories (NCL) of Japan Atomic Energy Agency (JAEA) has sufficient experience and ability through its 50 year operation to establish the next generation closed cycle. It strives to become a world-class Center Of Excellence. 2. Current activity in NCL: 1) - Recycling of MOX fuel: The Tokai Reprocessing Plant has reprocessed 29 tons of MOX fuel from the ATR Fugenh as a part of 1140 tons of cumulative spent fuel reprocessed. JAEA has supported the pre-operation of the Rokkasho Reprocessing Plant. An innovative MOX pellet fabrication process has been developed in the Plutonium Fuel Development Center, and a part of products obtained by the development are used as a fuel for core confirmation test for re-startup of the FBR Monjuh. Characterization of MOX containing Am and Np has been studied and a new data such as melting point and thermal conductivity were reported. In the Chemical Processing Facility, a hot lab., an advanced aqueous reprocessing technology has been tested for TRU recovery, economical improvement, etc., using irradiated MOX fuel from the FR Joyoh. 2) - Supporting Activity: JAEA has improved the effectiveness and efficiency of existing safeguards activities. The Integrated Safeguards approach for all facilities in NCL has been implemented since August, 2008, as a pioneer and a good example in the world. To reduce anxiety among local residents, NCL has explained its operation plans and exchanged information and opinions with them concerning potential risks to health and environment. Recently, stake-holder participation in the management of NCL was started from the view point of Corporate Social Responsibility. In April, 2008, the agreement was signed with Idaho National Laboratory for cooperation of personnel training in fuel cycle area. 3. Mid-Term Direction: In Japan, feasibility and direction of the transition period from the LWR era to the FBR era should be discussed for the next several years. Study

  15. Hydrogen and fuel cell research networking in Ontario

    Energy Technology Data Exchange (ETDEWEB)

    Peppley, B.A. [Queen' s-RMC Fuel Cell Research Centre, Kingston, ON (Canada)

    2009-07-01

    This presentation reviewed the activities of the Ontario Fuel Cell Research and Innovation Network since its launch in 2006. Funded by the Ontario Ministry of Research and Innovation, the project involves 17 academic researchers from 8 universities and is supported by 8 industrial partners. The group of researchers has made progress in supporting the developing fuel cell industry in Ontario and in Canada. Their work has the potential to help deploy the province's automotive-oriented manufacturing sector in directions that address the issues of clean air and climate change. New initiatives in the development of hydrogen and fuel cell technologies are instrumental in expanding this network to leverage new business activities in the post financial crisis period. These activities are expected to result in economic benefits for job and economic growth.

  16. Criticality safety research on nuclear fuel cycle facility

    Energy Technology Data Exchange (ETDEWEB)

    Miyoshi, Yoshinori [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2004-07-01

    This paper present d s current status and future program of the criticality safety research on nuclear fuel cycle made by Japan Atomic Energy Research Institute. Experimental research on solution fuel treated in reprocessing plant has been performed using two critical facilities, STACY and TRACY. Fundamental data of static and transient characteristics are accumulated for validation of criticality safety codes. Subcritical measurements are also made for developing a monitoring system for criticality safety. Criticality safety codes system for solution and power system, and evaluation method related to burnup credit are developed. (author)

  17. Radiological Characterization and Final Facility Status Report Tritium Research Laboratory

    International Nuclear Information System (INIS)

    Garcia, T.B.; Gorman, T.P.

    1996-08-01

    This document contains the specific radiological characterization information on Building 968, the Tritium Research Laboratory (TRL) Complex and Facility. We performed the characterization as outlined in its Radiological Characterization Plan. The Radiological Characterization and Final Facility Status Report (RC ampersand FFSR) provides historic background information on each laboratory within the TRL complex as related to its original and present radiological condition. Along with the work outlined in the Radiological Characterization Plan (RCP), we performed a Radiological Soils Characterization, Radiological and Chemical Characterization of the Waste Water Hold-up System including all drains, and a Radiological Characterization of the Building 968 roof ventilation system. These characterizations will provide the basis for the Sandia National Laboratory, California (SNL/CA) Site Termination Survey .Plan, when appropriate

  18. Tritium monitoring at the Sandia Tritium Research Laboratory

    International Nuclear Information System (INIS)

    Devlin, T.K.

    1978-10-01

    Sandia Laboratories at Livermore, California, is presently beginning operation of a Tritium Research Laboratory (TRL). The laboratory incorporates containment and cleanup facilities such that any unscheduled tritium release is captured rather than vented to the atmosphere. A sophisticated tritium monitoring system is in use at the TRL to protect operating personnel and the environment, as well as ensure the safe and effective operation of the TRL decontamination systems. Each monitoring system has, in addition to a local display, a display in a centralized control room which, when coupled room which, when coupled with the TRL control computer, automatically provides an immediate assessment of the status of the entire facility. The computer controls a complex alarm array status of the entire facility. The computer controls a complex alarm array and integrates and records all operational and unscheduled tritium releases

  19. Current Sandia programs and laboratory facilities for tritium research

    International Nuclear Information System (INIS)

    Swansiger, W.A.; West, L.A.

    1975-01-01

    Currently envisioned fusion reactor systems will contain substantial quantities of tritium. Strict control of the overall tritium inventory and environmental safety considerations require an accurate knowledge of the behavior of this isotope in the presence of Controlled Thermonuclear Reactor (CTR) materials. A 14,000 ft 2 laboratory for tritium research is currently under construction at Sandia Laboratories in Livermore. Details about the laboratory in general are provided. Results from studies of hydrogen isotope diffusion in surface-characterized metals will be presented. Details of two permeation systems (one for hydrogen and deuterium, the other for tritium) will be discussed. Data will also be presented concerning the gettering of hydrogen isotopes and application to CTR collector designs. (auth)

  20. The Laboratories at Seibersdorf: Multi-disciplinary research and support centre

    International Nuclear Information System (INIS)

    Danesi, P.R.

    1987-01-01

    The main research activities performed at the IAEA laboratories at Seibersdorf in the Agriculture Laboratory, Physics-Chemistry-Instrumentation Laboratory and Safeguards Analytical Laboratory, as well as the training activities are briefly described

  1. Fuel enrichment reduction for heavy water moderated research reactors

    International Nuclear Information System (INIS)

    McCulloch, D.B.

    1984-01-01

    Twelve heavy-water-moderated research reactors of significant power level (5 MW to 125 MW) currently operate in a number of countries, and use highly enriched uranium (HEU) fuel. Most of these reactors could in principle be converted to use uranium of lower enrichment, subject in some cases to the successful development and demonstration of new fuel materials and/or fuel element designs. It is, however, generally accepted as desirable that existing fuel element geometry be retained unaltered to minimise the capital costs and licensing difficulties associated with enrichment conversion. The high flux Australian reactor, HIFAR, at Lucas Heights, Sydney is one of 5 Dido-class reactors in the above group. It operates at 10 MW using 80% 235 U HEU fuel. Theoretical studies of neutronic, thermohydraulic and operational aspects of converting HIFAR to use fuels of reduced enrichment have been made over a period. It is concluded that with no change of fuel element geometry and no penalty in the present HEU fuel cycle burn-up performance, conversion to MEU (nominally 45% 235 U) would be feasible within the limits of current fully qualified U-Al fuel materials technology. There would be no significant, adverse effects on safety-related parameters (e.g. reactivity coefficients) and only small penalties in reactor flux. Conversion to LEU (nominally 20% 235 U) a similar basis would require that fuel materials of about 2.3 g U cm -3 be fully qualified, and would depress the in-core thermal neutron flux by about 15 per cent relative to HEU fuelling. In qualitative terms, similar conclusions would be expected to hold for a majority of the above heavy water moderated reactors. (author)

  2. D and D of a plutonium research laboratory and related auxiliary systems

    International Nuclear Information System (INIS)

    Diaz Arocas, P.; Martinez Ortega, A.; Sama Colao, J.; Garcia Diaz, A.; Torre Rodriguez, J.; Diaz Diaz, J.L.; Argiles, E.; Garrido, C.

    2010-01-01

    CIEMAT, former Junta de Energia Nuclear (JEN) started nuclear research at the 60. decade, focussed on the development of pacific uses of Nuclear Energy. At that time, CIEMAT research and pilot plants developed involved the whole nuclear fuel cycle steps. It means from the uranium recovery to the spent fuel reprocessing. With this scope a plutonium research laboratory was constructed and operated from 1961 to the 90's focussed on chemistry of plutonium studies, separation processes and radiochemical analyses, in order to assist the working pilot plants at the Centre. Thereafter, as the result of the changes on the research objectives of CIEMAT, the plutonium laboratory suffered several modifications and finally it was safety stopped due to the obsolescence of its equipments and auxiliary systems. Present paper shows the D and D activities performed and techniques developed to avoid alpha emitter contamination. In every dismantling phase there were established the measures of operational radiological protection adapted to the radiological risk. Dosimetric controls realized during dismantlement showed that incorporation of radionuclides was not detected. Radiological final control was performed applying the derived levels of declassification to request the installation decommissioning. (authors)

  3. Basic research and industrialization of CANDU advanced fuel

    Energy Technology Data Exchange (ETDEWEB)

    Chun, Suk Ho; Park, Joo Hwan; Jun, Ji Su [and others

    2000-04-01

    handling, the preliminary evaluation of the CANFLEX-RU economics and some specification and description for the irradiation test of the CANFLEX-RU fuel NRU research reactor.

  4. Basic research and industrialization of CANDU advanced fuel

    International Nuclear Information System (INIS)

    Chun, Suk Ho; Park, Joo Hwan; Jun, Ji Su

    2000-04-01

    handling, the preliminary evaluation of the CANFLEX-RU economics and some specification and description for the irradiation test of the CANFLEX-RU fuel NRU research reactor

  5. Underlying chemistry research for the nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Torgerson, D.F.; Sagert, N.H.; Shoesmith, D.W.; Taylor, P.

    1984-04-01

    This document reviews the underlying chemistry research part of the Canadian Nuclear Fuel Waste Management Program, carried out in the Research Chemistry Branch. This research is concerned with developing the basic chemical knowledge and under-standing required in other parts of the Program. There are four areas of underlying research: Waste Form Chemistry, Solute and Solution Chemistry, Rock-Water-Waste Interactions, and Abatement and Monitoring of Gas-Phase Radionuclides

  6. Laboratory Directed Research and Development FY2011 Annual Report

    International Nuclear Information System (INIS)

    Craig, W.; Sketchley, J.; Kotta, P.

    2012-01-01

    A premier applied-science laboratory, Lawrence Livermore National Laboratory (LLNL) has earned the reputation as a leader in providing science and technology solutions to the most pressing national and global security problems. The LDRD Program, established by Congress at all DOE national laboratories in 1991, is LLNL's most important single resource for fostering excellent science and technology for today's needs and tomorrow's challenges. The LDRD internally directed research and development funding at LLNL enables high-risk, potentially high-payoff projects at the forefront of science and technology. The LDRD Program at Livermore serves to: (1) Support the Laboratory's missions, strategic plan, and foundational science; (2) Maintain the Laboratory's science and technology vitality; (3) Promote recruiting and retention; (4) Pursue collaborations; (5) Generate intellectual property; and (6) Strengthen the U.S. economy. Myriad LDRD projects over the years have made important contributions to every facet of the Laboratory's mission and strategic plan, including its commitment to nuclear, global, and energy and environmental security, as well as cutting-edge science and technology and engineering in high-energy-density matter, high-performance computing and simulation, materials and chemistry at the extremes, information systems, measurements and experimental science, and energy manipulation. A summary of each project was submitted by the principal investigator. Project summaries include the scope, motivation, goals, relevance to DOE/NNSA and LLNL mission areas, the technical progress achieved in FY11, and a list of publications that resulted from the research. The projects are: (1) Nuclear Threat Reduction; (2) Biosecurity; (3) High-Performance Computing and Simulation; (4) Intelligence; (5) Cybersecurity; (6) Energy Security; (7) Carbon Capture; (8) Material Properties, Theory, and Design; (9) Radiochemistry; (10) High-Energy-Density Science; (11) Laser Inertial

  7. Safety research in nuclear fuel cycle at PNC

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This report collects the results of safety research in nuclear fuel cycle at Power Reactor and Nuclear Fuel Development Corporation, in order to answer to the Questionnaire of OECD/NEA. The Questionnaire request to include information concerning to research topic, description, main results (if available), reference documents, research institutes involved, sponsoring organization and other pertinent information about followings: a) Recently completed research projects. b) Ongoing (current) research projects. Achievements on following items are omitted by the request of OECD/NEA, uranium mining and milling, uranium refining and conversion to UF{sub 6}, uranium enrichment, fuel manufacturers, spent fuel storage, radioactive waste management, transport of radioactive materials, decommissioning. We select topics from the fields of a) nuclear installation, b) seismic, and c) PSA, in projects from frame of annual safety research plan for nuclear installations established by Nuclear Safety Commission. We apply for the above a) and b) projects as follows: a) Achievements in Safety Research, fiscal 1991-1995, b) fiscal 1996 Safety Research Achievements: Progress. (author)

  8. Safety research in nuclear fuel cycle at PNC

    International Nuclear Information System (INIS)

    1998-09-01

    This report collects the results of safety research in nuclear fuel cycle at Power Reactor and Nuclear Fuel Development Corporation, in order to answer to the Questionnaire of OECD/NEA. The Questionnaire request to include information concerning to research topic, description, main results (if available), reference documents, research institutes involved, sponsoring organization and other pertinent information about followings: a) Recently completed research projects. b) Ongoing (current) research projects. Achievements on following items are omitted by the request of OECD/NEA, uranium mining and milling, uranium refining and conversion to UF 6 , uranium enrichment, fuel manufacturers, spent fuel storage, radioactive waste management, transport of radioactive materials, decommissioning. We select topics from the fields of a) nuclear installation, b) seismic, and c) PSA, in projects from frame of annual safety research plan for nuclear installations established by Nuclear Safety Commission. We apply for the above a) and b) projects as follows: a) Achievements in Safety Research, fiscal 1991-1995, b) fiscal 1996 Safety Research Achievements: Progress. (author)

  9. Nuclear fuels technologies fiscal year 1996 research and research development test results

    International Nuclear Information System (INIS)

    Beard, C.A.; Blair, H.T.; Buksa, J.J.; Butt, D.P.

    1996-01-01

    During fiscal year 1996, the Department of Energy's Office of Fissile Materials Disposition (OFMD) funded Los Alamos National Laboratory (LANL) to investigate issues associated with the fabrication of plutonium from dismantled weapons into mixed-oxide (MOX) nuclear fuel for disposition in nuclear power reactors. These issues can be divided into two main categories: issues associated with the fact that the plutonium from dismantled weapons contains gallium, and issues associated with the unique characteristics of the PuO 2 produced by the dry conversion process that OFMD is proposing to convert the weapons material. Initial descriptions of the experimental work performed in fiscal year 1996 to address these issues can be found in Nuclear Fuels Technologies Fiscal Year 1996 Research and Development Test Matrices'. However, in some instances the change in programmatic emphasis towards the Parallex program either altered the manner in which some of these experiments were performed (i.e., the work was done as part of the Parallex fabrication development and not as individual separate-effects tests as originally envisioned) or delayed the experiments into Fiscal Year 1997. This report reviews the experiments that were conducted and presents the results. 7 figs., 14 tabs

  10. Annual report on operation, utilization and technical development of Research Reactors and Hot Laboratory, from April 1, 1983 to March 31, 1984

    International Nuclear Information System (INIS)

    1984-11-01

    Activities of the Department of Research Reactor Operation in fiscal year 1983 are described. The department is responsible for operation and maintenance of JRR-2, JRR-3, JRR-4 and Hot Laboratory. In the above connection, various other work has also been performed, such as technical management of fuel and coolant, radiation control, irradiation technique, etc. In Hot Laboratory, we have performed post-irradiation examinations of fuels and materials, and also development of examination procedures, too. (author)

  11. Status of Avian Research at the National Renewable Energy Laboratory

    International Nuclear Information System (INIS)

    Sinclair, K.

    2001-01-01

    As the use of wind energy expands across the United States, concerns about the impacts of commercial wind farms on bird and bat populations are frequently raised. Two primary areas of concern are (1) possible litigation resulting from the killing of even one bird if it is protected by the Migratory Bird Treaty Act, the Endangered Species Act, or both; and (2) the effect of avian mortality on bird populations. To properly address these concerns, the U.S. Department of Energy's National Renewable Energy Laboratory (NREL) supports scientifically based avian/wind power interaction research. In this paper I describe NREL's field-based research projects and summarize the status of the research. I also summarize NREL's other research activities, including lab-based vision research to increase the visibility of moving turbine blades and avian acoustic research, as well as our collaborative efforts with the National Wind Coordinating Committee's Avian Subcommittee

  12. Research on assurance system of nuclear fuel supply (Contract research)

    International Nuclear Information System (INIS)

    Kobayashi, Naoki; Naoi, Yosuke; Wakabayashi, Shuji; Tazaki, Makiko; Senzaki, Masao

    2010-03-01

    Assurance of supply (AOS) of nuclear fuel is a special arrangement in case of nuclear fuel supply disruption caused by political reasons other than nonproliferation. It aims to support a stable supply of nuclear fuel while avoiding unnecessary spread of sensitive enrichment technology. Current discussions on AOS have been initiated by the IAEA Director-General's article published in The Economist entitled 'Towards a Safer World' Oct. 2003. Since then, various proposals on AOS have been presented. In order to facilitate international discussions on AOS, authors have conducted studies of AOS system based on Japanese Government's proposal 'IAEA Standby Arrangement System (INFCIRC/683)'. In this paper, we gave an overview of discussions on AOS since World War II, and elaborated on some of current proposals. We have been able to discuss feasibility of AOS system more specifically by including additional costs and period required for AOS, and to present a system which could work as a practical system. Issues we have tried to tackle here include definitions of AOS, and roles of consumer states, supplier states, IAEA and nuclear industries. We present some solutions including broadening coverage of AOS, declaration by supplier states on AOS, establishing advisory committee in the IAEA on the actual application of AOS, and setting up an IAEA fund for AOS. (author)

  13. Research on assurance system of nuclear fuel supply (Contract research)

    International Nuclear Information System (INIS)

    Kobayashi, Naoki; Naoi, Yosuke; Wakabayashi, Shuji; Tazaki, Makiko; Senzaki, Masao

    2010-08-01

    Assurance of supply (AOS) of nuclear fuel is a special arrangement in case of nuclear fuel supply disruption caused by political reasons other than nonproliferation. It aims to support a stable supply of nuclear fuel while avoiding spread of sensitive enrichment technology. Current discussions on AOS have been initiated by the IAEA Director-General's article published in The Economist entitled 'Towards a Safer World' Oct. 2003. Since then, various proposals on AOS have been presented. In order to facilitate international discussions on AOS, authors have conducted studies of AOS system based on Japanese Government's proposal 'IAEA Standby Arrangement System (INFCIRC/683)'. In this paper, we have been able to discuss feasibility of AOS system more specifically by including additional costs and period required for AOS, and to present a system which could work as a practical system. Issues we have tried to tackle here include definitions of AOS, and roles of consumer States, supplier States, IAEA and nuclear industries. We present some solutions including broadening coverage of AOS, declaration by supplier States on AOS, establishing advisory committee in the IAEA on the actual application of AOS, and setting up an IAEA fund for AOS. (author)

  14. Georgia Teachers in Academic Laboratories: Research Experiences in the Geosciences

    Science.gov (United States)

    Barrett, D.

    2005-12-01

    The Georgia Intern-Fellowships for Teachers (GIFT) is a collaborative effort designed to enhance mathematics and science experiences of Georgia teachers and their students through summer research internships for teachers. By offering business, industry, public science institute and research summer fellowships to teachers, GIFT provides educators with first-hand exposure to the skills and knowledge necessary for the preparation of our future workforce. Since 1991, GIFT has placed middle and high school mathematics, science and technology teachers in over 1000 positions throughout the state. In these fellowships, teachers are involved in cutting edge scientific and engineering research, data analysis, curriculum development and real-world inquiry and problem solving, and create Action Plans to assist them in translating the experience into changed classroom practice. Since 2004, an increasing number of high school students have worked with their teachers in research laboratories. The GIFT program places an average of 75 teachers per summer into internship positions. In the summer of 2005, 83 teachers worked in corporate and research environments throughout the state of Georgia and six of these positions involved authentic research in geoscience related departments at the Georgia Institute of Technology, including aerospace engineering and the earth and atmospheric sciences laboratories. This presentation will review the history and the structure of the program including the support system for teachers and mentors as well as the emphasis on inquiry based learning strategies. The focus of the presentation will be a comparison of two placement models of the teachers placed in geoscience research laboratories: middle school earth science teachers placed in a 6 week research experience and high school teachers placed in 7 week internships with teams of 3 high school students. The presentation will include interviews with faculty to determine the value of these experiences

  15. Laboratory Directed Research and Development Program FY2004

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, Todd C.

    2005-03-22

    The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab or LBNL) is a multi-program national research facility operated by the University of California for the Department of Energy (DOE). As an integral element of DOE's National Laboratory System, Berkeley Lab supports DOE's missions in fundamental science, energy resources, and environmental quality. Berkeley Lab programs advance four distinct goals for DOE and the nation: (1) To perform leading multidisciplinary research in the computing sciences, physical sciences, energy sciences, biosciences, and general sciences in a manner that ensures employee and public safety and protection of the environment. (2) To develop and operate unique national experimental facilities for qualified investigators. (3) To educate and train future generations of scientists and engineers to promote national science and education goals. (4) To transfer knowledge and technological innovations and to foster productive relationships among Berkeley Lab's research programs, universities, and industry in order to promote national economic competitiveness. Berkeley Lab's research and the Laboratory Directed Research and Development (LDRD) program support DOE's Strategic Goals that are codified in DOE's September 2003 Strategic Plan, with a primary focus on Advancing Scientific Understanding. For that goal, the Fiscal Year (FY) 2004 LDRD projects support every one of the eight strategies described in the plan. In addition, LDRD efforts support the goals of Investing in America's Energy Future (six of the fourteen strategies), Resolving the Environmental Legacy (four of the eight strategies), and Meeting National Security Challenges (unclassified fundamental research that supports stockpile safety and nonproliferation programs). The LDRD supports Office of Science strategic plans, including the 20 year Scientific Facilities Plan and the draft Office of Science Strategic Plan. The research also

  16. Argonne National Laboratory annual report of Laboratory Directed Research and Development Program Activities FY 2009.

    Energy Technology Data Exchange (ETDEWEB)

    Office of the Director

    2010-04-09

    I am pleased to submit Argonne National Laboratory's Annual Report on its Laboratory Directed Research and Development (LDRD) activities for fiscal year 2009. Fiscal year 2009 saw a heightened focus by DOE and the nation on the need to develop new sources of energy. Argonne scientists are investigating many different sources of energy, including nuclear, solar, and biofuels, as well as ways to store, use, and transmit energy more safely, cleanly, and efficiently. DOE selected Argonne as the site for two new Energy Frontier Research Centers (EFRCs) - the Institute for Atom-Efficient Chemical Transformations and the Center for Electrical Energy Storage - and funded two other EFRCs to which Argonne is a major partner. The award of at least two of the EFRCs can be directly linked to early LDRD-funded efforts. LDRD has historically seeded important programs and facilities at the lab. Two of these facilities, the Advanced Photon Source and the Center for Nanoscale Materials, are now vital contributors to today's LDRD Program. New and enhanced capabilities, many of which relied on LDRD in their early stages, now help the laboratory pursue its evolving strategic goals. LDRD has, since its inception, been an invaluable resource for positioning the Laboratory to anticipate, and thus be prepared to contribute to, the future science and technology needs of DOE and the nation. During times of change, LDRD becomes all the more vital for facilitating the necessary adjustments while maintaining and enhancing the capabilities of our staff and facilities. Although I am new to the role of Laboratory Director, my immediate prior service as Deputy Laboratory Director for Programs afforded me continuous involvement in the LDRD program and its management. Therefore, I can attest that Argonne's program adhered closely to the requirements of DOE Order 413.2b and associated guidelines governing LDRD. Our LDRD program management continually strives to be more efficient. In

  17. Argonne National Laboratory annual report of Laboratory Directed Research and Development Program Activities FY 2009

    International Nuclear Information System (INIS)

    2010-01-01

    I am pleased to submit Argonne National Laboratory's Annual Report on its Laboratory Directed Research and Development (LDRD) activities for fiscal year 2009. Fiscal year 2009 saw a heightened focus by DOE and the nation on the need to develop new sources of energy. Argonne scientists are investigating many different sources of energy, including nuclear, solar, and biofuels, as well as ways to store, use, and transmit energy more safely, cleanly, and efficiently. DOE selected Argonne as the site for two new Energy Frontier Research Centers (EFRCs) - the Institute for Atom-Efficient Chemical Transformations and the Center for Electrical Energy Storage - and funded two other EFRCs to which Argonne is a major partner. The award of at least two of the EFRCs can be directly linked to early LDRD-funded efforts. LDRD has historically seeded important programs and facilities at the lab. Two of these facilities, the Advanced Photon Source and the Center for Nanoscale Materials, are now vital contributors to today's LDRD Program. New and enhanced capabilities, many of which relied on LDRD in their early stages, now help the laboratory pursue its evolving strategic goals. LDRD has, since its inception, been an invaluable resource for positioning the Laboratory to anticipate, and thus be prepared to contribute to, the future science and technology needs of DOE and the nation. During times of change, LDRD becomes all the more vital for facilitating the necessary adjustments while maintaining and enhancing the capabilities of our staff and facilities. Although I am new to the role of Laboratory Director, my immediate prior service as Deputy Laboratory Director for Programs afforded me continuous involvement in the LDRD program and its management. Therefore, I can attest that Argonne's program adhered closely to the requirements of DOE Order 413.2b and associated guidelines governing LDRD. Our LDRD program management continually strives to be more efficient. In addition to

  18. Laboratory directed research and development program FY 1999

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, Todd; Levy, Karin

    2000-03-08

    The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab or LBNL) is a multi-program national research facility operated by the University of California for the Department of Energy (DOE). As an integral element of DOE's National Laboratory System, Berkeley Lab supports DOE's missions in fundamental science, energy resources, and environmental quality. Berkeley Lab programs advance four distinct goals for DOE and the nation: (1) To perform leading multidisciplinary research in the computing sciences, physical sciences, energy sciences, biosciences, and general sciences in a manner that ensures employee and public safety and protection of the environment. (2) To develop and operate unique national experimental facilities for qualified investigators. (3) To educate and train future generations of scientists and engineers to promote national science and education goals. (4) To transfer knowledge and technological innovations and to foster productive relationships among Berkeley Lab's research programs, universities, and industry in order to promote national economic competitiveness. This is the annual report on Laboratory Directed Research and Development (LDRD) program for FY99.

  19. Laboratory Directed Research and Development Program FY 2001

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, Todd; Levy, Karin

    2002-03-15

    The Ernest Orlando Lawrence Berkeley National Laboratory (Berkeley Lab or LBNL) is a multi-program national research facility operated by the University of California for the Department of Energy (DOE). As an integral element of DOE's National Laboratory System, Berkeley Lab supports DOE's missions in fundamental science, energy resources, and environmental quality. Berkeley Lab programs advance four distinct goals for DOE and the nation: (1) To perform leading multidisciplinary research in the computing sciences, physical sciences, energy sciences, biosciences, and general sciences in a manner that ensures employee and public safety and protection of the environment. (2) To develop and operate unique national experimental facilities for qualified investigators. (3) To educate and train future generations of scientists and engineers to promote national science and education goals. (4) To transfer knowledge and technological innovations and to foster productive relationships among Berkeley Lab's research programs, universities, and industry in order to promote national economic competitiveness. This is the annual report on Laboratory Directed Research and Development (LDRD) program for FY01.

  20. DESALINATION AND WATER TREATMENT RESEARCH AT SANDIA NATIONAL LABORATORIES.

    Energy Technology Data Exchange (ETDEWEB)

    Rigali, Mark J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Miller, James E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Altman, Susan J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Biedermann, Laura [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Brady, Patrick Vane. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Kuzio, Stephanie P. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Nenoff, Tina M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Rempe, Susan [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-11-01

    Water is the backbone of our economy - safe and adequate supplies of water are vital for agriculture, industry, recreation, and human consumption. While our supply of water today is largely safe and adequate, we as a nation face increasing water supply challenges in the form of extended droughts, demand growth due to population increase, more stringent health-based regulation, and competing demands from a variety of users. To meet these challenges in the coming decades, water treatment technologies, including desalination, will contribute substantially to ensuring a safe, sustainable, affordable, and adequate water supply for the United States. This overview documents Sandia National Laboratories' (SNL, or Sandia) Water Treatment Program which focused on the development and demonstration of advanced water purification technologies as part of the larger Sandia Water Initiative. Projects under the Water Treatment Program include: (1) the development of desalination research roadmaps (2) our efforts to accelerate the commercialization of new desalination and water treatment technologies (known as the 'Jump-Start Program),' (3) long range (high risk, early stage) desalination research (known as the 'Long Range Research Program'), (4) treatment research projects under the Joint Water Reuse & Desalination Task Force, (5) the Arsenic Water Technology Partnership Program, (6) water treatment projects funded under the New Mexico Small Business Administration, (7) water treatment projects for the National Energy Technology Laboratory (NETL) and the National Renewable Energy Laboratory (NREL), (8) Sandia- developed contaminant-selective treatment technologies, and finally (9) current Laboratory Directed Research and Development (LDRD) funded desalination projects.

  1. Field tracer transport experiments at the site of Canada's underground research laboratory

    International Nuclear Information System (INIS)

    Frost, L.H.; Davison, C.C.; Vandergraaf, T.T.; Scheier, N.W.; Kozak, E.T.

    1997-01-01

    To gain a better understanding of the processes affecting solute transport in fractured crystalline rock, groundwater tracer experiments are being performed within natural fracture domains and excavation damage zones at various scales at the site of AECL's Underground Research Laboratory (URL). The main objective of these experiments is to develop and demonstrate methods for characterizing the solute transport properties within fractured crystalline rock. Estimates of these properties are in turn being used in AECL's conceptual and numerical models of groundwater flow and solute transport through the geosphere surrounding a nuclear fuel waste disposal vault in plutonic rock of the Canadian Shield. (author)

  2. HANARO Neutron Radiography Facility and Fuel Cell Research

    International Nuclear Information System (INIS)

    Kim, Taejoo

    2013-01-01

    Fuel cell which generates electric energy from hydrogen and oxygen is one of noticed renewable energy system because this has high efficiency and free from CO 2 . Especially, PEMFC (Polymer Electrolyte Membrane Fuel Cell) is focused by automotive companies because PEMFC, which has high power rate per volume and low operating temperature (60∼80), is suited due to the compact design and short start-up time. The water management is one of the most critical issues for fuel cell commercialization. In order to make a proper scheme for water management, thein formation of water distribution and behavior is very important. Neutron imaging is the best method to visualize the water at fuel cell and has been applied worldwide with qualitative and quantitative results. Because the NRF has large beam size (350Χ450mm 2 ) and relatively high neutron flux (2Χ107 n/cm 2 sec), it is suitable for large scale fuel cell research. Neutron imaging technique was used to investigate the water distribution and behavior in PEMFC under different operating conditions. The NRF has contributed the improvement of fuel cell performance and is one of the best choices for fuel cell study

  3. New In-pile Instrumentation to Support Fuel Cycle Research and Development

    Energy Technology Data Exchange (ETDEWEB)

    J. Rempe; H. MacLean; R. Schley; D. Hurley; J. Daw; S. Taylor; J. Smith; J. Svoboda; D. Kotter; D. Knudson; M. Guers; S. C. Wilkins

    2011-01-01

    New and enhanced nuclear fuels are a key enabler for new and improved reactor technologies. For example, the goals of the next generation nuclear plant (NGNP) will not be met without irradiations successfully demonstrating the safety and reliability of new fuels. Likewise, fuel reliability has become paramount in ensuring the competitiveness of nuclear power plants. Recently, the Office of Nuclear Energy in the Department of Energy (DOE-NE) launched a new direction in fuel research and development that emphasizes an approach relying on first principle models to develop optimized fuel designs that offer significant improvements over current fuels. To facilitate this approach, high fidelity, real-time, data are essential for characterizing the performance of new fuels during irradiation testing. A three-year strategic research program is proposed for developing the required test vehicles with sensors of unprecedented accuracy and resolution for obtaining the data needed to characterize three-dimensional changes in fuel microstructure during irradiation testing. When implemented, this strategy will yield test capsule designs that are instrumented with new sensor technologies for the Advanced Test Reactor (ATR) and other irradiation locations for the Fuel Cycle Research and Development (FC R&D) program. Prior laboratory testing, and as needed, irradiation testing, of these sensors will have been completed to give sufficient confidence that the irradiation tests will yield the required data. Obtaining these sensors must draw upon the expertise of a wide-range of organizations not currently supporting nuclear fuels research. This document defines this strategic program and provides the necessary background information related to fuel irradiation testing, desired parameters for detection, and an overview of currently available in-pile instrumentation. In addition, candidate sensor technologies are identified in this document, and a list of proposed criteria for ranking

  4. 2016 Fermilab Laboratory Directed Research & Development Program Plan

    Energy Technology Data Exchange (ETDEWEB)

    Wester, W. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States)

    2016-05-25

    Fermilab is executing Laboratory Directed Research and Development (LDRD) as outlined by order DOE O 413.2B in order to enhance and realize the mission of the laboratory in a manner that also supports the laboratory’s strategic objectives and the mission of the Department of Energy. LDRD funds enable scientific creativity, allow for exploration of “high risk, high payoff” research, and allow for the demonstration of new ideas, technical concepts, and devices. LDRD also has an objective of maintaining and enhancing the scientific and technical vitality of Fermilab. LDRD is able to fund employee-initiated proposals that address the current strategic objectives and better position Fermilab for future mission needs. The request for such funds is made in consideration of the investment needs, affordability, and directives from DOE and Congress. Review procedures of the proposals will insure that those proposals which most address the strategic goals of the DOE and the Laboratory or which best position Fermilab for the future will be recommended to the Laboratory Director who has responsibility for approval. The execution of each approved project will be the responsibility of the Principal Investigator, PI, who will follow existing Laboratory guidelines to ensure compliance with safety, environmental, and quality assurance practices. A Laboratory Director-appointed LDRD Coordinator will work with Committees, Laboratory Management, other Fermilab Staff, and the PI’s to oversee the implementation of policies and procedures of LDRD and provide the management and execution of this Annual Program Plan. FY16 represents third fiscal year in which LDRD has existed at Fermilab. The number of preliminary proposals (117) submitted in response to the LDRD Call for Proposals indicates very strong interest of the program within the Fermilab community. The first two Calls have resulted in thirteen active LDRD projects – and it is expected that between five and seven new

  5. Research on a Scania 11 liter ethanol fueled bus engine

    Energy Technology Data Exchange (ETDEWEB)

    Egebaeck, K E; Pettersson, E

    1996-05-01

    This report presents research carried out on an alcohol fueled bus engine. The engine used was a six cylinder 11 liter compression ignition turbo-charged engine with an inter cooler. The research program included studies of the impact on the emissions when changing different engine components and different settings of the engine. A study of the impact on the engine performance and emissions when using different fuel compositions was also carried out. During the course of the work, the engine was equipped with oxidation catalysts of two different types, one of which was more efficient than the other concerning the oxidation of unburnt fuel related components. One of the main purposes of the research was to improve the emission characteristics of the engine by an optimization of the engine and its setting. The exhaust emissions were thoroughly characterized with respect to both regulated and unregulated emissions. 13 refs, figs, tabs

  6. Environmental survey at Lucas Heights Research Laboratories, 1993

    International Nuclear Information System (INIS)

    Hoffmann, E.L.; Looz, T.

    1995-04-01

    Results are presented of the environmental survey conducted in the neighbourhood of the Lucas Heights Research Laboratories during 1993. No activity which could have originated from these laboratories was found in samples collected from possible human food chains. All low-level liquid and gaseous waste discharges were within authorised limits. The maximum possible annual dose to the general public from airborne discharges during this period is estimated to be less than 0.01 mSv, which is one per cent of the dose limit for long term exposure that is recommended by the National Health and Medical Research Council. A list of previous environmental survey reports is attached. 22 refs., 21 tabs., 4 figs

  7. Eighteenth annual risk reduction engineering laboratory research symposium

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    The Eighteenth Annual Risk Reduction Engineering Laboratory Research Symposium was held in Cincinnati, Ohio, April 14-16, 1992. The purpose of this Symposium was to present the latest significant research findings from ongoing and recently completed projects funded by the Risk Reduction Engineering Laboratory (RREL). These Proceedings are organized into two sections. Sessions A and B, which contain extended abstracts of the paper presentations. A list of poster displays is also included. Subjects include remedial action, treatment, and control technologies for waste disposal, landfill liner and cover systems, underground storage tanks, and demonstration and development of innovative/alternative treatment technologies for hazardous waste. Alternative technology subjects include thermal destruction of hazardous wastes, field evaluations, existing treatment options, emerging treatment processes, waste minimization, and biosystems for hazardous waste destruction

  8. Virtual Laboratory Enabling Collaborative Research in Applied Vehicle Technologies

    Science.gov (United States)

    Lamar, John E.; Cronin, Catherine K.; Scott, Laura E.

    2005-01-01

    The virtual laboratory is a new technology, based on the internet, that has had wide usage in a variety of technical fields because of its inherent ability to allow many users to participate simultaneously in instruction (education) or in the collaborative study of a common problem (real-world application). The leadership in the Applied Vehicle Technology panel has encouraged the utilization of this technology in its task groups for some time and its parent organization, the Research and Technology Agency, has done the same for its own administrative use. This paper outlines the application of the virtual laboratory to those fields important to applied vehicle technologies, gives the status of the effort, and identifies the benefit it can have on collaborative research. The latter is done, in part, through a specific example, i.e. the experience of one task group.

  9. Research and development of nitride fuel cycle technology in Europe

    International Nuclear Information System (INIS)

    Wallenius, Janne

    2004-01-01

    Research and development on nitride fuels for minor actinide burning in accelerator driven systems is performed in Europe in context of the CONFIRM project. Dry and wet methods for fabrication of uranium free nitride fuels have been developed with the assistance of thermo-chemical modelling. Four (Pu, Zr) pins have been fabricated by PSI and will be irradiated in Studsvik at a rating of 40-50 kW/m. The thermal conductivity of (Pu, Zr)N has been measured and was found to be in agreement with earlier theoretical assessments. Safety modeling indicates that americium bearing nitride fuels, in spite of their relatively poor high temperature stability under atmospheric pressure, can survive power transients as long as the fuel cladding remains intact. (author)

  10. Nuclear criticality assessment of Oak Ridge research fuel element storage

    International Nuclear Information System (INIS)

    Thomas, J.T.

    1978-06-01

    Spent and partially spent Oak Ridge Research Reactor (ORR) fuel elements are retained in the storage section of the ORR pool facility. Determination of a maximum expected neutron multiplication factor for the storage area is accomplished by a validated calculational method. The KENO Monte Carlo code and the Hansen-Roach 16-group neutron cross section sets were validated by calculations of critical experiments performed with early ORR fuel elements and with SPERT-D fuel elements. Calculations of various fuel element arrangements are presented which confirm the subcriticality previously inferred from critical experiments and indicate the k/sub eff/ would not exceed 0.85, were the storage area to be filled to capacity with storage racks containing elements with the fissionable material loading increased to 350 g of 235 U

  11. Annual report 1984. Nuclear fuel research department

    International Nuclear Information System (INIS)

    Nebel, D.

    1985-12-01

    Research activities have been reviewed in the field of powder metallurgy and the production of new ceramic materials in particular silicon nitrides. Communications on the chemistry of solutions and the analytical chemistry have been compiled specially under the aspect of technical solutions and the development of new devices, equipments and methods. In a final chapter publications and lectures are assorted

  12. ENS RRFM 2005: 9th international topical meeting on research reactor fuel management. Transactions

    International Nuclear Information System (INIS)

    2005-01-01

    The ENS topical meeting on research reactor fuel management is an annual conference launched successfully in 1997. It has since then grown into well established international forum for the exchange and expertise on all significant aspects of the nuclear fuel cycle of research reactors. Oral presentations at this meeting were divided in the following four sessions: International Topics; Fuel Development, Qualification, Fabrication and Licensing; Reactor Operation, Fuel Safety and Core Conversion; Spent Fuel Management, Back-end Options, Transportation. The three poster sessions were devoted to fuel development, qualification, fabrication and licensing; reactor operation, fuel safety, core conversion, spent fuel; spent fuel management, fuel cycle back-end options, transportation

  13. Federal laboratory nondestructive testing research and development applicable to industry

    Energy Technology Data Exchange (ETDEWEB)

    Smith, S.A.; Moore, N.L.

    1987-02-01

    This document presents the results of a survey of nondestructive testing (NDT) and related sensor technology research and development (R and D) at selected federal laboratories. Objective was to identify and characterize NDT activities that could be applied to improving energy efficiency and overall productivity in US manufacturing. Numerous federally supported R and D programs were identified in areas such as acoustic emissions, eddy current, radiography, computer tomography and ultrasonics. A Preliminary Findings Report was sent to industry representatives, which generated considerable interest.

  14. Laboratory directed research and development FY91. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, S.E.; Hedman, I.; Kirvel, R.D.; McGregor, C.K. [eds.

    1991-12-31

    This review of research programs at Lawrence Livermore National Laboratory is composed of individual papers on various subjects. Broad topics of interest are: chemistry and materials science, computation, earth sciences, engineering, nuclear physics, and physics, and biology. Director`s initiatives include the development of a transgenic mouse, accelerator mass spectrometry, high-energy physics detectors, massive parallel computing, astronomical telescopes, the Kuwaiti oil fires and a compact torus accelerator. (GHH)

  15. Air Force Research Laboratory Success Stories. A Review of 2003

    Science.gov (United States)

    2003-01-01

    or non-NBC mode. The ECU can act as either a heater or an air conditioner and can be operated with a remote control. Compared to previous models...separation system, PSC is developing a motorized activation mechanism. Once completed, this will allow for virtually unlimited testing of the actual...stories in this book or on the CD-ROM, or for other technical activities in the Air Force Research Laboratory, contact TECH CONNECT at (800) 203-6451

  16. Environmental Quality Laboratory Research Report, 1985-1987

    OpenAIRE

    Brooks, Norman H.

    1988-01-01

    The Environmental Quality Laboratory at Caltech is a center for research on large-scale systems problems of natural resources and environmental quality. The principal areas of investigation at EQL are: 1. Air quality management. 2. Water resources and water quality management. 3. Control of hazardous substances in the environment. 4. Energy policy, including regulation, conservation and energy-environment tradeoffs. 5. Resources policy (other than energy); residuals m...

  17. HTGR safety research at the Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Stroh, K.R.; Anderson, C.A.; Kirk, W.L.

    1982-01-01

    This paper summarizes activities undertaken at the Los Alamos National Laboratory as part of the High-Temperature Gas-Cooled Reactor (HTGR) Safety Research Program sponsored by the US Nuclear Regulatory Commission. Technical accomplishments and analysis capabilities in six broad-based task areas are described. These tasks are: fission-product technology, primary-coolant impurities, structural investigations, safety instrumentation and control systems, accident delineation, and phenomena modeling and systems analysis

  18. Mission of mediation on planting underground research laboratories

    International Nuclear Information System (INIS)

    Bataille, C.

    1994-01-01

    France, who chose to have a strong nuclear industry, is confronted to the problem of management, treatment, storage and elimination of radioactive waste. The law defined an important research program with a study of underground storage in laboratories. Here is the report of this mission. A problem of people confidence arose; there is a difference between the great level of science or technology and the level of understanding of public opinion. The only answer brought by a democratic society is to develop information

  19. Bulletin of the Research Laboratory for Nuclear Reactors

    International Nuclear Information System (INIS)

    Aritomi, Masanori

    2008-01-01

    The bulletin consists of two parts. The first part includes General Research Report. The Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology has three engineering divisions such as Energy Engineering, Mass Transmutation Engineering, and System and Safety Engineering. In this part, 17 reports of Energy Engineering division, 8 reports of Mass transmutation Engineering division, 11 reports of System and Safety Engineering division are described as their activities. In addition, 3 reports of Cooperative Researches are also summarized. The second part is Special Issue about COE-INES RESEARCH REPORT 2007. In this part, 3 reports of Innovative Reactor Group, 2 reports of Innovative Nuclear Energy Utilization System Group, 3 reports of Innovative Transmutation/Separation Group, 2 reports of Relationship between Nuclear and Society Group, 1 report of RA Students in the COE-INES Captainship Educational Program are described as results to their researches. (J.P.N.)

  20. 2014 Fermilab Laboratory Directoed Research & Development Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    Wester, W. [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States)

    2016-05-26

    After initiation by the Fermilab Laboratory Director, a team from the senior Laboratory leadership and a Laboratory Directed Research and Development (LDRD) Advisory Committee developed an implementation plan for LDRD at Fermilab for the first time. This implementation was captured in the approved Fermilab 2014 LDRD Program Plan and followed directions and guidance from the Department of Energy (DOE) order, DOE O 413.2B, a “Roles, Responsibilities, and Guidelines, …” document, and examples of best practices at other DOE Office of Science Laboratories. At Fermilab, a FY14 midyear Call for Proposals was issued. A LDRD Selection Committee evaluated those proposals that were received and provided a recommendation to the Laboratory Director who approved seven LDRD projects. This Annual Report focuses on the status of those seven projects and provides an overview of the current status of LDRD at Fermilab. The seven FY14 LDRD approved projects had a date of initiation late in FY14 such that this report reflects approximately six months of effort approximately through January 2015. The progress of these seven projects, the subsequent award of six additional new projects beginning in FY15, and preparations for the issuance of the FY16 Call for Proposals indicates that LDRD is now integrated into the overall annual program at Fermilab. All indications are that LDRD is improving the scientific and technical vitality of the Laboratory and providing new, novel, or cutting edge projects carried out at the forefront of science and technology and aligned with the mission and strategic visions of Fermilab and the Department of Energy.