WorldWideScience

Sample records for university researchers fuel

  1. The University of Missouri Research Reactor, its fuel and productivity

    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

    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. Transmutation research and fuel cycle (report on discussion at Research Reactor Institute, Kyoto University)

    Yamana, Hajimu

    1999-01-01

    A symposium was held on a topic of 'Transmutation Research' on Dec. 21 and 22, 1999 at Research Reactor Institute, Kyoto University. This meeting was held as a joint-meeting of KUR's specialist meeting and Tokyo University's activity supported by the Grant-in-Aid for Scientific Research of Ministry of Education, Sport and Culture of Japan. This paper describes the overview of the discussions of this joint-meeting, and interprets their significance. Major themes discussed are, needed discussions on the transmutation research, policy and concepts of the organizations doing transmutation researches, a view from university side, transmutation researches in the oversea countries, opinions from various standpoints of the nuclear fuel cycle, conclusive discussions. 'the meanings of the transmutation research should be discussed together with the geological disposal and fast reactor system', 'transmutation may be a cooperative option for the disposal, thus, they should not be in a independent relation', and Balance evaluation will be needed' are the examples of the conclusive remarks of this meeting. (author)

  4. Brief of the joint research with universities, etc. for 2002. Except the research by the JNC cooperative research scheme on the nuclear fuel cycle

    2003-09-01

    The Japan Nuclear Cycle Development Institute (JNC) promote the basic and fundamental research in relation to the research and development projects of JNC through collaboration with universities and other research institutes (referred to as 'universities, etc.' below). This report includes a summary of the results of the research carried out in fiscal year 2002 on 15 joint researches with universities, etc. In addition, this report removes the research by the JNC Cooperative Research Scheme on the Nuclear Fuel Cycle. (author)

  5. Fossil Fuel Industry Funding of Climate-Relevant Research at U.S. Universities

    Franta, B.; Supran, G.

    2017-12-01

    Commercial producers of lead, tobacco, petroleum, and other products have funded extensive scholarly research in ways designed to confuse the public about the dangers of those products and thwart regulation [1-3]. For example, strategy documentation of the U.S. oil and gas industry from the late 1990s describes using selective support for scientists as a strategy for creating an atmosphere of debate and uncertainty, with the ultimate goal of delaying and defeating climate policies [4]. In this context, we systematically examine current funding from commercial fossil fuel interests of climate-relevant research - such as energy technology and climate policy research - in U.S. universities. We quantify such funding using charitable giving databases, university websites, and other publicly available records. We find that, especially among the most influential universities, climate-related research programs are frequently dominated by funding from fossil fuel interests. Moreover, these relationships sometimes afford funders privileges including formal control over research directions. This work represents an advance in mapping the presence of commercial fossil fuel interests in academia and may contribute to discussions of appropriate funding systems for climate-relevant research. 1. Markowitz, G. and D. Rosner, Lead Wars: The Politics of Science and the Fate of America's Children. 1st ed. 2013: University of California Press. 2. Brandt, A.M., Inventing Conflicts of Interest: A History of Tobacco Industry Tactics. American Journal of Public Health, 2012. 102(1): p. 63-71. 3. Oreskes, N. and E.M. Conway, Merchants of Doubt: How a Handful of Scientists Obscured the Truth on Issues from Tobacco Smoke to Global Warming. 2011: Bloomsbury Press. 4. Walker, J., Global Climate Science Communications Action Plan. 1998. Workshop held at the headquarters of the American Petroleum Institute.

  6. Hydrogen fuel - Universal energy

    Prince, A. G.; Burg, J. A.

    The technology for the production, storage, transmission, and consumption of hydrogen as a fuel is surveyed, with the physical and chemical properties of hydrogen examined as they affect its use as a fuel. Sources of hydrogen production are described including synthesis from coal or natural gas, biomass conversion, thermochemical decomposition of water, and electrolysis of water, of these only electrolysis is considered economicially and technologically feasible in the near future. Methods of production of the large quantities of electricity required for the electrolysis of sea water are explored: fossil fuels, hydroelectric plants, nuclear fission, solar energy, wind power, geothermal energy, tidal power, wave motion, electrochemical concentration cells, and finally ocean thermal energy conversion (OTEC). The wind power and OTEC are considered in detail as the most feasible approaches. Techniques for transmission (by railcar or pipeline), storage (as liquid in underwater or underground tanks, as granular metal hydride, or as cryogenic liquid), and consumption (in fuel cells in conventional power plants, for home usage, for industrial furnaces, and for cars and aircraft) are analyzed. The safety problems of hydrogen as a universal fuel are discussed, noting that they are no greater than those for conventional fuels.

  7. The Outlook for Low-Grade Fuels in Tomsk Region: Research Experience at Tomsk Polytechnic University

    Khaustov Sergei A.

    2016-01-01

    Full Text Available The urgency of the discussed issue is caused by the need to substitute in the regional fuel-energy balances imported energy resources with local low-grade fuels. The main aim of the study is to estimate thermal properties of local fuels in Tomsk region and evaluate its energy use viability. The methods used in the study were based standard GOST 52911-2008, 11022-95 and 6382-2001, by means of a bomb calorimeter ABK-1 and Vario micro cube analyzer. The mineral ash of researched fuels was studied agreeing with GOST 10538-87. The results state the fact that discussed low-grade fuels of Tomsk region in the unprepared form are not able to replace imported coal in regional energy balance, because of the high moisture and ash content values. A promosing direction of a low-temperature fue processing is a catalytic converter, which allows receiving hydrogen-enriched syngas from the initial solid raw.

  8. Development of a practical Monte Carlo based fuel management system for the Penn State University Breazeale Research Reactor (PSBR)

    Tippayakul, Chanatip; Ivanov, Kostadin; Frederick Sears, C.

    2008-01-01

    A practical fuel management system for the he Pennsylvania State University Breazeale Research Reactor (PSBR) based on the advanced Monte Carlo methodology was developed from the existing fuel management tool in this research. Several modeling improvements were implemented to the old system. The improved fuel management system can now utilize the burnup dependent cross section libraries generated specifically for PSBR fuel and it is also able to update the cross sections of these libraries by the Monte Carlo calculation automatically. Considerations were given to balance the computation time and the accuracy of the cross section update. Thus, certain types of a limited number of isotopes, which are considered 'important', are calculated and updated by the scheme. Moreover, the depletion algorithm of the existing fuel management tool was replaced from the predictor only to the predictor-corrector depletion scheme to account for burnup spectrum changes during the burnup step more accurately. An intermediate verification of the fuel management system was performed to assess the correctness of the newly implemented schemes against HELIOS. It was found that the agreement of both codes is good when the same energy released per fission (Q values) is used. Furthermore, to be able to model the reactor at various temperatures, the fuel management tool is able to utilize automatically the continuous cross sections generated at different temperatures. Other additional useful capabilities were also added to the fuel management tool to make it easy to use and be practical. As part of the development, a hybrid nodal diffusion/Monte Carlo calculation was devised to speed up the Monte Carlo calculation by providing more converged initial source distribution for the Monte Carlo calculation from the nodal diffusion calculation. Finally, the fuel management system was validated against the measured data using several actual PSBR core loadings. The agreement of the predicted core

  9. Preparation for shipment of spent TRIGA fuel elements from the research reactor of the Medical University of Hannover

    Hampel, Gabriele; Cordes, Harro; Ebbinghaus, Kurt; Haferkamp, Dirk

    1998-01-01

    In the early seventies a research reactor of type TRIGA Mark I was installed in the Department of Nuclear Medicine at the Medical University of Hannover (MHH) for the production of isotopes with short decay times for medical use. Since new production methods have been developed, the reactor has become obsolete and the MHH decided to decommission it. Probably in the second quarter of 1999 all 76 spent TRIGA fuel elements will be shipped to Idaho National Engineering and Environmental Laboratory (INEEL), USA, in one cask of type GNS 16. Due to technical reasons within the MHH a special Mobile Transfer System, which is being developed by the company Noell-KRC, will be used for reloading the fuel elements and transferring them from the reactor to the cask GNS 16. A description of the main components of this system as well as the process for transferring the fuel elements follows. (author)

  10. Fuel safety research 1999

    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)

  11. Fuel safety research 2001

    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)

  12. Fuel safety research 2000

    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)

  13. Proceedings of the symposium on the joint research program between JAERI and Universities. Current status and future perspectives of the chemistry research in the nuclear fuel cycle back end field

    1999-10-01

    The first Symposium on the Joint Research Project between JAERI and Universities was held in Tokyo, January 27, 1999, to present the main achievements of the project in these 5 years and to discuss future perspectives of the chemistry research relating to the nuclear fuel cycle. The areas covered by the Joint Research Project are (1) Nuclear Chemistry for TRU Recycling, (2) Solid State Chemistry on Nuclear Fuels and Wastes, (3) Solution Chemistry on Fuel Reprocessing and Waste Management, and (4) Fundamental Chemistry on Radioactive Waste Disposal. The 8 papers are indexed individually. (J.P.N.)

  14. Motivating University Researchers

    Hendriks, P.H.J.; Alves de Sousa, C.A.

    2008-01-01

    This paper presents an empirical investigation into how universities approach the need and means for motivating university researchers through their management practices. The role of work motivation for this group deserves attention because pressures from outside and within the universities are said

  15. Universities as Research Partners

    Hall, Bronwyn; Link, Albert; Scott, John

    2010-01-01

    Universities are a key institution in the U.S. innovation system, and an important aspect of their involvement is the role they play in public-private partnerships. This note offers insights into the performance of industry-university research partnerships, using a survey of precommercial research projects funded by the Advanced Technology Program. Although results must be interpreted cautiously because of the small size of the sample, the study finds that projects with university involvement...

  16. Fuel Chemistry Research | Transportation Research | NREL

    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

  17. Improving University Research Value

    Kelley O’Reilly

    2012-07-01

    Full Text Available This article investigates the current data management practices of university researchers at an Intermountain West land-grant research university in the United States. Key findings suggest that researchers are primarily focused on the collection and housing of research data. However, additional research value exists within the other life cycle stages for research data—specifically in the stages of delivery and maintenance. These stages are where most new demands and requirements exist for data management plans and policies that are conditional for external grant funding; therefore, these findings expose a “gap” in current research practice. These findings should be of interest to academics and practitioners alike as findings highlight key management gaps in the life cycle of research data. This study also suggests a course of action for academic institutions to coalesce campus-wide assets to assist researchers in improving research value.

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

    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

  19. Fuel Cell Research

    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.

  20. NASA Hydrogen Research at Florida Universities

    David L Block; Ali T-Raissi

    2006-01-01

    This paper presents a summary of the activities and results from 36 hydrogen research projects being conducted over a four-year period by Florida universities for the U. S. National Aeronautics and Space Administration (NASA). The program entitled 'NASA Hydrogen Research at Florida Universities' is managed by the Florida Solar Energy Center (FSEC). FSEC has 22 years of experience in conducting research in areas related to hydrogen technologies and fuel cells. The R and D activities under this program cover technology areas related to production, cryogenics, sensors, storage, separation processes, fuel cells, resource assessments and education. (authors)

  1. Advanced Research Reactor Fuel Development

    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.

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

    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 ...

  3. Research reactor de-fueling and fuel shipment

    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

  4. Research on CDA for advanced fuel FBR

    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.)

  5. Caramel fuel for research reactors

    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

  6. The Mississippi University Research Consortium for the Utilization of Biomass: Production of Alternative Fuels from Waste Biomass Initiative

    Drs. Mark E. Zapp; Todd French; Lewis Brown; Clifford George; Rafael Hernandez; Marvin Salin (from Mississippie State University); Drs. Huey-Min Hwang, Ken Lee, Yi Zhang; Maria Begonia (from Jackson State University); Drs. Clint Williford; Al Mikell (from the University of Mississippi); Drs. Robert Moore; Roger Hester (from the University of Southern Mississippi).

    2009-03-31

    The Mississippi Consortium for the Utilization of Biomass was formed via funding from the US Department of Energy's EPSCoR Program, which is administered by the Office of Basic Science. Funding was approved in July of 1999 and received by participating Mississippi institutions by 2000. The project was funded via two 3-year phases of operation (the second phase was awarded based on the high merits observed from the first 3-year phase), with funding ending in 2007. The mission of the Consortium was to promote the utilization of biomass, both cultured and waste derived, for the production of commodity and specialty chemicals. These scientific efforts, although generally basic in nature, are key to the development of future industries within the Southeastern United States. In this proposal, the majority of the efforts performed under the DOE EPSCoR funding were focused primarily toward the production of ethanol from lignocellulosic feedstocks and biogas from waste products. However, some of the individual projects within this program investigated the production of other products from biomass feeds (i.e. acetic acid and biogas) along with materials to facilitate the more efficient production of chemicals from biomass. Mississippi is a leading state in terms of raw biomass production. Its top industries are timber, poultry production, and row crop agriculture. However, for all of its vast amounts of biomass produced on an annual basis, only a small percentage of the biomass is actually industrially produced into products, with the bulk of the biomass being wasted. This situation is actually quite representative of many Southeastern US states. The research and development efforts performed attempted to further develop promising chemical production techniques that use Mississippi biomass feedstocks. The three processes that were the primary areas of interest for ethanol production were syngas fermentation, acid hydrolysis followed by hydrolyzate fermentation, and

  7. Fuel Combustion Laboratory | Transportation Research | NREL

    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

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

    | 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

  9. Research reactor fuel - an update

    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

  10. Fuels for Canadian research reactors

    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

  11. Navy Fuel Research Facility

    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...

  12. Fuels Combustion Research: Supercritical Fuel Pyrolysis

    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...

  13. Fuels Combustion Research: Supercritical Fuel Pyrolysis

    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...

  14. Mississippi State University Sustainable Energy Research Center

    Steele, W. Glenn [Mississippi State Univ., Mississippi State, MS (United States)

    2014-09-26

    The Sustainable Energy Research Center (SERC) project at Mississippi State University included all phases of biofuel production from feedstock development, to conversion to liquid transportation fuels, to engine testing of the fuels. The feedstocks work focused on non-food based crops and yielded an increased understanding of many significant Southeastern feedstocks. an emphasis was placed on energy grasses that could supplement the primary feedstock, wood. Two energy grasses, giant miscanthus and switchgrass, were developed that had increased yields per acre. Each of these grasses was patented and licensed to companies for commercialization. The fuels work focused on three different technologies that each led to a gasoline, diesel, or jet fuel product. The three technologies were microbial oil, pyrolysis oil, and syngas-to liquid-hydrocarbons

  15. Growing an Emerging Research University

    Birx, Donald L.; Anderson-Fletcher, Elizabeth; Whitney, Elizabeth

    2013-01-01

    The emerging research college or university is one of the most formidable resources a region has to reinvent and grow its economy. This paper is the first of two that outlines a process of building research universities that enhance regional technology development and facilitate flexible networks of collaboration and resource sharing. Although the…

  16. Maritime Cyber Security University Research

    2016-05-01

    i Classification | CG-926 RDC | author | audience | month year Maritime Cyber Security University Research Phase I - Final Report...Distribution Statement A: Approved for public release; distribution is unlimited. May 2016 Report No. CG-D-06-16 Maritime Cyber Security...Director United States Coast Guard Research & Development Center 1 Chelsea Street New London, CT 06320 Maritime Cyber Security University

  17. Status of biomass fuels technologies research in the US

    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.

  18. Low enrichment fuel conversion for Iowa State University. Final report

    Bullen, D.B.; Wendt, S.E.

    1996-01-01

    The UTR-10 research and teaching reactor at Iowa State University (ISU) has been converted from high-enriched fuel (HEU) to low- enriched fuel (LEU) under Grant No. DE-FG702-87ER75360 from the Department of Energy (DOE). The original contract period was August 1, 1987 to July 31, 1989. The contract was extended to February 28, 1991 without additional funding. Because of delays in receiving the LEU fuel and the requirement for disassembly of the HEU assemblies, the contract was renewed first through May 31, 1992, then through May 31, 1993 with additional funding, and then again through July 31, 1994 with no additional funding. In mid-August the BMI cask was delivered to Iowa State. Preparations are underway to ship the HEU fuel when NRC license amendments for the cask are approved

  19. Fuels Performance | Transportation Research | NREL

    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

  20. Fuel cells: Trends in research and applications

    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.

  1. Low enrichment fuel conversion for Iowa State University

    Rohach, A.F.; Hendrickson, R.A.

    1990-08-01

    Work during the reported period was centered primarily in preparation for receiving the LEU fuel and the shipping of the HEU fuel. The LEU fuel has not been received. The HEU fuel assemblies for the UTR-10 reactor will not fit into any current research reactor shipping containers; therefore, the fuel assemblies must be disassembled and the fuel shipped as fuel plates. Procedures and practices have been developed so that the fuel assemblies will be disassembled in a shielded environment

  2. Hohenheim University. 1991 research report

    Geiler, U.

    1992-06-01

    The 1991 Research Report of the Hohenheim University near Stuttgart is based on data collected in 1989 and extensively in 1990 and 1991. The progress reports were sent to all of the faculties, institutions, particular research areas and centres of the University. Questions were posed regarding current and recently completed projects. The final version was adapted for print. The survey also enquired about financial support from third parties. The numerous contacts abroad of the Hohenheim University are also documented in this book. Finally, it was asked under which of the nine main Hohenheim research programme headings the particular project could be listed. (orig.) [de

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

    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.

  4. The first university research reactor in India

    Murty, G.S.

    1999-01-01

    As the first university research reactor in India, the low power, pool type with fixed core and low enriched uranium fuel research reactor is under construction in the Andhra university campus, Andhra Pradesh, India. The reactor is expected to be commissioned during 2001-2002. The mission of the reactor is to play the research center as a regional research facility catering to the needs of academic institutions and industrial organizations of this region of the country. Further, to encourage interdisplinary and multidisplinary research activities, to supply radioisotope and labelled compounds to the user institutions and to create awareness towards the peaceful uses of atomic energy. This report describes its objectives, status and future plans in brief. (H. Itami)

  5. The first university research reactor in India

    Murty, G.S. [Co-ordinator, Low Power Research Reactor, Andhra Univ., Visakapatnam (India)

    1999-08-01

    As the first university research reactor in India, the low power, pool type with fixed core and low enriched uranium fuel research reactor is under construction in the Andhra university campus, Andhra Pradesh, India. The reactor is expected to be commissioned during 2001-2002. The mission of the reactor is to play the research center as a regional research facility catering to the needs of academic institutions and industrial organizations of this region of the country. Further, to encourage interdisplinary and multidisplinary research activities, to supply radioisotope and labelled compounds to the user institutions and to create awareness towards the peaceful uses of atomic energy. This report describes its objectives, status and future plans in brief. (H. Itami)

  6. Advanced research reactor fuel development

    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

  7. Green energy and hydrogen research at University of Waterloo

    Fowler, M.

    2006-01-01

    This paper summarises Green Energy and Hydrogen Research at the University of Waterloo in Canada. Green energy includes solar, wind, bio fuels, hydrogen economy and conventional energy sources with carbon dioxide sequestration

  8. Reducing enrichment of fuel for research reactors

    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.)

  9. Research and development of thorium fuel cycle

    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.)

  10. Composite Solid Fuel: Research of Formation Parameters

    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.

  11. Unified fuel elements development for research reactors

    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)

  12. Fuel elements of research reactors in China

    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

    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. High Burnup Fuel Performance and Safety Research

    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.

  15. Summary of fuel safety research meeting 2004

    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)

  16. Fuels Performance | Transportation Research | NREL

    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

  17. Trends in fuel reprocessing safety research

    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.)

  18. Dispersion fuel for nuclear research facilities

    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

  19. Universal high-temperature heat treatment furnace for FBR mixed uranium and plutonium carbide fuel

    Handa, Muneo; Takahashi, Ichiro; Watanabe, Hitoshi

    1978-10-01

    A universal high-temperature heat treatment furnace for LMFBR advanced fuels was installed in Plutonium Fuel Laboratory, Oarai Research Establishment. Design, construction and performance of the apparatus are described. With the apparatus, heat treatment of the fuel under a controlled gas atmosphere and quenching of the fuel with blowing helium gas are possible. Equipment to measure impurity gas release of the fuel is also provided. Various plutonium enclosure techniques, e.g., a gas line filter with new exchange mechanics, have been developed. In performance test, results of the enclosure techniques are described. (author)

  20. Nuclear Fusion Fuel Cycle Research Perspectives

    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

  1. The Canadian research reactor spent fuel situation

    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

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

    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

  3. Research on bioorganic fuels as power sources

    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)

  4. Unification of fuel elements for research reactors

    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)

  5. Research project at Nagoya University

    Furukawa, M.; Nakai, N.; Nakano, E.

    1981-01-01

    We will have a dedicated facility from General Ionex Corporation at the Radioisotope Center of Nagoya Univeriy in 1981 FY. The building to install the machine was already completed in March 1981. We have held meetings of potential users of the facility and various research proposals have been presented by the participants from many departments of the university. The present research project at Nagoya is mainly devoted to the development of radiocarbon dating by the accelerator mass spectrometry, in which most of the users are interested. There are many archeological and geological samples in Japan which have too little carbon compounds for analysis by conventional radioactivity measurements. Concentrations of 14 C in these samples can be determined by the new technique. Some of the proposals connected with radiocarbon measurements are discussed

  6. Research universities for the 21st century

    Gover, J. [Sandia National Labs., Albuquerque, NM (United States); Huray, P.G. [Univ. of South Carolina, Columbia, SC (United States)

    1998-05-01

    The `public outcomes` from research universities are educated students and research that extends the frontiers of knowledge. Measures of these `public outcomes` are inadequate to permit either research or education consumers to select research universities based on quantitative performance data. Research universities annually spend over $20 billion on research; 60% of these funds are provided by Federal sources. Federal funding for university research has recently grown at an annual rate near 6% during a time period when other performers of Federal research have experienced real funding cuts. Ten universities receive about 25% of the Federal funds spent on university research. Numerous studies of US research universities are reporting storm clouds. Concerns include balancing research and teaching, the narrow focus of engineering education, college costs, continuing education, and public funding of foreign student education. The absence of research on the `public outcomes` from university research results in opinion, politics, and mythology forming the basis of too many decisions. Therefore, the authors recommend studies of other nations` research universities, studies of various economic models of university research, analysis of the peer review process and how well it identifies the most capable research practitioners and at what cost, and studies of research university ownership of intellectual property that can lead to increased `public outcomes` from publicly-funded research performed by research universities. They advocate two practices that could increase the `public outcomes` from university research. These are the development of science roadmaps that link science research to `public outcomes` and `public outcome` metrics. Changes in the university research culture and expanded use of the Internet could also lead to increased `public outcomes`. They recommend the use of tax incentives to encourage companies to develop research partnerships with research

  7. Association of African Universities : Education and Research ...

    Association of African Universities : Education and Research Networking Unit. The Association of African Universities (AAU), headquartered in Accra, Ghana, is an international nongovernmental organization (NGO) that promotes cooperation between African universities and with the international community.

  8. RESEARCH UNIVERSITIES IN MALAYSIA: WHAT BEHOLDS?

    Nooraini Mohamad Sheriff

    2017-12-01

    Full Text Available The National Higher Education Strategic Plan Beyond 2020 aims at further strengthening Malaysian research universities and envisions that two Malaysian universities will be among the Top 100 world universities. To date there are 5 research universities in Malaysia, namely University of Malaya (UM, Universiti Kebangsaan Malaysia (UKM, Universiti Sains Malaysia (USM, Universiti Putra Malaysia (UPM and Universiti Teknologi Malaysia (UTM being the latest addition. These research universities are required to focus primarily on research and innovation activities, driven by highly competent academics and competitive student admissions. Research universities too are expected to explore their intellectual capacity and become models of Malaysian universities in conducting research activities aimed at knowledge advancement. Apart from this research universities are entrusted to generate their own income and establish holding companies responsible for conducting business ventures through the commercialization of their research products. Quality and quantity of researchers, research and postgraduates are also expected to increase in these research driven institutions. This calls for a visionary university leadership and the application of a new image and organizational principles. Education, training and employment policies too have to be reviewed, to ensure staff have the skills necessary for the development of research activities.

  9. Fuel cell research: Towards efficient energy

    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...

  10. Handling of spent fuel from research reactors in Japan

    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)

  11. Fuel Fabrication Capability Research and Development Plan

    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.

  12. Research reactor spent fuel in Ukraine

    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

  13. Advanced fuel in the Budapest research reactor

    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)

  14. Alternative Fuels DISI Engine Research ? Autoignition Metrics.

    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.

  15. Summary of fuel safety research meeting 2005

    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)

  16. Fuels for Canadian research reactors

    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

  17. Hydrogen and fuel cell research networking in Ontario

    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.

  18. Radionuclide release from research reactor spent fuel

    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

  19. Future plant of basic research for nuclear energy by university researchers

    Shibata, Toshikazu

    1984-01-01

    National Committee for Nuclear Energy Research, Japan Science Council has completed a future plan for basic nuclear energy research by university researchers. The JSC has recommended the promotion of basic research for nuclear energy based on the plan in 1983. The future plan consists of four main research fields, namely, (1) improvements of reactor safety, (2) down stream, (3) thorium fuel reactors, and (4) applications of research reactor and radioisotopes. (author)

  20. Managing University Research Microdata Collections

    Woolfrey, Lynn; Fry, Jane

    2015-01-01

    This article examines the management of microdata collections in a university context. It is a cross-country analysis: Collection management at data services in Canada and South Africa are considered. The case studies are of two university sub-contexts: One collection is located in a library; the other at a Faculty-based Data Service. Stages in…

  1. Nuclear energy research in Germany 2008. Research centers and universities

    Tromm, Walter

    2009-01-01

    This summary report presents nuclear energy research at research centers and universities in Germany in 2008. Activities are explained on the basis of examples of research projects and a description of the situation of research and teaching in general. Participants are the - Karlsruhe Research Center, - Juelich Research Center (FZJ), - Dresden-Rossendorf Research Center (FZD), - Verein fuer Kernverfahrenstechnik und Analytik Rossendorf e.V. (VKTA), - Technical University of Dresden, - University of Applied Sciences, Zittau/Goerlitz, - Institute for Nuclear Energy and Energy Systems (IKE) at the University of Stuttgart, - Reactor Simulation and Reactor Safety Working Group at the Bochum Ruhr University. (orig.)

  2. The FLIP fuel experience at Washington State University

    Lovas, Thomas A.

    1977-01-01

    The Washington State University TRIGA-fueled modified G.E. reactor was refueled with a partial TRIGA-FLIP core in February, 1976. The final core loading consisted of 35 FLIP and 75 Standard TRIGA fuel rods and provided a core excess reactivity of $7.98. The observed performance of the reactor did not deviate significantly from the design predictions and specifications. Pulsing tests revealed a maximum power output of 1850 MW with a fuel temperature of 449 deg. C from a $2.50 pulse. Slight power fluctuations at 1 Megawatt steady-state operation and post-pulse power oscillations were observed. (author)

  3. ASSESSING UNIVERSITY RESEARCH PERFORMANCE WITH MULTIPLE CONSTITUENCIES

    Kuang-Liang Liu

    2012-12-01

    Full Text Available The research performance of the university is critical to the national competitiveness. Previous research has established that research performance is based on scholarly publishing. Several studies suggested that journal ranking is the important research quality indicator. However, unilateral measurement for the research performance will seriously corrode the development of university research work. Assessing university research performance with multiple constituencies is a better to enhance the university research. Although substantial studies have been performed on the critical factors that affect knowledge exploration in the university, those in knowledge exploitation are still lacking. With the multiple constituencies, a fully understanding of research performance can be gained. In the research model, knowledge exploration represents the academic research and knowledge exploitation represents the university–industry collaboration. Data collected from 124 university data in online database. The study shows that knowledge exploration and exploitation both are significant positive predictors of university competitiveness. University resources play important roles to affect both knowledge exploration and exploitation in the university. The study also shows that higher knowledge exploration will enhance knowledge exploitation. Implications for theory and practice and suggestions for future research are discussed.

  4. About fuel assemblies optimization in research reactor

    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

  5. Transformational Leadership in Research Universities

    Gilmore, Ryann M.

    2011-01-01

    In order to preserve research integrity, leaders at postsecondary research institutions must utilize transformational leadership behaviors in order to promote a campus culture that is the most conducive to responsible research conduct. In support of this assertion, the issue of research misconduct and its potential consequences for both…

  6. University of Maryland MRSEC - Research

    operation. This site remains as a history of the center, but will not be actively maintained. University of . Crystals are made up of layers, or "planes" of atoms, perfectly stacked in an ordered pattern . Because this surface has been cut at a slight angle to the crystal planes, it appears "stepped"

  7. Role Strain in University Research Centers

    Boardman, Craig; Bozeman, Barry

    2007-01-01

    One way in which university faculty members' professional lives have become more complex with the advent of contemporary university research centers is that many faculty have taken on additional roles. The authors' concern in this article is to determine the extent to which role strain is experienced by university faculty members who are…

  8. Universal autoignition models for designer fuels in HCCI combustion

    Vandersickel, A.; Boulouchos, K.; Wright, Y.M. [LAV - Aerothermochemistry and Combustion Systems Laboratory - Institute of Energy Technology, ETH Zurich (Switzerland)], email: vandersickel@lav.mavt.ethz.ch

    2010-07-01

    In the energy sector, stringent regulations have been implemented on combustion emissions in order to address health and environmental concerns and help improve air quality. A novel combustion mode, homogeneous charge compression ignition (HCCI), can improve the emissions performance of an engine in terms of NOx and soot release over that of diesel while maintaining the same efficiencies. However, problems of ignition timing control arise with HCCI. The aim of this paper is to determine how fuel properties impact the HCCI ignition process and operating range. This study was carried out as part of a collaboration among several universities and automotive companies and 10 fuels were investigated experimentally and numerically using Arrhenius' model and a lumped reaction model. The two ignition models were successfully adapted to describe the behavior of the studied fuels; atomizer engine experiments validated their results. Further work will be conducted to optimize the reaction mechanism for the remaining process fuels.

  9. Reduced enrichment fuel and its reactivity effects in the University Training Reactor Moata

    Wilson, D.J.

    1983-08-01

    Concern for nuclear proliferation is likely to preclude future supply of highly enriched uranium fuel for research reactors such as the University Training Reactor Moata. This study calculates the fuel densities necessary to maintain the reactivity per plate of the present high enrichment (90 per cent 235 U) fuel for a range of lower enrichments assuming that no geometry changes are allowed. The maximum uranium density for commercially available aluminium-type research reactor fuels is generally considered to be about 1.7 g cm -3 . With this density limitation, the minimum enrichment to maintain present reactivity per plate is about 35 per cent 235 U. For low enrichment (max. 20 per cent 235 U) fuel, the required U density is about 2.9 g cm -3 , which is beyond the expected range for UAl/sub x/-Al but within that projected for the longer term development and full qualification for U 3 O 8 -Al. Medium enrichment (nominally 45 per cent 235 U) Al/sub x/-Al would be entirely satisfactory as an immediate replacement fuel, requiring no modifications to the reactor and operating procedures, and minimal reappraisal of safety issues. Included in this study are calculations of the fuel coefficients at various enrichments, the effect of replacing standard fuel plates or complete elements with 45 per cent enriched fuel, and the reactivity to be gained by replacing 12-plate with 13-plate elements

  10. PCR+ In Diesel Fuels and Emissions Research

    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.

  11. Trade Union Participation in University Research Policies.

    Leydesdorff, Loet

    1984-01-01

    The recent development of Dutch research coordination agencies, the Science Shops, forms the context for a description of the relationship between university research and policy at Amsterdam University and the national trade union organization. Management tools such as project financing and other elements of this system are discussed. (MSE)

  12. French experience in research reactor fuel transportation

    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)

  13. Development of Green Fuels From Algae - The University of Tulsa

    Crunkleton, Daniel; Price, Geoffrey; Johannes, Tyler; Cremaschi, Selen

    2012-12-03

    The general public has become increasingly aware of the pitfalls encountered with the continued reliance on fossil fuels in the industrialized world. In response, the scientific community is in the process of developing non-fossil fuel technologies that can supply adequate energy while also being environmentally friendly. In this project, we concentrate on green fuels which we define as those capable of being produced from renewable and sustainable resources in a way that is compatible with the current transportation fuel infrastructure. One route to green fuels that has received relatively little attention begins with algae as a feedstock. Algae are a diverse group of aquatic, photosynthetic organisms, generally categorized as either macroalgae (i.e. seaweed) or microalgae. Microalgae constitute a spectacularly diverse group of prokaryotic and eukaryotic unicellular organisms and account for approximately 50% of global organic carbon fixation. The PI's have subdivided the proposed research program into three main research areas, all of which are essential to the development of commercially viable algae fuels compatible with current energy infrastructure. In the fuel development focus, catalytic cracking reactions of algae oils is optimized. In the species development project, genetic engineering is used to create microalgae strains that are capable of high-level hydrocarbon production. For the modeling effort, the construction of multi-scaled models of algae production was prioritized, including integrating small-scale hydrodynamic models of algae production and reactor design and large-scale design optimization models.

  14. Contract Research, the University, and the Academic.

    Crawshaw, Bruce

    1985-01-01

    Implications of the growth of university-based contract research are examined, including moral and ethical issues, legal aspects, ownership of research results, staff rights, researcher status, publication, authority, responsibility, social justice, and conflicts between teaching and research. Eleven suggestions for successful contract research…

  15. Human Research Ethics Committees in Technical Universities

    Koepsell, D.R.; Brinkman, W.P.; Pont, S.C.

    2014-01-01

    Human research ethics has developed in both theory and practice mostly from experiences in medical research. Human participants, however, are used in a much broader range of research than ethics committees oversee, including both basic and applied research at technical universities. Although

  16. University of Mauritius Research Journal

    for Researchers · for Journals · for Authors · for Policy Makers · about Open Access · Journal Quality. 521 African Journals. Browse By Category · Browse Alphabetically · Browse By Country · List All Titles · Free To Read Titles This Journal is Open Access. Featuring journals from 32 Countries: Algeria (5); Benin (2); Botswana ...

  17. The first university research reactor in India

    Murthy, G.S.

    1999-01-01

    At low power research reactor is being set up in Andhra University to cater to the needs of researchers and isotope users by the Department of Atomic Energy in collaboration with Andhra University. This reactor is expected to be commissioned by 2001-02. Departments like Chemistry, Earth Sciences, Physics, Life Sciences, Pharmacy, Medicine and Engineering would be the beneficiaries of the availability of this reactor. In this paper, details of the envisaged research programme and training activities are discussed. (author)

  18. Subcritical Measurements Research Program for Fresh and Spent Materials Test Reactor Fuels

    Blanchard, A.

    1999-01-01

    'A series of subcritical noise measurements were performed on fresh and spent University of Missouri Research Reactor fuel assemblies. These experimental measurements were performed for the purposes of providing benchmark quality data for validating transport theory computer codes and nuclear cross-section data used to perform criticality safety analyses for highly enriched, uranium-aluminum Material Test Reactor fuel assemblies. A mechanical test rig was designed and built to hold up to four fuel assemblies and neutron detectors in a subcritical array. The rig provided researchers with the ability to evaluate the reactivity effects of variable fuel/detector spacing, fuel rotation, and insertion of metal reflector plates into the lattice.'

  19. Conversion and standardization of university reactor fuels using low-enrichment uranium - Options and costs

    Harris, D.R.; Matos, J.E.; Young, H.H.

    1985-01-01

    The highly-enriched uranium (HEU) fuel used in twenty United States university reactors can be viewed as contributing to the risk of theft or diversion of weapons-useable material. The U.S. Nuclear Regulatory Commission has issued a policy statement expressing its concern and has published a proposed rule on limiting the use of HEU in NRC-licensed non-power reactors. The fuel options, functional impacts, licensing, and scheduling of conversion and standardization of these reactor fuels to use of low-enrichment uranium (LEU) have been assessed. The university reactors span a wide range in form and function, from medium-power intense neutron sources where HEU fuel may be required, to low-power training and research facilities where HEU fuel is unnecessary. Conversion provides an opportunity to standardize university reactor fuels and improve reactor utilization in some cases. The entire program is estimated to cost about $10 million and to last about five years. Planning for conversion and standardization is facilitated by the U.S. Department of Energy. (author)

  20. Conversion and standardization of university reactor fuels using low-enrichment uranium - options and costs

    Harris, D.R.; Matos, J.E.; Young, H.H.

    1985-01-01

    The highly-enriched uranium (HEU) fuel used in twenty United States university reactors can be viewed as contributing to the risk of theft or diversion of weapons-useable material. The US Nuclear Regulatory Commission has issued a policy statement expressing its concern and has published a proposed rule on limiting the use of HEU in NRC-licensed non-power reactors. The fuel options, functional impacts, licensing, and scheduling of conversion and standardization of these reactor fuels to use of low-enrichment uranium (LEU) have been assessed. The university reactors span a wide range in form and function, from medium-power intense neutron sources where HEU fuel may be required, to low-power training and research facilities where HEU fuel is unnecessary. Conversion provides an opportunity to standardize university reactor fuels and improve reactor utilization in some cases. The entire program is estimated to cost about $10 million and to last about five years. Planning for conversion and standardization is facilitated by the US Department of Energy. 20 refs., 1 tab

  1. Future plans on the Kyoto University Research Reactor (KUR)

    Shibata, Seiichi

    2000-01-01

    The Research Reactor Institute (RRI), Kyoto University, for aiming at performing the 'Experiments using a reactor and its related research', was established in Showa 38 (1963) as a cooperative research institute for universities and so on in allover Japan. Operation using KUR of one of main facilities in RRI was started by 1 MW of its rated output in 1964, and converted to 5 MW in 1968, after which through development , addition and modification of various research apparatus it has been proposed to the cooperative application researches with universities and so on in allover Japan, hitherto. Among these periods, its research organization is improved to six departments containing twenty divisions and two attached research facilities to progress some investigations on future plans at RRI for response to new researching trends. Here were described on present state of research on use of low concentrated uranium fuels at research reactor, and future plans on neutron factory and hybrid reactor. The former aims at establishment of a new research facility capable of alternating to KUR for future academic research on research reactor containing high quality and high degree application of neutron field and safety management and feature upgrading of nuclear energy. And, the latter aims at development on an accelerator drive uncritical reactor combined an accelerator neutron source and an uncritical reactor. (G.K.)

  2. US spent fuel research and experience

    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.

  3. Research reactors fuel cycle problems and dilemma

    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

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

    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

  5. The University Campus: Why Military Sponsored Research.

    Messing, Aubrey E.

    Military-sponsored research on the university campus has been a major issue during the past several years. Opposition has come from radicals, who wish to destroy the university itself, to critics, who feel such activities take needed funds and personnel from the more important task of solving our nation's social problems. These viewpoints and the…

  6. Handling of TRIGA spent fuel at the Medical University of Hanover and its return to the United States

    Hampel, Gabriele; Harke, Heinrich; Kelm, Wieland; Klaus, Uwe

    2008-01-01

    The Medical University of Hannover (MHH) was taking part in the US Department of Energy's (DOE) 'Research Reactor Spent Fuel Acceptance Program' to return its 76 spent TRIGA fuel elements to the United States in the middle of 1999. The fuel elements have been moved to the Idaho National Engineering and Environmental Laboratory (INEEL) in Idaho. This paper describes the technical facilities for handling the fuel elements at the MHH and the various steps in removing the fuel elements from the reactor, transferring them to the transport cask and shipping them to the INEEL. (authors)

  7. University Funding: Federal Funding Mechanisms in Support of University Research.

    1986-02-01

    disciplines in elec- tronic sciences. DOE supports a team of researchers in high-energy and nuclear physics through contracts to build customized equipment to...data available on up to 15 federal agen- Collges ,19631982cies, support of science research at universities since 1963. Although not all of the...recent Ph.D. Young Investigators in physicists. High Energy Physics Time in Effect: 1975 to present. Fiscal Year 1984 Average Number of Average

  8. Research reactor spent fuel management in Argentina

    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. The Triad Research University or a Post 20th Century Research University Model

    Tadmor, Zehev

    2006-01-01

    In this paper, a model for the future research university is proposed, which answers some of the key challenges facing universities. It consists of three independent yet closely knitted entities: a research institute, a university teaching college and a business unit creating a "triad" structure. The possible inevitability, the advantages and…

  10. Brief report of the JNC Cooperative Research (A) on the Nuclear Fuel Cycle for 2004

    2005-06-01

    The Japan Nuclear Cycle Development Institute (JNC) started the JNC Cooperative Research Scheme (A) on the Nuclear Fuel Cycle in 1995 in order to promote research collaboration with universities and other research institutes (referred to as 'universities, etc.' below), which means that the fiscal year 2004 was the tenth year of the scheme. The purpose of this scheme is to promote the basic and fundamental research that precedes the research and development projects of JNC through collaboration with universities, etc. by using mainly JNC's facilities and equipment. Under the scheme, universities, etc. propose methods and ideas, etc. to lead to the achievement of the goals of research collaboration themes which are set by JNC as research collaboration subjects. Then a screening committee consisting mainly of experts independent of JNC screens the research collaboration subjects. Research collaboration is performed by carrying out cooperative research with universities, etc. or by accepting researchers from universities, etc. as Visiting Research Fellows at JNC. The scheme allows students studying for doctorates at postgraduate schools either to participate in the cooperative research or to be accepted as trainee researchers. This report includes a summary of the results of the research carried out in fiscal year 2004 on 42 research collaboration subjects for preceding basic engineering research related to fast breeder reactors, the nuclear fuel cycle, radiation safety and geological disposal/geoscience; seventeen of which ended in 2004. Of these, eight were related to fast breeder reactors, eight to the nuclear fuel cycle, and one to geological disposal/geoscience. (author)

  11. Brief report of the JNC cooperative research (C) on the nuclear fuel cycle for 2002

    2003-08-01

    The Japan Nuclear Cycle Development Institute (JNC) started the JNC Cooperative Research Scheme (C) on the Nuclear Fuel Cycle in 1999 in order to promote research collaboration with universities and other research institutes (referred to as 'universities, etc. 'below'), which means that the fiscal year 2002 was the fourth year of the scheme. This scheme is to invite foresighted and original themes of basic and fundamental research, to be performed using JNC's facilities and equipment, in principle, for the research and development of JNC in the field of the nuclear fuel cycle, from researchers at universities, etc. Those researchers who propose research themes in response to the invitation are expected to lead the research. The purpose of the scheme is to promote the efficiency of basic and fundamental research and development by enhancing the research environment of JNC through collaboration between JNC's own researchers and other researchers, and exchange of information and publication of achievements, etc. Research themes proposed by researchers at universities, etc. are screened by a screening committee consisting mainly of experts independent of JNC. This report includes a summary of the results of the research carried out in fiscal year 2002 on twenty selected themes related to the JNC's collaborative research for fast breeder reactors, the nuclear fuel cycle, radiation safety and geological disposal/geoscience; eight of which ended in 2002. Of these, three were related to fast breeder reactors, two to the nuclear fuel cycle and three to geological disposal/geoscience. (author)

  12. Data analytics research in public universities

    Smeaton, Alan F.

    2014-01-01

    Research into big data in publicly-funded Universities and research centres has major disadvantages compared to the private sector, and not just in the obvious areas of funding and access to data. In this abstract we highlight some of these differences around the area of ethics and privacy, and two specific examples of our work are used to illustrate this.

  13. Maritime Cyber Security University Research: Phase 1

    2016-05-01

    i Classification | CG-926 RDC | author | audience | month year Maritime Cyber Security University Research Phase I - Final Report...Appendices Distribution Statement A: Approved for public release; distribution is unlimited. May 2016 Report No. CG-D-07-16 Maritime ...Macesker Executive Director United States Coast Guard Research & Development Center 1 Chelsea Street New London, CT 06320 Maritime Cyber Security

  14. University Research Consortium annual review meeting program

    1996-07-01

    This brochure presents the program for the first annual review meeting of the University Research Consortium (URC) of the Idaho National Engineering Laboratory (INEL). INEL is a multiprogram laboratory with a distinctive role in applied engineering. It also conducts basic science research and development, and complex facility operations. The URC program consists of a portfolio of research projects funded by INEL and conducted at universities in the United States. In this program, summaries and participant lists for each project are presented as received from the principal investigators

  15. University Research Consortium annual review meeting program

    NONE

    1996-07-01

    This brochure presents the program for the first annual review meeting of the University Research Consortium (URC) of the Idaho National Engineering Laboratory (INEL). INEL is a multiprogram laboratory with a distinctive role in applied engineering. It also conducts basic science research and development, and complex facility operations. The URC program consists of a portfolio of research projects funded by INEL and conducted at universities in the United States. In this program, summaries and participant lists for each project are presented as received from the principal investigators.

  16. Administrative mechanics of research fuel transportation

    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

  17. Administrative mechanics of research fuel transportation

    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.

  18. Human research ethics committees in technical universities.

    Koepsell, David; Brinkman, Willem-Paul; Pont, Sylvia

    2014-07-01

    Human research ethics has developed in both theory and practice mostly from experiences in medical research. Human participants, however, are used in a much broader range of research than ethics committees oversee, including both basic and applied research at technical universities. Although mandated in the United States, the United Kingdom, Canada, and Australia, non-medical research involving humans need not receive ethics review in much of Europe, Asia, Latin America, and Africa. Our survey of the top 50 technical universities in the world shows that, where not specifically mandated by law, most technical universities do not employ ethics committees to review human studies. As the domains of basic and applied sciences expand, ethics committees are increasingly needed to guide and oversee all such research regardless of legal requirements. We offer as examples, from our experience as an ethics committee in a major European technical university, ways in which such a committee provides needed services and can help ensure more ethical studies involving humans outside the standard medical context. We provide some arguments for creating such committees, and in our supplemental article, we provide specific examples of cases and concerns that may confront technical, engineering, and design research, as well as outline the general framework we have used in creating our committee. © The Author(s) 2014.

  19. UNIVERSITY BASIC RESEARCH AND APPLIED AGRICULTURAL BIOTECHNOLOGY

    Xia, Yin

    2004-01-01

    I examine the effects of R&D inputs on the subset of life-science outputs which demonstrably has influenced later technology, as evidenced by literature citations in agricultural biotechnology patents. Universities are found to be a principal seedbed for cutting-edge technology development. A university's life-science research budget strongly affects its technology-relevant life-science output as well as graduate education.

  20. Strategic Research, Post-modern Universities and Research Training

    Rip, Arie

    2004-01-01

    The old division of labour between fundamental and applied or problem-oriented research has almost disappeared, and with it, the functional distinctions between universities, public labs and industrial and other private research. Doctoral research training can then also become diversified in terms

  1. Fuel Fabrication Capability Research and Development Plan

    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

  2. Thermal-Hydraulic Research Review and Cooperation Outcome for Light Water Reactor Fuel

    In, Wang Kee; Shin, Chang Hwan; Lee, Chan; Chun, Tae Hyun; Oh, Dong Seok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Lee, Chi Young [Pukyong Nat’l Univ., Busan (Korea, Republic of)

    2016-12-15

    The fuel assembly for pressurized water reactor (PWR) consists of fuel rod bundle, spacer grid and bottom/top end fittings. The cooling water in high pressure and temperature is introduced in lower plenum of reactor core and directed to upper plenum through the subchannel which is formed between the fuel rods. The main thermalhydraulic performance parameters for the PWR fuel are pressure drop and critical heat flux in normal operating condition, and quenching time in accident condition. The Korea Atomic Energy Research Institute (KAERI) has been developing an advanced PWR fuel, dual-cooled annular fuel and accident tolerant fuel for the enhancement of fuel performance and the localization. For the key thermal-hydraulic technology development of PWR fuel, the KAERI LWR fuel team has conducted the experiments for pressure drop, turbulent flow mixing and heat transfer, critical heat flux(CHF) and quenching. The computational fluid dynamics (CFD) analysis was also performed to predict flow and heat transfer in fuel assembly including the spent fuel assembly in dry cask for interim repository. In addition, the research cooperation with university and nuclear fuel company was also carried out to develop a basic thermalhydraulic technology and the commercialization.

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

    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)

  4. Status of research reactor spent fuel world-wide

    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)

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

    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.

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

    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

  7. Universal electrode interface for electrocatalytic oxidation of liquid fuels.

    Liao, Hualing; Qiu, Zhipeng; Wan, Qijin; Wang, Zhijie; Liu, Yi; Yang, Nianjun

    2014-10-22

    Electrocatalytic oxidations of liquid fuels from alcohols, carboxylic acids, and aldehydes were realized on a universal electrode interface. Such an interface was fabricated using carbon nanotubes (CNTs) as the catalyst support and palladium nanoparticles (Pd NPs) as the electrocatalysts. The Pd NPs/CNTs nanocomposite was synthesized using the ethylene glycol reduction method. It was characterized using transmission electron microscopy, energy dispersive X-ray spectroscopy, X-ray diffraction, voltammetry, and impedance. On the Pd NPs/CNTs nanocomposite coated electrode, the oxidations of those liquid fuels occur similarly in two steps: the oxidations of freshly chemisorbed species in the forward (positive-potential) scan and then, in the reverse scan (negative-potential), the oxidations of the incompletely oxidized carbonaceous species formed during the forward scan. The oxidation charges were adopted to study their oxidation mechanisms and oxidation efficiencies. The oxidation efficiency follows the order of aldehyde (formaldehyde) > carboxylic acid (formic acid) > alcohols (ethanol > methanol > glycol > propanol). Such a Pd NPs/CNTs nanocomposite coated electrode is thus promising to be applied as the anode for the facilitation of direct fuel cells.

  8. Fuels and Combustion | Transportation Research | NREL

    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

  9. Government-University-Industry-Research Roundtable

    1995-02-01

    Roundtable projects active during 1993 are described in this section. Projects completed in prior years are not included here, but publications resulting from them are included in the list of publications which are attached. Such prior projects include nurturing science and engineering talent, research facility financing, multidisciplinary research and education, university-industry-federal laboratory partnerships, and federal-state cooperation in science and technology.

  10. Western Kentucky University Research Foundation Biodiesel Project

    Pan, Wei-Ping [Principal Investigator; Cao, Yan [Co-Principal Investigator

    2013-03-15

    production and combustion of ethanol and 41 % by bio-diesel. Bio-diesel also releases less air pollutants per net energy gain than ethanol. Bio-diesel has advantages over ethanol due to its lower agricultural inputs and more efficient conversion. Thus, to be a viable alternative, a bio-fuel firstly should be producible in large quantities without reducing food supplies. In this aspect, larger quantity supplies of cellulose biomass are likely viable alternatives. U. S. Congress has introduced an initiative and subsequently rolled into the basic energy package, which encourages the production of fuel from purely renewable resources, biomass. Secondly, a bio-fuel should also provide a net energy gain, have environmental benefits and be economically competitive. In this aspect, bio-diesel has advantages over ethanol. The commonwealth of Kentucky is fortunate to have a diverse and abundant supply of renewable energy resources. Both Kentucky Governor Beshear in the energy plan for Kentucky "Intelligent Energy Choices for Kentucky's Future", and Kentucky Renewable Energy Consortium, outlined strategies on developing energy in renewable, sustainable and efficient ways. Smart utilization of diversified renewable energy resources using advanced technologies developed by Kentucky public universities, and promotion of these technologies to the market place by collaboration between universities and private industry, are specially encouraged. Thus, the initially question answering Governor's strategic plan is if there is any economical way to make utilization of larger quantities of cellulose and hemicellulose for production of bio-fuels, especially bio-diesel. There are some possible options of commercially available technologies to convert cellulose based biomass energy to bio-fuels. Cellulose based biomass can be firstly gasified to obtain synthesis gas (a mixture of CO and H{sub 2}), which is followed up by being converted into liquid hydrocarbon fuels or oxygenate

  11. Managing a Modern University Research Center.

    Veres, John G., III

    1988-01-01

    The university research center of the future will function best to serve the rapidly changing public and private demand for services with a highly trained core staff, adequately funded and equipped, whose morale and quality of work performance is a prime consideration. (MSE)

  12. Georgetown University Research Psychologist Shares Terrorism Insight

    Center for Homeland Defense and Security

    2013-01-01

    Georgetown University research psychologist Dr. Anne Speckhard has spent the last decade interviewing more than four hundred terrorists, terrorist supporters, family members, close associates and even terrorist's hostages in Western Europe and the Middle East. Speckhard shared her insights with students at the Naval Postgraduate School Center for Homeland Defense and Security in July.

  13. University-Community Research Partnership for Community ...

    This paper analyses the existing university–community partnership in research in Tanzania and proposes a bottom-top model instead of the traditional top-bottom approach which works with perceived needs of communities rather than real needs. Given their core missions, many universities assume that they achieve their ...

  14. Association of African Universities : Education and Research ...

    The Association of African Universities (AAU), headquartered in Accra, Ghana, is an ... The Association operates a number of programs and services for its members. ... IWRA/IDRC webinar on climate change and adaptive water management ... Eleven world-class research teams set to improve livestock vaccine ...

  15. Overview of remote technologies applied to research reactor fuel

    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)

  16. Brief report of the JNC Cooperative Research (C) on the Nuclear Fuel Cycle for 2004

    2005-06-01

    The Japan Nuclear Cycle Development Institute (JNC) started the JNC Cooperative Research Scheme (C) on the Nuclear Fuel Cycle in 1999 in order to promote research collaboration with universities and other research institutes (referred to as 'universities, etc.' below), which means that the fiscal year 2004 was the sixth year of the scheme and ended in 2004. This scheme is to invite foresighted and original themes of basic and fundamental research, to be performed using JNC's facilities and equipment, in principle, for the research and development of JNC in the field of the nuclear fuel cycle, from researchers at universities, etc. Those researchers who propose research themes in response to the invitation are expected to lead the research. The purpose of the scheme is to promote the efficiency of basic and fundamental research and development by enhancing the research environment of JNC through collaboration between JNC's own researchers and other researchers, and exchange of information and publication of achievements, etc. Research themes proposed by researchers at universities, etc. are screened by a screening committee consisting mainly of experts independent of JNC. This report includes a summary of the result of the research carried out in fiscal year 2004 on four selected themes related the JNC's collaborative research for fast breeder reactors, the nuclear fuel cycle, radiation safety and geological disposal/geoscience. (author)

  17. Brief report of the JNC cooperative research (C) on the nuclear fuel cycle for 2003

    2004-06-01

    The Japan Nuclear Cycle Development Institute (JNC) started the JNC Cooperative Research Scheme (C) on the Nuclear Fuel Cycle in 1999 in order to promote research collaboration with universities and other research institutes (referred to as 'universities, etc.' below), which means that the fiscal year 2003 was the fifth year of the scheme. This scheme is to invite foresighted and original themes of basic and fundamental research, to be performed using JNC's facilities and equipment, in principle, for the research and development of JNC in the field of the nuclear fuel cycle, from researchers at universities, etc. Those researchers who propose research themes in response to the invitation are expected to lead the research. The purpose of the scheme is to promote the efficiency of basic and fundamental research and development by enhancing the research environment of JNC through collaboration between JNC's own researchers and other researchers, and exchange of information and publication of achievements, etc. Research themes proposed by researchers at universities, etc. are screened by a screening committee consisting mainly of experts independent of JNC. This report includes a summary of the results of the research carried out in fiscal year 2003 on twelve selected themes related to the JNC's collaborative research for fast breeder reactors, the nuclear fuel cycle, radiation safety and geological disposal/geoscience; eight of which ended in 2003. Of these, four were related to fast breeder reactors, one to radiation safety and three to geological disposal/geoscience. (author)

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

    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...

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

    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)

  20. Together with Research Centers and Universities

    Nuno Domingos Garrido

    2016-10-01

    Full Text Available The Journal Motricidade has always been walking in parallel with the scientific communities. We found that the affiliation of most authors has, nearly always, a University (Uni or a Research Center (RC. In fact it is almost impossible to conduct research outside these two universes. In this sense, Uni and RC feed the most, if not all, of scientific journals worldwide. By this I mean that is in the interest of Motricidade to be associated with high-quality RC and Uni equally recognized. With regard to RC, Motricidade will publish this year a supplement of the International Congress of Research Centre in Sports Sciences, Health Sciences and Human Development (CIDESD. This RC has conducted research in a variety of areas within the Sport Sciences and Health and always with high recognition and associated publications. It was not by chance that this RC was evaluated with ‘very good’ by the Portuguese Foundation for Science and Technology (FCT panel and has been granted funding. This Congress, which takes place every two years, targets to converge research and high level practices within these three areas: Sports, Health and Human Development. The 2016 CIDESD edition is dedicated to "Exercise and Health, Sports and Human Development" and will be held at the University of Évora, between 11 and 12 November of 2016. The readers can check the program in the following link http://gdoc.uevora.pt/450120 and get more information in the Congress Site available at http://www.cidesd2016.uevora.pt/. With regard to Uni, Motricidade signed a cooperation protocol with the University of Beira Interior (UBI in May of 2016, involving the development and dissemination of scientific knowledge in Sports Sciences, Psychology, Human Development and Health. At the present, UBI hosts more than 6,000 students spread across five faculties - Arts & Letters, Sciences, Health Sciences, Humanities and Social Sciences and Engineering. When looking at the rankings, for instance

  1. Management of radioisotope, radiation generator and fuel materials for independent administrative corporations of national university

    2003-03-01

    This report states the situation, problems and proposal of management of radioisotope, radiation generator and fuel materials by independent administrative corporations of national universities. Four proposals are stated as followings; 1) in order to improve management of radioisotope, radiation generator, fuel materials and X-ray in the universities, organization and definition of the control department in each university and accident measures have to be decided. The middle object and plan should be needed. An appropriate management for proceeding researches should be discussed by closer connection of universities in the country. 2) The budget for safety control has to be identified at distribution of budget of each national university corporations. The insurance method is needed to be discussed. 3) The department in the MEXT (Ministry of Education, Culture, Sports, Science and Technology) should be enriched to support researches and safety control of the staff and students. 4) The system, which carries out treatment and disposal of disuse materials and keeps them under the responsibility of the nation, is necessary. (S.Y.)

  2. Research and research impact of a technical university

    Schwarz, Annette Winkel; Schwarz, S.; Tijssen, R. J. W.

    1998-01-01

    The research output of the Danish Technical University (DTU) has been studied as an aspect of the organization's research policy and visibility in its international context. Papers published in the three-year period (1992-94) were grouped according to 20 clusters of research areas. Using citation...... analysis techniques, the dynamics of citation frequencies, and a number of other features of the research system, like self-citation, research collaborations, relative impact on the international literature, etc., could be studied. The methods can be used to analyze institutional and national research...

  3. Brief report of the JAEA cooperative research (A) on the nuclear fuel cycle for 2009

    2010-08-01

    The Japan Atomic Energy Agency (JAEA) started the JAEA Cooperative Research Scheme (A) on the Nuclear Fuel Cycle in 1995 in order to promote research collaboration with universities and other research institutes (referred to as 'universities, etc.' below), which means that the fiscal year 2009 was the fifteenth year of the scheme. The purpose of this scheme is to promote the basic and fundamental research that precedes the research and development projects in relation to the establishment of nuclear fuel cycle technology through collaboration with universities, etc. by using mainly JAEA's facilities and equipment. Under the scheme, universities, etc. propose methods and ideas, etc. to lead to the achievement of the goals of research collaboration themes which are set by JAEA as research collaboration subjects. Then a screening committee consisting mainly of experts independent of JAEA screens the research collaboration subjects. Research collaboration is performed by carrying out cooperative research with universities, etc. or by accepting researchers from universities, etc. as Visiting Research Fellows at JAEA. The scheme allows students studying for doctorates at postgraduate schools either to participate in the cooperative research or to be accepted as trainee researchers. This report includes a summary of the results of the research carried out in fiscal year 2009 on 32 research collaboration subjects for preceding basic engineering research related to fast breeder reactors, the nuclear fuel cycle, radiation safety and geological disposal/geoscience; eleven of which ended in 2009. Of these, six were related to fast breeder reactors, two to the nuclear fuel cycle, and three to geological disposal/geoscience. (author)

  4. Brief report of the JAEA cooperative research (A) on the nuclear fuel cycle for 2011

    2012-08-01

    The Japan Atomic Energy Agency (JAEA) started the JAEA Cooperative Research Scheme (A) on the Nuclear Fuel Cycle in 1995 in order to promote research collaboration with universities and other research institutes (referred to as “universities, etc.” below), which means that the fiscal year 2011 was the seventeenth year of the scheme. The purpose of this scheme is to promote the basic and fundamental research that precedes the research and development projects in relation to the establishment of nuclear fuel cycle technology through collaboration with universities, etc. by using mainly JAEA's facilities and equipment. Under the scheme, universities, etc. propose methods and ideas, etc. to lead to the achievement of the goals of research collaboration themes which are set by JAEA as research collaboration subjects. Then a screening committee consisting mainly of experts independent of JAEA screens the research collaboration subjects. Research collaboration is performed by carrying out cooperative research with universities, etc. or by accepting researchers from universities, etc. as Visiting Research Fellows at JAEA. The scheme allows students studying for doctorates at postgraduate schools either to participate in the cooperative research or to be accepted as trainee researchers. This report includes a summary of the results of the research carried out in fiscal year 2011 on 27 research collaboration subjects for preceding basic engineering research related to fast breeder reactors, the nuclear fuel cycle, radiation safety and geological disposal/geoscience; thirteen of which ended in 2011. Of these, seven were related to fast breeder reactors, two to the nuclear fuel cycle, one to radiation safety, and three to geological disposal/geoscience. (author)

  5. Brief report of the JAEA cooperative research (A) on the nuclear fuel cycle for 2007

    2008-10-01

    The Japan Atomic Energy Agency (JAEA) started the JAEA Cooperative Research Scheme (A) of the Nuclear Fuel Cycle in 1995 in order to promote research collaboration with universities and other research institutes (referred to as 'universities, etc.' below), which means that the fiscal year 2007 was the thirteenth year of the scheme. The purpose of this scheme is to promote the basic and fundamental research that precedes the research and development projects in relation to the establishment of nuclear fuel cycle technology through collaboration with universities, etc. by using mainly JAEA's facilities and equipment. Under the scheme, universities, etc. propose methods and ideas, etc. to lead to the achievement of the goals of research collaboration themes which are set by JAEA as research collaboration subjects. Then a screening committee consisting mainly of experts independent of JAEA screens the research collaboration subjects. Research collaboration is performed by carrying out cooperative research with universities, etc. or by accepting researchers from universities, etc. as Visiting Research Fellows at JAEA. The scheme allows students studying for doctorates at postgraduate schools either to participate in the cooperative research or to be accepted as trainee researchers. This report includes a summary of the results of the research carried out in fiscal year 2007 on 32 research collaboration subjects for preceding basic engineering research related to fast breeder reactors, the nuclear fuel cycle, radiation safety and geological disposal/geoscience; twelve of which ended in 2007. Of these, six were related to fast breeder reactors, two to the nuclear fuel cycle, and two to geological disposal/geoscience. (author)

  6. Brief report of the JAEA cooperative research (A) on the nuclear fuel cycle for 2008

    2009-09-01

    The Japan Atomic Energy Agency (JAEA) started the JAEA Cooperative Research Scheme (A) on the Nuclear Fuel Cycle in 1995 in order to promote research collaboration with universities and other research institutes (referred to as 'universities, etc.' below), which means that the fiscal year 2008 was the fourteenth year of the scheme. The purpose of this scheme is to promote the basic and fundamental research that precedes the research and development projects in relation to the establishment of nuclear fuel cycle technology through collaboration with universities, etc. by using mainly JAEA's facilities and equipment. Under the scheme, universities, etc. propose methods and ideas, etc. to lead to the achievement of the goals of research collaboration themes which are set by JAEA as research collaboration subjects. Then a screening committee consisting mainly of experts independent of JAEA screens the research collaboration subjects. Research collaboration is performed by carrying out cooperative research with universities, etc. or by accepting researchers from universities, etc. as Visiting Research Fellows at JAEA. The scheme allows students studying for doctorates at postgraduate schools either to participate in the cooperative research or to be accepted as trainee researchers. This report includes a summary of the results of the research carried out in fiscal year 2008 on 32 research collaboration subjects for preceding basic engineering research related to fast breeder reactors, the nuclear fuel cycle, radiation safety and geological disposal/geoscience; twelve of which ended in 2008. Of these, six were related to fast breeder reactors, one to the nuclear fuel cycle, one to radiation safety, and four to geological disposal/geoscience. (author)

  7. Brief report of the JAEA cooperative research (A) on the nuclear fuel cycle for 2012

    2013-11-01

    The Japan Atomic Energy Agency (JAEA) started the JAEA Cooperative Research Scheme (A) on the Nuclear Fuel Cycle in 1995 in order to promote research collaboration with universities and other research institutes (referred to as 'universities, etc.' below), which means that the fiscal year 2012 was the eighteenth year of the scheme. The purpose of this scheme is to promote the basic and fundamental research that precedes the research and development projects in relation to the establishment of nuclear fuel cycle technology through collaboration with universities, etc. by using mainly JAEA's facilities and equipment. Under the scheme, universities, etc. propose methods and ideas, etc. to lead to the achievement of the goals of research collaboration themes which are set by JAEA as research collaboration subjects. Then a screening committee consisting mainly of experts independent of JAEA screens the research collaboration subjects. Research collaboration is performed by carrying out cooperative research with universities, etc. or by accepting researchers from universities, etc. as Visiting Research Fellows at JAEA. The scheme allows students studying for doctorates at postgraduate schools either to participate in the cooperative research or to be accepted as trainee researchers. This report includes a summary of the results of the research carried out in fiscal year 2012 on 20 research collaboration subjects for preceding basic engineering research related to fast breeder reactors, the nuclear fuel cycle, radiation safety and geological disposal/geoscience; ten of which ended in 2012. Of these, three were related to fast breeder reactors, five to the nuclear fuel cycle, and two to geological disposal/geoscience. (author)

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

    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

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

    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

  10. New research facilities at the University of Missouri research reactor

    McKibben, J.C.; Rhyne, J.J.

    1992-01-01

    The University of Missouri-Columbia is investing its resources for a significant expansion of the research capabilities and utilization of MURR to provide it the opportunity to deliver on its obligation to become the nation's premier educational institution in nuclear-related fields and so that it can provide scientific personnel and a state-of-the-art research test bed to support the national need for highly trained graduates in nuclear science and engineering

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

    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

  12. Building Human Resources Management Capacity for University Research: The Case at Four Leading Vietnamese Universities

    Nguyen, T. L.

    2016-01-01

    At research-intensive universities, building human resources management (HRM) capacity has become a key approach to enhancing a university's research performance. However, despite aspiring to become a research-intensive university, many teaching-intensive universities in developing countries may not have created effective research-promoted HRM…

  13. Washington State University Algae Biofuels Research

    chen, Shulin [Washington State Univ., Pullman, WA (United States). Dept. of Biological Systems Engineering; McCormick, Margaret [Targeted Growth, Inc., Seattle, WA (United States); Sutterlin, Rusty [Inventure Renewables, Inc., Gig Harbor, WA (United States)

    2012-12-29

    The goal of this project was to advance algal technologies for the production of biofuels and biochemicals by establishing the Washington State Algae Alliance, a collaboration partnership among two private companies (Targeted Growth, Inc. (TGI), Inventure Chemicals (Inventure) Inc (now Inventure Renewables Inc) and Washington State University (WSU). This project included three major components. The first one was strain development at TGI by genetically engineering cyanobacteria to yield high levels of lipid and other specialty chemicals. The second component was developing an algal culture system at WSU to produce algal biomass as biofuel feedstock year-round in the northern states of the United States. This system included two cultivation modes, the first one was a phototrophic process and the second a heterotrophic process. The phototrophic process would be used for algae production in open ponds during warm seasons; the heterotrophic process would be used in cold seasons so that year-round production of algal lipid would be possible. In warm seasons the heterotrophic process would also produce algal seeds to be used in the phototrophic culture process. Selected strains of green algae and cyanobacteria developed by TGI were tested in the system. The third component was downstream algal biomass processing by Inventure that included efficiently harvesting the usable fuel fractions from the algae mass and effectively isolating and separating the usable components into specific fractions, and converting isolated fractions into green chemicals.

  14. Brief report of the JNC cooperative research (A) on the Nuclear Fuel Cycle for 2002

    2003-08-01

    The Japan Nuclear Cycle Development Institute (JNC) started the JNC Cooperative Research Scheme (A) on the Nuclear Fuel Cycle in 1995 in order to promote research collaboration with universities and other research institutes (referred to as 'universities, etc.' below), which means that the fiscal year 2002 was the eighth year of the scheme. The purpose of this scheme is to promote the basic and fundamental research that precedes the research and development projects of JNC through collaboration with universities, etc. by using mainly JNC's facilities and equipment. Under the scheme, universities, etc. propose methods and ideas, etc. to lead to the achievement of the goals of research collaboration themes which are set by JNC as research collaboration subjects. Then a screening committee consisting mainly of experts independent of JNC screens the research collaboration subjects. Research collaboration is performed by carrying out cooperative research with universities, etc. or by accepting researchers from universities, etc. as Visiting Research Fellows at JNC. The scheme allows students studying for doctorates at postgraduate schools either to participate in the cooperative research or to be accepted as trainee researchers. The report includes a summary of the results of the research carried out in fiscal year 2002 on 42 research collaboration subjects for preceding basic engineering research related to fast breeder reactors, the nuclear fuel cycle, radiation safety and geological disposal/geoscience; twelve of which ended in 2002. Of these, five were related to fast breeder reactors, three to the nuclear fuel cycle, one to radiation safety and three to geological disposal/geoscience. (author)

  15. Brief report of the JNC cooperative research (A) on the nuclear fuel cycle for 2003

    2004-08-01

    The Japan Nuclear Cycle Development Institute (JNC) started the JNC Cooperative Research Scheme (A) on the Nuclear fuel Cycle in 1995 in order to promote research collaboration with universities and other research institutes (referred to as 'universities, etc.' below), which means that the fiscal year 2003 was the ninth year of the scheme. The purpose of this scheme is to promote the basic and fundamental research that precedes the research and development projects of JNC through collaboration with universities, etc. by using mainly JNC's facilities and equipment. Under the scheme, universities, etc. propose methods and ideas, etc. to lead to the achievement of the goals of research collaboration themes which are set by JNC as research collaboration subjects. Then a screening committee consisting mainly of experts independent of JNC screens the research collaboration subjects. Research collaboration is performed by carrying out cooperative research with universities, etc. or by accepting researchers from universities, etc. as Visiting Research Fellows at JNC. The scheme allows students studying for doctorates at postgraduate schools either to participate in the cooperative research or to be accepted as trainee researchers. This report includes a summary of the results of the research carried out in fiscal year 2003 on 43 research collaboration subjects for preceding basic engineering research related to fast breeder reactors, the nuclear fuel cycle, radiation safety and geological disposal/geoscience; fourteen of which ended in 2003. Of these, seven were related to fast breeder reactors, five to the nuclear fuel cycle, one to radiation safety and one to geological disposal/geoscience. (author)

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

    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

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

    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

  18. Back-end of the research reactor fuel cycle

    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)

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

    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.

  20. CSBB: synthetic biology research at Newcastle University.

    Goñi-Moreno, Angel; Wipat, Anil; Krasnogor, Natalio

    2017-06-15

    The Centre for Synthetic Biology and the Bioeconomy (CSBB) brings together a far-reaching multidisciplinary community across all Newcastle University's faculties - Medical Sciences, Science, Agriculture and Engineering, and Humanities, Arts and Social Sciences. The CSBB focuses on many different areas of Synthetic Biology, including bioprocessing, computational design and in vivo computation, as well as improving understanding of basic molecular machinery. Such breadth is supported by major national and international research funding, a range of industrial partners in the North East of England and beyond, as well as a large number of doctoral and post-doctoral researchers. The CSBB trains the next generation of scientists through a 1-year MSc in Synthetic Biology. © 2017 The Author(s).

  1. Measuring the productivity of university research reactors

    Voth, M.H.

    1989-01-01

    University Research Reactors (URRs) on 33 campuses in the United States provide valuable contributions to academic instruction and research programs. In most cases, there are no alternative diagnostic techniques to supplant the need for a reactor and associated facilities. Since URRs constitute a major financial commitment, it is important that they be operated in a productive manner. Productivity may be defined as the sum of new knowledge generated, existing knowledge transferred to others, and analytical services provided to assist in the generation of new knowledge; another definition of productivity is this sum expressed as a function of the cost incurred. In either case, a consistent measurement is difficult and more qualitative than quantitative. A uniform reporting system has been proposed that defines simplified categories through which meaningful comparisons can be performed

  2. Abstracts and research accomplishments of university coal research projects

    1991-06-01

    The Principal Investigators of the grants supported by the University Coal Research Program were requested to submit abstracts and highlight accomplishments of their projects in time for distribution at a grantees conference. This book is a compilation of the material received in response to the request. Abstracts discuss the following area: coal science, coal surface science, reaction chemistry, advanced process concepts, engineering fundamentals and thermodynamics, environmental science

  3. Abstracts and research accomplishments of university coal research projects

    1991-06-01

    The Principal Investigators of the grants supported by the University Coal Research Program were requested to submit abstracts and highlight accomplishments of their projects in time for distribution at a grantees conference. This book is a compilation of the material received in response to the request. Abstracts discuss the following area: coal science, coal surface science, reaction chemistry, advanced process concepts, engineering fundamentals and thermodynamics, environmental science.

  4. Storage experience in Hungary with fuel from research reactors

    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)

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

    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...

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

    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...

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

    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...

  8. Radiation research in AINSE-affiliated universities

    Sangster, D. R.

    1997-01-01

    The Australian Institute of Nuclear Science and Engineering (AINSE) has enabled research workers from its member universities to make extensive use of the (sometimes unique) radiation facilities at Lucas Heights. This has resulted in a better understanding of the action of gamma, X-ray and electron beam radiation on physical, chemical and biological systems, and of the radical and excited species which are produced. A selection of the ensuing first class publications is described. Over the years the emphasis has changed from the obtaining of a fundamental understanding of the science and the refining of the techniques to utilising these in attacking problems in other fields. Examples are given of the use of radiation chemistry techniques in metal-organic, polymer, excited state and biological chemistry. In radiation biology, the early emphasis on genetics and on the production of chromosomal aberrations by radiation has given way to molecular biology and cancer treatment studies. In all of this, AAEC/ANSTO and CSIRO have played major roles. In addition, AINSE has organised a continuing series of specialist conferences which has facilitated interaction between research groups within the universities and involved other investigators in Australia, New Zealand and the rest of the world

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

    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.

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

    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

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

    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...

  12. Electrocatalysis research for fuel cells and hydrogen production

    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...

  13. Research and Test Reactor Fuel Elements (RTRFE)

    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)

  14. Experimental research of fuel element reliability

    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.)

  15. University of Kentucky Center for Applied Energy Research

    University of Kentucky Center for Applied Energy Research Search Help Research Our Expertise University of Kentucky Center for Applied Energy Research | An Equal Opportunity University All Rights Remediation Power Generation CAER TechFacts CAER Factsheets CAER Affiliations Research Contacts Publications

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

    Dixon, Cathy

    2012-01-01

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

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

    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)

  18. Abstract and research accomplishments of University Coal Research Projects

    NONE

    1995-06-01

    The Principal Investigators of the grants supported by the University Coal Research Program were requested to submit abstracts and highlight accomplishments of their respective projects in time for distribution at a conference on June 13--14, 1995 at Tennessee State University in Nashville, Tennessee. This book is a compilation of the material received in response to that request. For convenience, the 70 grants reported in this book are stored into eight technical areas, Coal Science, Coal Surface Science, Reaction Chemistry, Advanced Process Concepts, Engineering Fundamentals and Thermodynamics, Environmental Science, high Temperature Phenomena, and Special topics. Indexes are provided for locating projects by subject, principal investigators, and contracting organizations. Each extended abstract describes project objectives, work accomplished, significance to the Fossil Energy Program, and plans for the next year.

  19. A university hot laboratory for teaching and research

    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)

  20. Material test reactor fuel research at the BR2 reactor

    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

  1. Health physics aspects of a research reactor fuel shipment

    Dodd, B.; Johnson, A.G.; Anderson, T.V.

    1984-01-01

    In June 1982, 92 irradiated fuel elements were shipped from the Oregon State University TRIGA Reactor to Westinghouse Hanford Corporation to be used in the Fuel Materials Examination Facility, This paper describes some of the health physics aspects of the planning, preparation and procedures associated with that shipment. In particular, the lessons learned are described in order that the benefits of the experience gained may be readily available to other small institutions. (author)

  2. Low enrichment fuel conversion for Iowa State University

    Rohach, A.F.; Hendrickson, R.A.

    1991-08-01

    Work during the reported period was centered primarily in preparation for receiving the LEU fuel and the shipping of the HEU fuel. This included development of procedures and tools for the disassembly process. During the period we held many practice sessions applying these tools and practices to a dummy fuel assembly. The LEU fuel was received on April 10, 1991 and the reactor was shut down on May 3, 1991 for refueling. The twelve HEU fuel assemblies in the UTR-10 reactor core were removed and disassembled during the week of May 6--9, 1991. The disassembly process went smoothly with only a few minor problems. Also during this reporting period several experimental measurements and preventative maintenance tasks were accomplished. Finally procedures and practices have been developed for the new LEU fuel loading and critical experiments which are to be completed during the late summer of 1991

  3. Cost aspects of the research reactor fuel cycle

    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

  4. Researcher Mobility at a US Research-Intensive University: Implications for Research and Internationalization Strategies

    Payumo, Jane G.; Lan, George; Arasu, Prema

    2018-01-01

    This study offers a unique lens on the patterns, productivity, and impact of researcher mobility at a US research-intensive university. Bibliometric data for Washington State University (WSU) was extracted from Elsevier's Scopus database and analyzed for the 10-year period from 2002 to 2012. We grouped researchers into four categories based on…

  5. Research on burning of biomass fuels, KTH

    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.

  6. Growing dimensions. Spent fuel management at research reactors

    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

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

    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)

  8. Research and development of FBR fuel reprocessing in PNC

    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

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

    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

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

    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

  11. Research reactor fuel transport in the U.K

    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.

  12. Revitalizing Qatar's National University. Research Brief

    Steinberg, Paul

    2009-01-01

    Although Qatar University (QU) had been well regarded in the past, its performance had deteriorated by 2003, and the country's leadership was concerned that the university was not meeting Qatar's needs. From 2003 to 2007, the university led a reform process facilitated by RAND and outside experts, which clarified QU's mission and reformed QU's…

  13. CNG INJECTOR RESEARCH FOR DUAL FUEL ENGINE

    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.

  14. Biorefinery and Hydrogen Fuel Cell Research

    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.

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

    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)

  16. Biomedical Engineering Bionanosystems Research at Louisiana Tech University

    Palmer, James; Lvov, Yuri; Hegab, Hisham; Snow, Dale; Wilson, Chester; McDonald, John; Walker, Lynn; Pratt, Jon; Davis, Despina; Agarwal, Mangilal; DeCoster, Mark; Feng, June; Que, Long; O' Neal, Chad; Guilbeau, Eric; Zivanovic, Sandra; Dobbins, Tabbetha; Gold, Scott; Mainardi, Daniela; Gowda, Shathabish; Napper, Stan

    2010-03-25

    The nature of this project is to equip and support research in nanoengineered systems for biomedical, bioenvironmental, and bioenergy applications. Funds provided by the Department of Energy (DoE) under this Congressional Directive were used to support two ongoing research projects at Louisiana Tech University in biomedical, bioenvironmental, and bioenergy applications. Two major projects (Enzyme Immobilization for Large Scale Reactors to Reduce Cellulosic Ethanol Costs, and Nanocatalysts for Coal and Biomass Conversion to Diesel Fuel) and to fund three to five additional seed projects were funded using the project budget. The project funds also allowed the purchase and repair of sophisticated research equipment that will support continued research in these areas for many years to come. Project funds also supported faculty, graduate students, and undergraduate students, contributing to the development of a technically sophisticated work force in the region and the State. Descriptions of the technical accomplishments for each funded project are provided. Biofuels are an important part of the solution for sustainable transportation fuel and energy production for the future. Unfortunately, the country's appetite for fuel cannot be satisfied with traditional sugar crops such as sugar cane or corn. Emerging technologies are allowing cellulosic biomass (wood, grass, stalks, etc.) to also be converted into ethanol. Cellulosic ethanol does not compete with food production and it has the potential to decrease greenhouse gas (GHG) emissions by 86% versus current fossil fuels (current techniques for corn ethanol only reduce greenhouse gases by 19%). Because of these advantages, the federal government has made cellulosic ethanol a high priority. The Energy Independence and Security Act of 2007 (EISA) requires a minimum production of at least 16 billion gallons of cellulosic ethanol by 2022. Indeed, the Obama administration has signaled an ambitious commitment of achieving

  17. Thermal fuel research and development facilities in BNFL

    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

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

    2009-12-01

    A large variety of research reactor spent fuel with different fuel meats, different geometries and different enrichments in 235 U are presently stored underwater in basins located around the world. More than 90% of these fuels are clad in aluminium or aluminium based alloys that are notoriously susceptible to corrosion in water of less than optimum quality. Some fuel is stored in the reactor pools themselves, some in auxiliary pools (or basins) close to the reactor and some stored at away-from-reactor pools. Since the early 1990s, when corrosion induced degradation of the fuel cladding was observed in many of the pools, corrosion of research reactor aluminium clad spent nuclear fuel stored in light water filled basins has become a major concern, and programmes were implemented at the sites to improve fuel storage conditions. The IAEA has since then established a number of programmatic activities to address corrosion of research reactor aluminium clad spent nuclear fuel in water. Of special relevance was the Coordinated Research Project (CRP) on Corrosion of Research Reactor Aluminium Clad Spent Fuel in Water (Phase I) initiated in 1996, whose results were published in IAEA Technical Reports Series No. 418. At the end of this CRP it was considered necessary that a continuation of the CRP should concentrate on fuel storage basins that had demonstrated significant corrosion problems and would therefore provide additional insight into the fundamentals of localized corrosion of aluminium. As a consequence, the IAEA started a new CRP entitled Corrosion of Research Reactor Aluminium Clad Spent Fuel in Water (Phase II), to carry out more comprehensive research in some specific areas of corrosion of aluminium clad spent nuclear fuel in water. In addition to this CRP, one of the activities under IAEA's Technical Cooperation Regional Project for Latin America Management of Spent Fuel from Research Reactors (2001-2006) was corrosion monitoring and surveillance of research

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

    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.

  20. Situation of test and research reactors' spent fuels

    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)

  1. Research reactor fuel development at AECL

    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)

  2. Research reactor fuel development at AECL

    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)

  3. Research Establishment progress report 1978 - uranium fuel cycle

    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

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

    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)

  5. Researches at the University of Tokyo fast neutron sources reactor, YAYOI

    Koshizuka, S.; Oka, Y.; Saito, I.

    1992-01-01

    The Fast neutron source reactor YAYOI was critical in 1971 at the Nuclear Engineering Research Laboratory, the Faculty of Engineering, the University of Tokyo (UTNL). The core is fueled with the enriched uranium surrounded by the depleted uranium. YAYOI is the first fast reactor in Japan. Many types of studies have been carried out by the researchers of the University of Tokyo in these 20 years. It also contributed to the Japan's national project of developing fast breeder reactors. The reactor is opened to the visiting researchers from universities and research institutes. YAYOI has also been utilized for education of undergraduate and graduate students of the Department of Nuclear Engineering of the University of Tokyo. The present paper briefly summerizes past and present researchers. (author)

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

    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)

  7. A Research Mapping of Dropout Phenomena at Universities

    Larsen, Michael Søgaard; Larsen, Malene; Kristensen, Rune

    This is a systematic research mapping of the research which can provide reliable answers to the questions posed in the title at European Universities.......This is a systematic research mapping of the research which can provide reliable answers to the questions posed in the title at European Universities....

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

    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)

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

    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)

  10. [Research and workshop on alternative fuels for aviation. Final report

    NONE

    1999-09-01

    The Renewable Aviation Fuels Development Center (RAFDC) at Baylor University was granted U. S. Department of Energy (US DOE) and Federal Aviation Administration (FAA) funds for research and development to improve the efficiency in ethanol powered aircraft, measure performance and compare emissions of ethanol, Ethyl Tertiary Butyl Ether (ETBE) and 100 LL aviation gasoline. The premise of the initial proposal was to use a test stand owned by Engine Components Inc. (ECI) based in San Antonio, Texas. After the grant was awarded, ECI decided to close down its test stand facility. Since there were no other test stands available at that time, RAFDC was forced to find additional support to build its own test stand. Baylor University provided initial funds for the test stand building. Other obstacles had to be overcome in order to initiate the program. The price of the emission testing equipment had increased substantially beyond the initial quote. Rosemount Analytical Inc. gave RAFDC an estimate of $120,000.00 for a basic emission testing package. RAFDC had to find additional funding to purchase this equipment. The electronic ignition unit also presented a series of time consuming problems. Since at that time there were no off-the-shelf units of this type available, one had to be specially ordered and developed. FAA funds were used to purchase a Super Flow dynamometer. Due to the many unforeseen obstacles, much more time and effort than originally anticipated had to be dedicated to the project, with much of the work done on a volunteer basis. Many people contributed their time to the program. One person, mainly responsible for the initial design of the test stand, was a retired engineer from Allison with extensive aircraft engine test stand experience. Also, many Baylor students volunteered to assemble the. test stand and continue to be involved in the current test program. Although the program presented many challenges, which resulted in delays, the RAFDC's test

  11. Assessment of Research Needs for Advanced Fuel Cells

    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.

  12. Basic research on cermet nuclear fuel

    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.)

  13. University Research Initiative Program for Combat Readiness

    1999-05-01

    microscope image of one of the lenses. This array was selected for testing because it is fabricated in a relatively inexpensive polyacrylic material, the...potent analogues of the potassium -sparing diuretic, amiloride. However, our results 179 University Reasearch Initiative for Combat Readiness Annual Report...for Combat Readiness Annual Report for the period June 1, 1998 - June 30, 1999 Roger H. Sawyer University of South Carolina Columbia, SC 29208 May

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

    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. The JAERI and Universities joint project research reports on the 4th joint research project between JAERI and Universities on backend chemistry

    NONE

    2003-02-01

    In the Joint Research Project between JAERI and Universities on Backend Chemistry, the 4th-term researches of it were performed on sixteen themes from April of 1999 to March of 2001 under the four categories, i.e. Nuclear-chemistry and physical-chemistry properties of actinides', 'Solid state chemistry and nuclear fuel engineering of actinides', 'Solution chemistry and technologies for separation and analysis of actinides' and Treatment of radioactive waste and environmental chemistry'. The present report compiled the papers contributed to the Joint Research Project. (author)

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

    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.)

  17. Alternative Fuels Data Center: James Madison University Teaches Alternative

    Alternative Fuels Sept. 16, 2017 Photo of a truck Phoenix Utility Fleet Drives Smarter with Biodiesel Aug. 26 Cooking Oil Powers Biodiesel Vehicles in Rhode Island July 14, 2017 Photo of a truck Idaho Transports Mail Home Runs on Biodiesel in North Carolina June 9, 2017 Photo of a bus New Hampshire Cleans up with

  18. Measuring recent research performance for Chinese universities using bibliometric methods

    Zhu, Jia

    2014-07-29

    This paper focuses on measuring the academic research performance of Chinese universities by using Scopus database from 2007 to 2010. We have provided meaningful indicators to measure the research performance of Chinese universities as compared to world class universities of the US and the European region. Using these indicators, we first measure the quantity and quality of the research outcomes of the universities and then examine the internationalization of research by using international collaborations, international citations and international impact metrics. Using all of this data, we finally present an overall score called research performance point to measure the comprehensive research strength of the universities for the selected subject categories. The comparison identifies the gap between Chinese universities and top-tier universities from selected regions across various subject areas. We find that Chinese universities are doing well in terms of publication volume but receive less citations from their published work. We also find that the Chinese universities have relative low percentage of publications at high impact venues, which may be the reason that they are not receiving more citations. Therefore, a careful selection of publication venues may help the Chinese universities to compete with world class universities and increase their research internationalization. © 2014 Akadémiai Kiadó, Budapest, Hungary.

  19. A basic research on the transient behavior for a metallic fuel FBR

    Baba, Mamoru; Hirano, Go; Kawada, Ken-ichi; Niwa, Hajime

    1999-03-01

    A metallic fuel with novel design has received great deal of interest recently as an option of advanced fuel to be substituted MOX fuel, however, the behavior at the transient has not been studied in many aspects. Therefore, for the purpose to show the basic tendency of the behavior and released energy at CDA (core disruptive accident) for a metallic fuel FBR and to prepare the basic knowledge for consideration of the adoption of the advanced fuel, Tohoku university and Power Reactor and Nuclear Fuel Development Corporation have made a joint research entitled 'A basic research on the transient behavior for a metallic fuel FBR'. The results are the following. (1) Target and Results of analysis: The accident initiator considered is a LOF accident without scram. The LOF analysis was performed for a metallic fuel 600 MWe homogeneous two region core at the beginning of cycle, both for an ordinary metallic fuel core and for a metallic fuel core with ZrH pins. It was necessary mainly to change the constants of input parameters to apply the code for the analysis of a metallic fueled reactor. These changes were made by assuming appropriate models. Basic LOF cases and all blackout case that assumed using electromagnetic pumps were analyzed. The results show that the basic LOF cases for a metallic fuel core and all the cases for a metallic fuel core with ZrH pins could be avoided to become prompt-critical, and mildly transfer to the transition phase. It is shown that the moderator is quite elective to mitigate the accident at the initiation phase. However, it is necessary to analyze the transition phase to know if the re-criticality is totally avoided after the initiation phase. (2) Improvement of CDA initiation phase analysis code: At present, it is difficult for the code to adapt to the large scale material movement in the core at the transient. Therefore, the nuclear calculation model in the code was improved by using the adiabatic space dependent kinetics, and examined

  20. Research reactors spent fuel management in the Nuclear Research Institute Rez

    Rychecky, J.

    2001-01-01

    In Czech Republic 3 research and testing nuclear reactors are operated at present time, with the biggest one being the Nuclear Research Institute (NRI) reactor LVR-15, operated with maximum power 10 MW. This reactor serves as a radiation source for material testing, producing of ionizing radiation sources, theoretical studies, and, most recently, for boron neutron capture therapy. Another NRI reactor LR-0 is a reactor of zero power used mainly for the studies of WWER 1000 spent fuel criticality. For training of students the reactor called VRABEC (VR-1), operated also with very low power, serves since 1990 at the Faculty of Nuclear Engineering, of Czech Technical University. The similar testing type reactor (SR-0), already decommissioned, was also used since 1974 to 1989 in Skoda, Nuclear Machinery, Plzen. This contribution summarizes the present state of the spent fuel (SF) management of these nuclear reactors. As the SF management is different for very low or zero power reactors and power reactors, the first type will be only briefly discussed, and then the main attention will be devoted to SF management of the NRI experimental reactor LVR-15

  1. Research reactors spent fuel management in the Nuclear Research Institute Rez

    Rychecky, J. [Nuclear Research Institute, 25068 Rez (Czech Republic)

    2001-07-01

    In Czech Republic 3 research and testing nuclear reactors are operated at present time, with the biggest one being the Nuclear Research Institute (NRI) reactor LVR-15, operated with maximum power 10 MW. This reactor serves as a radiation source for material testing, producing of ionizing radiation sources, theoretical studies, and, most recently, for boron neutron capture therapy. Another NRI reactor LR-0 is a reactor of zero power used mainly for the studies of WWER 1000 spent fuel criticality. For training of students the reactor called VRABEC (VR-1), operated also with very low power, serves since 1990 at the Faculty of Nuclear Engineering, of Czech Technical University. The similar testing type reactor (SR-0), already decommissioned, was also used since 1974 to 1989 in Skoda, Nuclear Machinery, Plzen. This contribution summarizes the present state of the spent fuel (SF) management of these nuclear reactors. As the SF management is different for very low or zero power reactors and power reactors, the first type will be only briefly discussed, and then the main attention will be devoted to SF management of the NRI experimental reactor LVR-15.

  2. The impact of science shops on university research and education

    Hende, Merete; Jørgensen, Michael Søgaard

    This report discusses the impact from university-based science shops on curricula and research. Experience from science shops show that besides assisting citizen groups, science shops can also contribute to the development of university curricula and research. This impact has been investigated...... through the SCIPAS questionnaire sent out to science shops and through follow-up interviews with employees from nine different university-based science shops and one university researcher. Not all the cases call themselves science shops, but in the report the term 'science shop' will be used most...... way or the other has had impact on university curricula and/or research. The analysis and the case studies have theoretically been based on literature on universities and education and research as institutions and a few articles about the impact of science shops on education and research. The analysis...

  3. Mississippi State University Cooling, Heating, and Power (Micro-CHP) and Bio-Fuel Center

    Mago, Pedro [Mississippi State Univ., Mississippi State, MS (United States); Newell, LeLe [Mississippi State Univ., Mississippi State, MS (United States)

    2014-01-31

    Between 2008 and 2014, the U.S. Department of Energy funded the MSU Micro-CHP and Bio-Fuel Center located at Mississippi State University. The overall objective of this project was to enable micro-CHP (micro-combined heat and power) utilization, to facilitate and promote the use of CHP systems and to educate architects, engineers, and agricultural producers and scientists on the benefits of CHP systems. Therefore, the work of the Center focused on the three areas: CHP system modeling and optimization, outreach, and research. In general, the results obtained from this project demonstrated that CHP systems are attractive because they can provide energy, environmental, and economic benefits. Some of these benefits include the potential to reduce operational cost, carbon dioxide emissions, primary energy consumption, and power reliability during electric grid disruptions. The knowledge disseminated in numerous journal and conference papers from the outcomes of this project is beneficial to engineers, architects, agricultural producers, scientists and the public in general who are interested in CHP technology and applications. In addition, more than 48 graduate students and 23 undergraduate students, benefited from the training and research performed in the MSU Micro-CHP and Bio-Fuel Center.

  4. University Teacher Educators' Research Engagement: Perspectives from Saudi Arabia

    Borg, Simon; Alshumaimeri, Yousif

    2012-01-01

    This paper examines university teacher educators' engagement with and in educational research. Survey results collected from eighty-two teacher educators at a leading university in Saudi Arabia pointed to modest levels of research activity and also suggested that these individuals held largely technical views of what research is. Their assessments…

  5. An Analysis of Female Research Productivity in Nigerian Universities

    Ogbogu, Christiana O.

    2009-01-01

    This study examines the research output of female staff and the factors that affect their research productivity in the Nigerian university system. The study was carried out with a view to promoting strategies that will enhance productivity and increase the research output of female staff in Nigerian universities. The study adopted a survey…

  6. Key Strategies for Building Research Capacity of University Faculty Members

    Huenneke, Laura F.; Stearns, Diane M.; Martinez, Jesse D.; Laurila, Kelly

    2017-01-01

    Universities are under pressure to increase external research funding, and some federal agencies offer programs to expand research capacity in certain kinds of institutions. However, conflicts within faculty roles and other aspects of university operations influence the effectiveness of particular strategies for increasing research activity. We…

  7. Status of USNRC research on fuel behavior under accident conditions

    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

  8. Career Plans of Novice University Teachers: The Research Perspective

    Wiegerová Adriana

    2017-04-01

    Full Text Available Introduction: The career trajectories of young university teachers have been a relatively frequent research target in North American and Western European countries but an entirely neglected topic of the Czech and Slovak educational research. This paper’s ambition is to narrow the gap. The research goal is to describe one aspect of career advancement of young university teachers - their professional plans after their entry to an academic position at a university after completion of their doctoral studies.

  9. Criticality safety research on nuclear fuel cycle facility

    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)

  10. Fuel enrichment reduction for heavy water moderated research reactors

    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)

  11. Basic research and industrialization of CANDU advanced fuel

    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.

  12. Basic research and industrialization of CANDU advanced fuel

    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

  13. Center for Transportation Research | The University of Tennessee, Knoxville

    IRIS WEB ACCOUNTS PASSWORDS Libraries UNIVERSITY LIBRARIES AGRICULTURE & VET MED LAW MEDICAL MUSIC transportation research, service, and training needs of state and local government, business, and industry in

  14. University of Washington Center for Child Environmental Health Risks Research

    Federal Laboratory Consortium — The theme of the University of Washington based Center for Child Environmental Health Risks Research (CHC) is understanding the biochemical, molecular and exposure...

  15. Underlying chemistry research for the nuclear fuel waste management program

    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

  16. Safety research in nuclear fuel cycle at PNC

    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)

  17. Safety research in nuclear fuel cycle at PNC

    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)

  18. Experience and advantages in implementation of educational program in network form at Department «Closed nuclear fuel cycle Technologies» of National Research Nuclear University «MEPhI»

    Beygel‧, A. G.; Kutsenko, K. V.; Lavrukhin, A. A.; Magomedbekov, E. P.; Pershukov, V. A.; Sofronov, V. L.; Tyupina, E. A.; Zhiganov, A. N.

    2017-01-01

    The experience of implementation of the basic educational program of magistracy on direction «Nuclear Physics and Technologies» in a network form is presented. Examples of joint implementation of the educational process with employers organizations, other universities and intranet mobility of students are given.

  19. Experience and advantages in implementation of educational program in network form at Department «Closed nuclear fuel cycle Technologies» of National Research Nuclear University «MEPhI»

    Beygel', A G; Kutsenko, K V; Lavrukhin, A A; Pershukov, V A; Sofronov, V L; Tyupina, E A; Zhiganov, A N; Magomedbekov, E P

    2017-01-01

    The experience of implementation of the basic educational program of magistracy on direction «Nuclear Physics and Technologies» in a network form is presented. Examples of joint implementation of the educational process with employers organizations, other universities and intranet mobility of students are given. (paper)

  20. Funding the Technology of a Research University

    Ostrom-Blonigen, Jean

    2013-01-01

    Using the central information technology unit (CITU) on the North Dakota State University (NDSU) campus, this project triangulated two independent studies in an effort to converge data findings. The studies were conducted in an effort to determine whether CITU's budget constraints were known to its stakeholders and how the extended use of the…

  1. University of Maryland MRSEC - Research: Seed 2

    operation. This site remains as a history of the center, but will not be actively maintained. University of . Crystals are made up of layers, or "planes" of atoms, perfectly stacked in an ordered pattern . Because this surface has been cut at a slight angle to the crystal planes, it appears "stepped"

  2. University of Maryland MRSEC - Research: IRG1

    operation. This site remains as a history of the center, but will not be actively maintained. University of . Crystals are made up of layers, or "planes" of atoms, perfectly stacked in an ordered pattern . Because this surface has been cut at a slight angle to the crystal planes, it appears "stepped"

  3. University of Maryland MRSEC - Research: Publications

    operation. This site remains as a history of the center, but will not be actively maintained. University of . Crystals are made up of layers, or "planes" of atoms, perfectly stacked in an ordered pattern . Because this surface has been cut at a slight angle to the crystal planes, it appears "stepped"

  4. University of Maryland MRSEC - Research: Seed 3

    operation. This site remains as a history of the center, but will not be actively maintained. University of . Crystals are made up of layers, or "planes" of atoms, perfectly stacked in an ordered pattern . Because this surface has been cut at a slight angle to the crystal planes, it appears "stepped"

  5. University of Maryland MRSEC - Research: Seed 1

    operation. This site remains as a history of the center, but will not be actively maintained. University of . Crystals are made up of layers, or "planes" of atoms, perfectly stacked in an ordered pattern . Because this surface has been cut at a slight angle to the crystal planes, it appears "stepped"

  6. University of Maryland MRSEC - Research: IRG2

    operation. This site remains as a history of the center, but will not be actively maintained. University of . Crystals are made up of layers, or "planes" of atoms, perfectly stacked in an ordered pattern . Because this surface has been cut at a slight angle to the crystal planes, it appears "stepped"

  7. Researcher might have found answer to 'birth of the universe'

    2003-01-01

    A National Taiwan University (NTU) research team has discovered a new physical phenomenon that could challenge the well-accepted theory about the birth of the universe. However,Lee Shih-chang, a researcher at Academia Sinica's Institute of Physics, said the new scientific research results will be accepted only after an academic paper detailing the research process and conclusions is released and the research results are verified by experts in the field.

  8. Key Strategies for Building Research Capacity of University Faculty Members.

    Huenneke, Laura F; Stearns, Diane M; Martinez, Jesse D; Laurila, Kelly

    2017-12-01

    Universities are under pressure to increase external research funding, and some federal agencies offer programs to expand research capacity in certain kinds of institutions. However, conflicts within faculty roles and other aspects of university operations influence the effectiveness of particular strategies for increasing research activity. We review conventional approaches to increasing research, focusing on outcomes for individual faculty members and use one federally-funded effort to build cancer-related research capacity at a public university as an example to explore the impact of various strategies on research outcomes. We close with hypotheses that should be tested in future formal studies.

  9. Research on assurance system of nuclear fuel supply (Contract research)

    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)

  10. Research on assurance system of nuclear fuel supply (Contract research)

    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)

  11. Some observations in university participation in nuclear engineering research

    Eickhoff, K.G.; Hill, K.M.

    1980-01-01

    A general discussion is presented on the kinds of problem which with suitable co-ordination would form appropriate topics for university research. R and D work can be done in-house, or with an industrial contractor, or with a university or polytechnic. The criteria are examined. Involvement by universities and polytechnics, and topics and location, are considered further. (U.K.)

  12. HANARO Neutron Radiography Facility and Fuel Cell Research

    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

  13. The University of Missouri Research Reactor HEU to LEU conversion project status

    McKibben, James C; Kutikkad, Kiratadas; Foyto, Leslie P; Peters, Nickie J; Solbrekken, Gary L; Kennedy, John [University of Missouri Research Reactor, Missouri (United States); Stillman, John A; Feldman, Earl E; Tzanos, Constantine P; Stevens, John G [Argonne National Laboratory, Argonne, Illinois (United States)

    2012-03-15

    The University of Missouri Research Reactor (MURR) is one of five U.S. high performance research and test reactors that are actively collaborating with the U.S. Department of Energy (DOE) to find a suitable low-enriched uranium (LEU) fuel replacement for the currently required highly-enriched uranium (HEU) fuel. A conversion feasibility study based on U-10Mo monolithic LEU fuel was completed in 2009. It was concluded that the proposed LEU fuel assembly design, in conjunction with an increase in power level from 10 to 12 MWth, will (1) maintain safety margins during operation, (2) allow operating fuel cycle lengths to be maintained for efficient and effective use of the facility, and (3) preserve an acceptable level and spectrum of key neutron fluxes to meet the scientific mission of the facility. The MURR and Argonne National Laboratory (ANL) team is continuing to work toward realization of the conversion. The 'Preliminary Safety Analysis Report Methodologies and Scenarios for LEU Conversion of MURR' was completed in June 2011. This report documents design parameter values critical to the Fuel Development (FD), Fuel Fabrication Capability (FFC) and Hydromechanical Fuel Test Facility (HMFTF) projects. The report also provides a preliminary evaluation of safety analysis techniques and data that will be needed to complete the fuel conversion Safety Analysis Report (SAR), especially those related to the U-10Mo monolithic LEU fuel. Specific studies are underway to validate the proposed path to an LEU fuel conversion. Coupled fluid-structure simulations and experiments are being conducted to understand the hydrodynamic plate deformation risk for 0.965 mm (38 mil) thick fuel plates. Methodologies that were recently developed to answer the U.S. Nuclear Regulatory Commission (NRC) Request for Additional Information (RAI) regarding the MURR 2006 relicensing submittal will be used in the LEU conversion effort. Transition LEU fuel elements that will have a minimal impact on

  14. Research on a Scania 11 liter ethanol fueled bus engine

    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

  15. University-Industry Collaboration in IS Research

    Schubert, Petra; Bjørn-Andersen, Niels

    2012-01-01

    of successful modes of collaboration. In this paper, we present the findings of the first qualitative in‐depth phase, in which we inter‐ viewed nine experienced researchers in order to understand the phenomenon of university‐ industry collaboration in the context of different research backgrounds. The findings...... from the preliminary interviews show that researchers have very differing individual preferences regarding the ideal setup of such collaborative research projects. They also show that design research and case study are the most common research methods in such projects. While peer‐ reviewed conference...... papers and journal articles are the most popular forms of academic output, reports and sessions with managers are the prevalent output for industry partners. This work is a precursor to a larger survey, which will allow us to study correlations between characteristics of researcher/project type...

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

    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)

  17. Nuclear criticality assessment of Oak Ridge research fuel element storage

    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

  18. Annual report 1984. Nuclear fuel research department

    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

  19. ENS RRFM 2005: 9th international topical meeting on research reactor fuel management. Transactions

    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

  20. Research-University Governance in Thailand: The Case of Chulalongkorn University

    Rungfamai, Kreangchai

    2017-01-01

    This specific case of Chulalongkorn University (CU), Thailand, is useful to readers who are interested in comparative aspect of the experiences of research universities in the South East Asian context. This paper aims to provide a description of the environments, changes, and university stakeholders' perceptions in terms of governance arrangements…

  1. Difficulties Encountered by Academicians in Academic Research Processes in Universities

    Yalçin, Sinan; Altun Yalçin, Sema

    2017-01-01

    This present research, aimed to determine the occasions, which the academicians encountered during the academic research process and how these affect the research process, was prepared as a case study pattern among the qualitative research methods. 34 academicians, who were working in a university in Turkey, participated in the research. The data…

  2. TEL4Health research at University College Cork (UCC)

    Drachsler, Hendrik

    2013-01-01

    Drachsler, H. (2013, 12 May). TEL4Health research at University College Cork (UCC). Invited talk given at Application of Science to Simulation, Education and Research on Training for Health Professionals Centre (ASSERT for Health Care), Cork, Ireland.

  3. University of Maryland Energy Research Center |

    breakthroughs into commercial, clean energy solutions. The Clark School Celebrates Women's History Month The Clark School is featuring our female engineering faculty members throughout March. UMD Researchers

  4. Fuel isolation research for the Canadian nuclear fuel waste management program

    1982-06-01

    This document is intended to give a broad outline of the Fuel Isolatikn program and to indicate how this program fits into the overall framework of the Canadian Nuclear Fuel Waste Management Program. Similar activities in other countries are described, and the differences in philosophy behind these and the Canadian program are highlighted. A program plan is presented that outlines the development of research programs that contribute to the safety assessment of the disposal concept and the development of technology required for selection and optimization of a feasible fuel isolation system. Some indication of the work that might take place beyond concept assessment, at the end of the decade, is also given. The current program is described in some detail, with emphasis on what the prkgram has achieved to date and hopes to achieve in the future for the concept assessment phase of the waste management program. Finally, some major capital facilities associated with the fuel isolation program are described

  5. Spent fuel performance assessment and research. Final report of a co-ordinated research project on Spent Fuel Performance Assessment and Research (SPAR) 1997-2001

    2003-03-01

    The report provides an overview of technical issues related to spent fuel wet and dry storage and summarizes the objectives and major findings of research, carried out within the framework of the Coordinated Research Program. Included are the fuel integrity aspects, fuel degradation mechanisms in dry and wet storage, behaviour of storage facility components (metallic components, reinforced concrete). Also included are issues related to long-term storage and monitoring technologies and techniques. Country reports on research projects within the SPAR Coordinated Research Program is presented. A brief history is given on the history of the BEFAST and SPAR Coordinated Research Projects

  6. Spent fuel performance assessment and research. Final report of a co-ordinated research project on Spent Fuel Performance Assessment and Research (SPAR) 1997-2001

    NONE

    2003-03-01

    The report provides an overview of technical issues related to spent fuel wet and dry storage and summarizes the objectives and major findings of research, carried out within the framework of the Coordinated Research Program. Included are the fuel integrity aspects, fuel degradation mechanisms in dry and wet storage, behaviour of storage facility components (metallic components, reinforced concrete). Also included are issues related to long-term storage and monitoring technologies and techniques. Country reports on research projects within the SPAR Coordinated Research Program is presented. A brief history is given on the history of the BEFAST and SPAR Coordinated Research Projects.

  7. Fuel Cycle Research and Development. Technical Monthly - March 2012

    Miller, Michael C.

    2012-01-01

    meeting. Kenneth Dayman, the graduate student from University of Texas, completed an initial draft of his master's thesis. His research will contribute to the multivariate classifier currently under development. Sarah Bender, the graduate student from Pennsylvania State University, presented her work on a poster and in a conference paper at the MARC IX meeting. A mass balance flowsheet for the fast reactor fuel was completed and a model simulation is scheduled to begin construction next month. The development of a mass balance flowsheet for light water reactor fuel will predict the behavior of the separation process using mathematical functions. The completed flowsheet will be utilized as the basis for constructing the model simulation for the electrochemical separations. Comments and review of the model from the MPACT Working Group meeting have been used to evaluate updates to the EChem model. A preliminary physical security layout has been developed in ATLAS. Thermal stability tests for high temperature microfluidic interconnections were completed on all compounds tested for bonding strength. An interconnection strategy was determined based on these results that we expect will allow for operation at 400C in the first generation of sampling systems. Design of the sampling system using the chosen interconnections was initiated, with handoff to an external foundry for fabrication based on ANL specified process conditions expected by the middle of the month. Monte Carlo simulations of the sampling system were conducted under conditions of realistic sampling size distributions, electrorefiner inhomogeneity distributions, and detector efficiencies. These simulations were used to establish a baseline limit of detection for system operation, assuming an on-line separation step is conducted before detection. Sensor for measuring density and depth of molten electrolyte - The procurement effort continued. 80% of the components ordered to assemble the double bubbler have arrived at

  8. Spent Fuel Performance Assessment and Research. Final Report of a Coordinated Research Project (SPAR-II)

    NONE

    2012-07-01

    As storage of spent fuel has become a key technology in spent fuel management, wet and dry storage have become mature technologies and continue to demonstrate good performance. Increased spent fuel storage capacity in combination with longer storage durations will be needed over the foreseeable future as many countries have delayed their decision on spent fuel disposal or reprocessing. Extended spent fuel storage is, and will remain, an important activity for all countries with nuclear power programmes. A number of countries are planning or have already initiated research programmes on spent fuel storage performance, and there is a continuing benefit in exchanging spent fuel storage experience of the Member States in order to build a comprehensive technology knowledge base. Potential degradation mechanisms that may affect cladding integrity during wet storage are uniform corrosion, pitting, galvanic, and microbiologically-influenced corrosion. Potential degradation mechanisms that may affect cladding integrity during dry storage and subsequent handling and transportation operations are air oxidation, thermal creep, stress corrosion cracking (SCC), delayed hydride cracking (DHC), hydride re-orientation, hydrogen migration and re-distribution. Investigations carried out so far indicate that from the degradation mechanisms that may affect the integrity of spent fuel assembly/bundle structure during interim storage, hydride re-orientation has the potential to impair the ability of the cladding to effectively withstand potentially adverse mechanical challenges resulting from handling or transportation accidents. Fuel integrity issues are related to the definition and criteria of fuel integrity, failure classification, packaging and retrieval of damaged fuel and transport of damaged fuel assemblies. Various monitoring technologies have been developed and used to confirm the continued spent fuel integrity during storage or to provide an early indication of developing

  9. Spent Fuel Performance Assessment and Research. Final Report of a Coordinated Research Project (SPAR-II)

    2012-01-01

    As storage of spent fuel has become a key technology in spent fuel management, wet and dry storage have become mature technologies and continue to demonstrate good performance. Increased spent fuel storage capacity in combination with longer storage durations will be needed over the foreseeable future as many countries have delayed their decision on spent fuel disposal or reprocessing. Extended spent fuel storage is, and will remain, an important activity for all countries with nuclear power programmes. A number of countries are planning or have already initiated research programmes on spent fuel storage performance, and there is a continuing benefit in exchanging spent fuel storage experience of the Member States in order to build a comprehensive technology knowledge base. Potential degradation mechanisms that may affect cladding integrity during wet storage are uniform corrosion, pitting, galvanic, and microbiologically-influenced corrosion. Potential degradation mechanisms that may affect cladding integrity during dry storage and subsequent handling and transportation operations are air oxidation, thermal creep, stress corrosion cracking (SCC), delayed hydride cracking (DHC), hydride re-orientation, hydrogen migration and re-distribution. Investigations carried out so far indicate that from the degradation mechanisms that may affect the integrity of spent fuel assembly/bundle structure during interim storage, hydride re-orientation has the potential to impair the ability of the cladding to effectively withstand potentially adverse mechanical challenges resulting from handling or transportation accidents. Fuel integrity issues are related to the definition and criteria of fuel integrity, failure classification, packaging and retrieval of damaged fuel and transport of damaged fuel assemblies. Various monitoring technologies have been developed and used to confirm the continued spent fuel integrity during storage or to provide an early indication of developing

  10. Sustainable Disposal of Edible Food Byproducts at University Research Farms

    Baldwin, Sherill; Chung, Kimberly

    2007-01-01

    Purpose: Research at agricultural universities often generates food crops that are edible by-products of the research process. The purpose of this paper is to explore the factors that affect decision-making around the disposal of these crops. Understanding decision-making suggests how universities might include food crop production into campus…

  11. Nuclear science and engineering education at a university research reactor

    Loveland, W.

    1993-01-01

    The role of an on-site irradiation facility in nuclear science and engineering education is examined. Using the example of a university research reactor, the use of such devices in laboratory instruction, public outreach programs, special instructional programs, research, etc. is discussed. Examples from the Oregon State University curriculum in nuclear chemistry, nuclear engineering and radiation health are given. (author) 1 tab

  12. Return of TRIGA fuel from the Medical University of Hanover (MHH) to the United States

    Hampel, Gabriele; Klaus, Uwe; Schmidt, Thomas

    1999-01-01

    The Medical University of Hanover (MHH) returned its TRIGA fuel to the United States in the summer of 1999. This paper deals with the procedure for handling the fuel elements within and outside the reactor facility. It describes the dry loading technology, taking into account the special conditions relevant to the MHH. It also includes the time scale for both the various steps of the procedure and the entire process, as well as the main results of the radiological surveys. (author)

  13. Research resources for Drosophila: the expanding universe.

    Matthews, Kathleen A; Kaufman, Thomas C; Gelbart, William M

    2005-03-01

    Drosophila melanogaster has been the subject of research into central questions about biological mechanisms for almost a century. The experimental tools and resources that are available or under development for D. melanogaster and its related species, particularly those for genomic analysis, are truly outstanding. Here we review three types of resource that have been developed for D. melanogaster research: databases and other sources of information, biological materials and experimental services. These resources are there to be exploited and we hope that this guide will encourage new uses for D. melanogaster information, materials and services, both by those new to flies and by experienced D. melanogaster researchers.

  14. The basic research on the CDA initiation phase for a metallic fuel FBR

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

    1998-03-01

    A metallic fuel with novel design has received great deal of interest recently as an option of advanced fuel to be substituted MOX fuel, however, the behavior at the transient has not been studied in many aspects. Therefore, for the purpose to show the basic tendency of the behavior and released energy at CDA (core disruptive accident) for a metallic fuel FBR and to prepare the basic knowledge for consideration of the adoption of the advanced fuel, Tohoku University and Power Reactor and Nuclear Fuel Development Corporation have made a joint research entitled. (1) Target and Results of analysis: The accident initiator considered is a LOF accident with ATWS. The LOF analysis was performed for a metallic fuel 600 MWe homogeneous two region core at the beginning of cycle, both for an ordinary metallic fuel core and for a metallic fuel core with ZrH pins. It was necessary mainly to change the constants of input parameters to apply the code for the analysis of a metallic fueled reactor. These changes were made by assuming appropriate models. Basic LOF cases and all blackout case that assumed using electromagnetic pumps were analyzed. The results show that the basic LOF cases for a metallic fuel core and all the cases for a metallic fuel core with ZrH pins could be avoided to become prompt-critical, and mildly transfer to the transient phase. (2) Improvement of CDA initiation phase analysis code: At present, it is difficult for the code to adapt to the large material movement to in the core at the transient. Therefore, the nuclear calculation model in the code was improved by using the adiabatic space dependent kinetics. The results of a sample case, that is a metallic fueled core at the beginning of cycle, show this improvement is appropriate. (3) Conclusion: The behavior at CDA of a metallic fueled core of a fast reactor was analyzed using the CDA initiation phase analysis code and the knowledge of the important characteristics at the CDA initiation phase was obtained

  15. Testing of a transport cask for research reactor spent fuel

    Mourao, Rogerio P.; Silva, Luiz Leite da; Miranda, Carlos A.; Mattar Neto, Miguel; Quintana, Jose F.A.; Saliba, Roberto O.; Novara, Oscar E.

    2011-01-01

    Since the beginning of the last decade three Latin American countries which operate research reactors - Argentina, Brazil and Chile - have been joining efforts to improve the regional capability in the management of spent fuel elements from the reactors operated in the region. As a step in this direction, a packaging for the transport of irradiated fuel from research reactors was designed by a tri-national team and a half-scale model for MTR fuel constructed in Argentina and tested in Brazil. Two test campaigns have been carried out so far, covering both normal conditions of transportation and hypothetical accident conditions. Although the specimen has not successfully performed the tests, its overall performance was considered very satisfactory, and improvements are being introduced to the design. A third test sequence is planned for 2011. (author)

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

    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

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

    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)

  18. Princeton University High Energy Physics Research

    Marlow, Daniel R. [Princeton Univ., NJ (United States)

    2015-06-30

    This is the Final Report on research conducted by the Princeton Elementary Particles group over the approximately three-year period from May 1, 2012 to April 30, 2015. The goal of our research is to investigate the fundamental constituents of matter, their fields, and their interactions; to understand the properties of space and time; and to study the profound relationships between cosmology and particle physics. During the funding period covered by this report, the group has been organized into a subgroup concentrating on the theory of particles, strings, and cosmology; and four subgroups performing major experiments at laboratories around the world: CERN, Daya Bay, Gran Sasso as well as detector R\\&D on the Princeton campus. Highlights in of this research include the discovery of the Higgs Boson at CERN and the measurement of $\\sin^22\\theta_{13}$ by the Daya Bay experiment. In both cases, Princeton researchers supported by this grant played key roles.

  19. Status of the University of Missouri-Columbia Research Reactor upgrade

    McKibben, J C; Edwards, Jr, C B; Meyer, Jr, W A [MU Research Reactor, Columbia, MO (United States); Kim, S S [Idaho Nuclear Engineering Laboratory, Idaho Falls, ID (United States)

    1990-05-01

    The University of Missouri-Columbia (MU) Research Reactor Facility staff is in the process of upgrading the operational and research capabilities of the reactor and associated facilities. The upgrades include an extended life aluminide fuel element, a power increase, improved instrumentation and control equipment, a cold neutron source, a building addition, and improved research instrumentation and equipment. These upgrades will greatly enhance the capabilities of the facility and the research programs. This paper discusses the parts of the upgrade and current status of implementation. (author)

  20. Status of the University of Missouri-Columbia Research Reactor upgrade

    McKibben, J.C.; Edwards, C.B. Jr.; Meyer, W.A. Jr.; Kim, S.S.

    1990-01-01

    The University of Missouri-Columbia (MU) Research Reactor Facility staff is in the process of upgrading the operational and research capabilities of the reactor and associated facilities. The upgrades include an extended life aluminide fuel element, a power increase, improved instrumentation and control equipment, a cold neutron source, a building addition, and improved research instrumentation and equipment. These upgrades will greatly enhance the capabilities of the facility and the research programs. This paper discusses the parts of the upgrade and current status of implementation. (author)

  1. Profiling the Personality Traits of University Undergraduate and Postgraduate Students at a Research University in Malaysia

    Mey, See Ching; Abdullah, Melissa Ng Lee Yen; Yin, Chuah Joe

    2014-01-01

    Research universities in Malaysia are striving to transform into world-class institutions. These universities have the capacity to attract the best students to achieve excellence in education and research. It is important to monitor the psychological well-being of students during the transformation process so that proactive intervention can help…

  2. Dry Storage of Research Reactor Spent Nuclear Fuel - 13321

    Adams, T.M.; Dunsmuir, M.D.; Leduc, D.R.; Severynse, T.F.; Sindelar, R.L. [Savannah River National Laboratory (United States); Moore, E.N. [Moore Nuclear Energy, LLC (United States)

    2013-07-01

    Spent fuel from domestic and foreign research reactors is received and stored at the Savannah River Site's L Area Material Storage (L Basin) Facility. This DOE-owned fuel consists primarily of highly enriched uranium in metal, oxide or silicide form with aluminum cladding. Upon receipt, the fuel is unloaded and transferred to basin storage awaiting final disposition. Disposition alternatives include processing via the site's H Canyon facility for uranium recovery, or packaging and shipment of the spent fuel to a waste repository. A program has been developed to provide a phased approach for dry storage of the L Basin fuel. The initial phase of the dry storage program will demonstrate loading, drying, and storage of fuel in twelve instrumented canisters to assess fuel performance. After closure, the loaded canisters are transferred to pad-mounted concrete overpacks, similar to those used for dry storage of commercial fuel. Unlike commercial spent fuel, however, the DOE fuel has high enrichment, very low to high burnup, and low decay heat. The aluminum cladding presents unique challenges due to the presence of an oxide layer that forms on the cladding surface, and corrosion degradation resulting from prolonged wet storage. The removal of free and bound water is essential to the prevention of fuel corrosion and radiolytic generation of hydrogen. The demonstration will validate models predicting pressure, temperature, gas generation, and corrosion performance, provide an engineering scale demonstration of fuel handling, drying, leak testing, and canister backfill operations, and establish 'road-ready' storage of fuel that is suitable for offsite repository shipment or retrievable for onsite processing. Implementation of the Phase I demonstration can be completed within three years. Phases II and III, leading to the de-inventory of L Basin, would require an additional 750 canisters and 6-12 years to complete. Transfer of the fuel from basin storage

  3. Conjugate heat transfer simulations of advanced research reactor fuel

    Piro, M.H.A., E-mail: pirom@aecl.ca; Leitch, B.W.

    2014-07-01

    Highlights: • Temperature predictions are enhanced by coupling heat transfer in solid and fluid zones. • Seven different cases are considered to observe trends in predicted temperature and pressure. • The seven cases consider high/medium/low power, flow, burnup, fuel material and geometry. • Simulations provide temperature predictions for performance/safety. Boiling is unlikely. • Simulations demonstrate that a candidate geometry can enhance performance/safety. - Abstract: The current work presents numerical simulations of coupled fluid flow and heat transfer of advanced U–Mo/Al and U–Mo/Mg research reactor fuels in support of performance and safety analyses. The objective of this study is to enhance predictions of the flow regime and fuel temperatures through high fidelity simulations that better capture various heat transfer pathways and with a more realistic geometric representation of the fuel assembly in comparison to previous efforts. Specifically, thermal conduction, convection and radiation mechanisms are conjugated between the solid and fluid regions. Also, a complete fuel element assembly is represented in three dimensional space, permitting fluid flow and heat transfer to be simulated across the entire domain. Seven case studies are examined that vary the coolant inlet conditions, specific power, and burnup to investigate the predicted changes in the pressure drop in the coolant and the fuel, clad and coolant temperatures. In addition, an alternate fuel geometry is considered with helical fins (replacing straight fins in the existing design) to investigate the relative changes in predicted fluid and solid temperatures. Numerical simulations predict that the clad temperature is sensitive to changes in the thermal boundary layer in the coolant, particularly in simultaneously developing flow regions, while the temperature in the fuel is anticipated to be unaffected. Finally, heat transfer between fluid and solid regions is enhanced with

  4. Research on the Scientific and Technological Innovation of Research University and Its Strategic Measures

    Cheng, Yongbo; Ge, Shaowei

    2005-01-01

    This paper illustrates the important role that the scientific and technological innovation plays in the research university. Technological innovation is one of the main functions that the research university serves and contributes for the development of economy and society, which is the essential measure for Research University to promote…

  5. Fuel Management at the Dalat Nuclear Research Reactor

    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

  6. Fossil fuel power generation within the European Research Area

    NONE

    2003-12-10

    The report is the first in a series of three produced by the PowerClean Thematic Network that looks at and defines future requirements for research and development of fossil fuel power generation in the European Union. It makes the case for fossil fuel R & D with emphasis on the need for clean coal technologies (to increased efficiency and other CO{sub 2} capture and storage) For satisfying future energy demands of the enlarged European Union between now and 2030. The report concludes that affirmative R, D and D action is needed to support the EU power industry, working together on a Europe-wide basis, to establish the use of coal and other fossil fuels in near-zero emissions power plant. The role model would be the European Research Area, as in the Sixth Framework Programme (FP6), but with a more comprehensive range of technical objectives recognising the importance of fossil fuels. Section headings are: introduction; current energy use; future needs and requirements; the future for clean fossil fuel energy in Europe; comparison with approaches adopted elsewhere (USA Vision 21 and FutureGen programmes, Japan); and responsibilities for EU coal R, D & D. 14 refs., 9 figs., 4 tabs.

  7. Commercial Aspect of Research Reactor Fuel Element Production

    Susanto, B.G; Suripto, A

    1998-01-01

    Several aspects affecting the commercialization of the Research Reactor Fuel Element Production Installation (RR FEPI) under a BUMN (state-owned company)have been studied. The break event point (BEP) value based on total production cost used is greatly depending upon the unit selling price of the fuel element. At a selling price of USD 43,500/fuel element, the results of analysis shows that the BEP will be reached at 51% of minimum available capacity. At a selling price of US$ 43.500/fuel element the total income (after tax) for 7 years ahead is US $ 4.620.191,- The net present value in this study has a positive value is equal to US $ 2.827.527,- the internal rate of return will be 18% which is higher than normal the bank interest rare (in US dollar) at this time. It is concluded therefore that the nuclear research reactor fuel element produced by state-owned company BUMN has a good prospect to be sold commercially

  8. Executable Architecture Research at Old Dominion University

    Tolk, Andreas; Shuman, Edwin A.; Garcia, Johnny J.

    2011-01-01

    Executable Architectures allow the evaluation of system architectures not only regarding their static, but also their dynamic behavior. However, the systems engineering community do not agree on a common formal specification of executable architectures. To close this gap and identify necessary elements of an executable architecture, a modeling language, and a modeling formalism is topic of ongoing PhD research. In addition, systems are generally defined and applied in an operational context to provide capabilities and enable missions. To maximize the benefits of executable architectures, a second PhD effort introduces the idea of creating an executable context in addition to the executable architecture. The results move the validation of architectures from the current information domain into the knowledge domain and improve the reliability of such validation efforts. The paper presents research and results of both doctoral research efforts and puts them into a common context of state-of-the-art of systems engineering methods supporting more agility.

  9. History of Research Reactor Fuel Fabrication at Babcock and Wilcox

    Freim, J.B.

    1983-01-01

    1982 was a year of tremendous growth for Babcock and Wilcox and its Research Reactor Fuel Facility. The Division has progressed from essentially being a non-competitor to a position where we are growing in strength. This paper describes some of the general aspects of past history and where B and W is now

  10. Research development at a South African university of technology: A ...

    This article portrays the research development strategies followed by a University of Technology in an attempt to increase and sustain a research culture. It discusses the approach of research development through building structural and intellectual capacity amongst the existing population of researchers which includes, ...

  11. The Relationship between Basic and Applied Research in Universities

    Bentley, Peter James; Gulbrandsen, Magnus; Kyvik, Svein

    2015-01-01

    What is the central research activity in modern universities? This paper uses a comprehensive survey among individuals from 15 countries to map differences in orientation towards basic/fundamental research, applied/practical research and a combination of the two. Despite some claims in the literature that basic research is no longer a…

  12. The Challenges of Developing Research Resources for Leading Vietnamese Universities

    Nguyen, Thi Lan Huong

    2013-01-01

    This paper examines the challenges of developing research resources for leading Vietnamese universities. The first part of the paper presents the background to the study, including literature review on the challenges to research resources development, and describes the research questions and research methods. The next part provides empirical…

  13. Engineering Education in Research-Intensive Universities

    Alpay, E.; Jones, M. E.

    2012-01-01

    The strengths and weaknesses of engineering education in research-intensive institutions are reported and key areas for developmental focus identified. The work is based on a questionnaire and session summaries used during a two-day international conference held at Imperial College London. The findings highlight several common concerns, such as…

  14. Gender Issues in the University Research Environment

    Alpay, E.; Hari, A.; Kambouri, M.; Ahearn, A. L.

    2010-01-01

    Recruiting and retaining females within science, engineering and technology continues to challenge many European higher education institutions. This study looks at female self-perceptions relating to effective research work and career progression. Focus groups are used to examine the attitudes and experiences of females and a questionnaire is used…

  15. South African universities, research and positive psychology ...

    The purpose of this article is to highlight pioneering and fundamental contributions by South African researchers to establishing a new paradigm in psychology, namely positive psychology. The article provides an overview of the national and international historic development of this field. Current and completed South ...

  16. Water Resources Research Institute | Mississippi State University

    Welcome The Mississippi Water Resources Research Institute provides a statewide center of expertise in water and associated land-use and serves as a repository of knowledge for use in education private interests in the conservation, development, and use of water resources; to provide training

  17. Research collaboration 2011: a joint publication highlighting the research partnerships between Tshwane University of Technology, University of Johannesburg, University of the Witwatersrand and the CSIR

    CSIR

    2011-01-01

    Full Text Available to be productive during 2011. The three Universities collaborated with the CSIR through research projects, teaching and supervision of the student research, exchange of staff and the use of facilities. Collaborative projects and supervised student research have...

  18. Managing the accountability-autonomy tensions in university research commercialisation

    Narayan, Anil K.; Northcott, Deryl; Parker, Lee D.

    2017-01-01

    This article investigates organisational responses to emerging concerns about how accountability–autonomy tensions can be managed within the context of university research commercialisation. The findings suggest that changed expectations of university research practices, which result from the introduction of a commercialisation logic, can be managed via the homogenisation of research goals and strategies. The successful management of accountability–autonomy tensions also depends on utilising ...

  19. Research Collaborations Between Universities and Department of Defense Laboratories

    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

  20. UNIVERSITY TURBINE SYSTEMS RESEARCH PROGRAM SUMMARY AND DIRECTORY

    Lawrence P. Golan; Richard A. Wenglarz

    2004-07-01

    The South Carolina Institute for Energy Studies (SCIES), administratively housed at Clemson University, has participated in the advancement of combustion turbine technology for over a decade. The University Turbine Systems Research Program, previously referred to as the Advanced Gas Turbine Systems Research (AGTSR) program, has been administered by SCIES for the U.S. DOE during the 1992-2003 timeframe. The structure of the program is based on a concept presented to the DOE by Clemson University. Under the supervision of the DOE National Energy Technology Laboratory (NETL), the UTSR consortium brings together the engineering departments at leading U.S. universities and U.S. combustion turbine developers to provide a solid base of knowledge for the future generations of land-based gas turbines. In the UTSR program, an Industrial Review Board (IRB) (Appendix C) of gas turbine companies and related organizations defines needed gas turbine research. SCIES prepares yearly requests for university proposals to address the research needs identified by the IRB organizations. IRB technical representatives evaluate the university proposals and review progress reports from the awarded university projects. To accelerate technology transfer technical workshops are held to provide opportunities for university, industry and government officials to share comments and improve quality and relevancy of the research. To provide educational growth at the Universities, in addition to sponsored research, the UTSR provides faculty and student fellowships. The basis for all activities--research, technology transfer, and education--is the DOE Turbine Program Plan and identification, through UTSR consortium group processes, technology needed to meet Program Goals that can be appropriately researched at Performing Member Universities.

  1. Research efforts on fuels, fuel models, and fire behavior in eastern hardwood forests

    Thomas A. Waldrop; Lucy Brudnak; Ross J. Phillips; Patrick H. Brose

    2006-01-01

    Although fire was historically important to most eastern hardwood systems, its reintroduction by prescribed burning programs has been slow. As a result, less information is available on these systems to fire managers. Recent research and nationwide programs are beginning to produce usable products to predict fuel accumulation and fire behavior. We introduce some of...

  2. Basic research on high-uranium density fuels for research and test reactors

    Ugajin, M.; Itoh, A.; Akabori, M.

    1992-01-01

    High-uranium density fuels, uranium silicides (U 3 Si 2 , U 3 Si) and U 6 Me-type uranium alloys (Me = Fe, Mn, Ni), were prepared and examined metallurgically as low-enriched uranium (LEU) fuels for research and test reactors. Miniature aluminum-dispersion plate-type fuel (miniplate) and aluminum-clad disk-type fuel specimens were fabricated and subjected to the neutron irradiation in JMTR (Japan Materials Testing Reactor). Fuel-aluminum compatibility tests were conducted to elucidate the extent of reaction and to identify reaction products. The relative stability of the fuels in an aluminum matrix was established at 350degC or above. Experiments were also performed to predict the chemical form of the solid fission-products in the uranium silicide (U 3 Si 2 ) simulating a high burnup anticipated for reactor service. (author)

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

    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

  4. Research on Elemental Technology of Advanced Nuclear Fuel Performance Verification

    Kim, Yong Soo; Lee, Dong Uk; Jean, Sang Hwan; Koo, Min

    2003-04-01

    Most of current properties models and fuel performance models used in the performance evaluation codes are based on the in-pile data up to 33,000 MWd/MtU. Therefore, international experts are investigating the properties changes and developing advanced prediction models for high burn-up application. Current research is to develop high burn-up fission gas release model for the code and to support the code development activities by collecting data and models, reviewing/assessing the data and models together, and benchmarking the selected models against the appropriate in-pile data. For high burn-up applications, two stage two step fission gas release model is developed based on the real two diffusion process in the grain lattice and grain boundaries of the fission gases and the observation of accelerated release rate in the high burn-up. It is found that the prediction of this model is in excellent agreement with the in-pile measurement results, not only in the low burn-up but also in the high burn-up. This research is found that the importance of thermal conductivity of oxide fuel, especially in the high burn-up, is focused again. It is found that even the temperature dependent models differ from one to another and most of them overestimate the conductivity in the high burn-up. An in-pile data benchmarking of high LHGR fuel rod shows that the difference can reach 30%∼40%, which predicts 400 .deg. C lower than the real fuel centerline temperature. Recent models on the thermal expansion and heat capacity of oxide fuel are found to be well-defined. Irradiation swelling of the oxide fuel are now well-understood that in most cases in LWRs solid fission product swelling is dominant. Thus, the accumulation of in-pile data can enhance the accuracy of the model prediction, rather than theoretical modeling works. Thermo-physical properties of Zircaloy cladding are also well-defined and well-understood except the thermal expansion. However, it turns out that even the

  5. Fuel shuffling optimization for the Delft research reactor

    Geemert, R. van; Hoogenboom, J.E.; Gibcus, H.P.M. [Delft Univ. of Technology, Interfaculty Reactor Inst., Delft (Netherlands); Quist, A.J. [Delft Univ., Fac. of Applied Mathematics and Informatics, Delft (Netherlands)

    1997-07-01

    A fuel shuffling optimization procedure is proposed for the Hoger Onderwijs Reactor (HOR) in Delft, the Netherlands, a 2 MWth swimming-pool type research reactor. In order to cope with the fluctuatory behaviour of objective functions in loading pattern optimization, the proposed cyclic permutation optimization procedure features a gradual transition from global to local search behaviour via the introduction of stochastic tests for the number of fuel assemblies involved in a cyclic permutation. The possible objectives and the safety and operation constraints, as well as the optimization procedure, are discussed, followed by some optimization results for the HOR. (author) 5 figs., 4 refs.

  6. Fuel shuffling optimization for the Delft research reactor

    Geemert, R. van; Hoogenboom, J.E.; Gibcus, H.P.M.; Quist, A.J.

    1997-01-01

    A fuel shuffling optimization procedure is proposed for the Hoger Onderwijs Reactor (HOR) in Delft, the Netherlands, a 2 MWth swimming-pool type research reactor. In order to cope with the fluctuatory behaviour of objective functions in loading pattern optimization, the proposed cyclic permutation optimization procedure features a gradual transition from global to local search behaviour via the introduction of stochastic tests for the number of fuel assemblies involved in a cyclic permutation. The possible objectives and the safety and operation constraints, as well as the optimization procedure, are discussed, followed by some optimization results for the HOR. (author)

  7. Fuel shuffling optimization for the Delft research reactor

    Geemert, R. van; Hoogenboom, J.E.; Gibcus, H.P.M. [Delft Univ. of Technology, Interfaculty Reactor Inst., Delft (Netherlands); Quist, A.J. [Delft Univ., Fac. of Applied Mathematics and Informatics, Delft (Netherlands)

    1997-07-01

    A fuel shuffling optimization procedure is proposed for the Hoger Onderwijs Reactor (HOR) in Delft, the Netherlands, a 2 MWth swimming-pool type research reactor. In order to cope with the fluctuatory behaviour of objective functions in loading pattern optimization, the proposed cyclic permutation optimization procedure features a gradual transition from global to local search behaviour via the introduction of stochastic tests for the number of fuel assemblies involved in a cyclic permutation. The possible objectives and the safety and operation constraints, as well as the optimization procedure, are discussed, followed by some optimization results for the HOR. (author)

  8. Design and research of fuel element for pulsed reactor

    Tian Sheng

    1994-05-01

    The fuel element is the key component for pulsed reactor and its design is one of kernel techniques for pulsed reactor. Following the GA Company of US the NPIC (Nuclear Power Institute of China) has mastered this technique. Up to now, the first pulsed reactor in China (PRC-1) has been safely operated for about 3 years. The design and research of fuel element undertaken by NPIC is summarized. The verification and evaluation of this design has been carried out by using the results of measured parameters during operation and test of PRC-1 as well as comparing the design parameters published by others

  9. Some tooling for manufacturing research reactor fuel plates

    Knight, R.W.

    1999-01-01

    This paper will discuss some of the tooling necessary to manufacture aluminum-based research reactor fuel plates. Most of this tooling is intended for use in a high-production facility. Some of the tools shown have manufactured more than 150,000 pieces. The only maintenance has been sharpening. With careful design, tools can be made to accommodate the manufacture of several different fuel elements, thus, reducing tooling costs and maintaining tools that the operators are trained to use. An important feature is to design the tools using materials with good lasting quality. Good tools can increase return on investment. (author)

  10. Some Tooling for Manufacturing Research Reactor Fuel Plates

    Knight, R.W.

    1999-01-01

    This paper will discuss some of the tooling necessary to manufacture aluminum-based research reactor fuel plates. Most of this tooling is intended for use in a high-production facility. Some of the tools shown have manufactured more than 150,000 pieces. The only maintenance has been sharpening. With careful design, tools can be made to accommodate the manufacture of several different fuel elements, thus, reducing tooling costs and maintaining tools that the operators are trained to use. An important feature is to design the tools using materials with good lasting quality. Good tools can increase return on investment

  11. Final Technical Report for the MIT Annular Fuel Research Project

    Mujid S. Kazimi; Pavel Hejzlar

    2008-01-01

    MIT-NFC-PR-082 (January 2006) Abstract This summary provides an overview of the results of the U.S. DOE funded NERI (Nuclear Research Energy Initiative) program on development of the internally and externally cooled annular fuel for high power density PWRs. This new fuel was proposed by MIT to allow a substantial increase in power density (on the order of 30% or higher) while maintaining or improving safety margins. A comprehensive study was performed by a team consisting of MIT (lead organization), Westinghouse Electric Corporation, Gamma Engineering Corporation, Framatome ANP(formerly Duke Engineering) and Atomic Energy of Canada Limited

  12. University Crystalline Silicon Photovoltaics Research and Development

    Ajeet Rohatgi; Vijay Yelundur; Abasifreke Ebong; Dong Seop Kim

    2008-08-18

    The overall goal of the program is to advance the current state of crystalline silicon solar cell technology to make photovoltaics more competitive with conventional energy sources. This program emphasizes fundamental and applied research that results in low-cost, high-efficiency cells on commercial silicon substrates with strong involvement of the PV industry, and support a very strong photovoltaics education program in the US based on classroom education and hands-on training in the laboratory.

  13. A Referential-Structural Research on Universals

    Pareyon, Gabriel

    2004-01-01

    This research and practice project studies the way in which some aspects of linguistic order are also found in music’s order. Whereas some aspects of order and organisation are attributed to music because of their psychophysical integration, other aspects seem to be more related to the configuration of music in memory and experience (i.e. individual memory and memory-in-society processes). This fundamental condition is shared with speech and visual symbolizing. Since order in music is commonl...

  14. PROBLEMS AND PROSPECTS OF UNIVERSITY DEVELOPMENT: THE SOCIOLOGICAL RESEARCH EXPERIENCE

    Y. M. Dorozhkin

    2015-03-01

    Full Text Available The paper reveals the sociological research findings reflecting the development problems and prospects of theRussianStateVocationalPedagogicalUniversity. A survey, conducted in March 2013, demonstrates positive dynamics of the university prestige, rank and popularity index compared to the year 2003. The academic staff tends to recognize the unique competitive advantages of the given university: status of the Russian higher school and leading vocational pedagogical institution; professional quality of human resources, variety of prestigious specializations, existence of the Educational Methodology Association, Dissertation Board, etc. Although the respondents point out some factors adversely affecting the university image and public opinion, the criticism helps to identify the problematic units and corresponding contradictions of the university development. The research outcomes can provide the background for strategic development programs ofRussianStateVocationalPedagogicalUniversityfor the nearest future; and help to promote the university brand as the leading, dynamic and competitive educational centre at the regional, federal and international levels.

  15. PROBLEMS AND PROSPECTS OF UNIVERSITY DEVELOPMENT: THE SOCIOLOGICAL RESEARCH EXPERIENCE

    Y. M. Dorozhkin

    2014-01-01

    Full Text Available The paper reveals the sociological research findings reflecting the development problems and prospects of theRussianStateVocationalPedagogicalUniversity. A survey, conducted in March 2013, demonstrates positive dynamics of the university prestige, rank and popularity index compared to the year 2003. The academic staff tends to recognize the unique competitive advantages of the given university: status of the Russian higher school and leading vocational pedagogical institution; professional quality of human resources, variety of prestigious specializations, existence of the Educational Methodology Association, Dissertation Board, etc. Although the respondents point out some factors adversely affecting the university image and public opinion, the criticism helps to identify the problematic units and corresponding contradictions of the university development. The research outcomes can provide the background for strategic development programs ofRussianStateVocationalPedagogicalUniversityfor the nearest future; and help to promote the university brand as the leading, dynamic and competitive educational centre at the regional, federal and international levels.

  16. Encouraging entrepreneurship in university labs: Research activities, research outputs, and early doctorate careers

    Roach, Michael

    2017-01-01

    This paper investigates how the encouragement of entrepreneurship within university research labs relates with research activities, research outputs, and early doctorate careers. Utilizing a panel survey of 6,840 science & engineering doctoral students at 39 R1 research universities, this study shows that entrepreneurship is widely encouraged across university research labs, ranging from 54% in biomedical engineering to 18% in particle physics, while only a small share of labs openly discoura...

  17. [Heavy ion physics research at Creighton University

    Cherney, M.

    1992-01-01

    This research continues the baseline efforts i n the investigation of the behavior of hadronic matter under extreme conditions. The project is concerned with the search for indications of a phase transition from hadronic to quark matter in the STAR, NA44 and NA36 experiments. It is believed that the conditions. This project contributes to the development of a slow control system and time projection chamber tracking for the STAR experiment, upgrades for the NA44 experiment at CERN through studies of a spot focusing Cherenkov-detector, and the remaining analysis of data collected with the NA36 experiment at CERN.

  18. [Heavy ion physics research at Creighton University

    Cherney, M.

    1992-01-01

    This research continues the baseline efforts i n the investigation of the behavior of hadronic matter under extreme conditions. The project is concerned with the search for indications of a phase transition from hadronic to quark matter in the STAR, NA44 and NA36 experiments. It is believed that the conditions. This project contributes to the development of a slow control system and time projection chamber tracking for the STAR experiment, upgrades for the NA44 experiment at CERN through studies of a spot focusing Cherenkov-detector, and the remaining analysis of data collected with the NA36 experiment at CERN

  19. Atomization of U3Si2 for research reactor fuel

    Kim, C.K.; Kim, K.H.; Lee, C.T.; Kuk, I.H.

    1995-01-01

    Rotating disk atomization technique is applied to KMRR (Korea Multi-purpose Research Reactor) fuel fabrication. A rotating disk atomizer is designed and manufactured locally and U-4.0 wt. % Si alloy powders are produced. The atomized powders are heat-treated to transform into U 3 Si and the mixture of U 3 Si and Al are extruded to fuel meat. Most of the atomized powders are spherical in shape. The microstructure of the powder is fine due to the rapid solidification. The time required for peritectoid reaction is reduced due to the fine microstructures and the resultant U 3 Si grain size is finer than ever obtained from ingot process. The mechanical properties of the fuel meat are improved: yield strength about 30 %, tensile strength 10% and elongation 250 % increased. (author)

  20. Neutronic calculations for the conversion of the University of Florida Training Reactor from HEU to LEU fuel

    Dugan, E T; Diaz, N J [Department of Nuclear Engineering Sciences, University of Florida, Gainesville, FL (United States); Kniedler, G S [Reactor Analysis Group, TVA, Chattanooga, TN (United States)

    1983-09-01

    The University of Florida Training Reactor (UFTR) is located on the University of Florida campus in Gainesville, Florida. The reactor is the Argonaut type, heterogeneous in design and currently fueled with 93% enriched, uranium-aluminum alloy MTR plate-type fuel. Investigations are being performed to examine te feasibility of replacing the highly-enriched fuel of the current UFTR with 4.8% enriched, cylindrical pin SPERT fuel. The SPERT fuel is stainless steel clad and contains uranium dioxide (UO{sub 2}) pellets. On a broad spectrum, training reactor conversion from high enrichment uranium (HEU) to low enrichment uranium (LEU) fueled facilities has been a continuing concern in the International Atomic Energy Agency (IAEA) and significant work has been done in this area by the Argonne RERTR Program. The International Atomic Energy Agency cites three reasons for reactor conversion to low-enriched uranium. The main reason is the desire to reduce the proliferation potential of research reactor fuels. The second is to increase the assurance of continued fuel availability in the face of probable restrictions on the supply of highly-enriched uranium. The third reason is the possible reduction in requirements for physical security measures during fabrication, transportation, storage and use. This same IAEA report points out that the three reasons stated for the conversion of the fuel of research reactors are interrelated and cannot be considered individually. The concerns of the Nuclear Engineering Sciences Department at the University of Florida relating to the HEU fuel of the UFTR coincide with those of the International Atomic Energy Agency. The primary reason for going to low-enriched pin-type fuel is the concern with proliferation provoked by the highly-enriched plate fuel which has led to tighter security of nuclear facilities such as the UFTR. A second reason for changing to the pin-type fuel is because of difficulties that are being encountered in the supply of

  1. Neutronic calculations for the conversion of the University of Florida Training Reactor from HEU to LEU fuel

    Dugan, E.T.; Diaz, N.J.; Kniedler, G.S.

    1983-01-01

    The University of Florida Training Reactor (UFTR) is located on the University of Florida campus in Gainesville, Florida. The reactor is the Argonaut type, heterogeneous in design and currently fueled with 93% enriched, uranium-aluminum alloy MTR plate-type fuel. Investigations are being performed to examine te feasibility of replacing the highly-enriched fuel of the current UFTR with 4.8% enriched, cylindrical pin SPERT fuel. The SPERT fuel is stainless steel clad and contains uranium dioxide (UO 2 ) pellets. On a broad spectrum, training reactor conversion from high enrichment uranium (HEU) to low enrichment uranium (LEU) fueled facilities has been a continuing concern in the International Atomic Energy Agency (IAEA) and significant work has been done in this area by the Argonne RERTR Program. The International Atomic Energy Agency cites three reasons for reactor conversion to low-enriched uranium. The main reason is the desire to reduce the proliferation potential of research reactor fuels. The second is to increase the assurance of continued fuel availability in the face of probable restrictions on the supply of highly-enriched uranium. The third reason is the possible reduction in requirements for physical security measures during fabrication, transportation, storage and use. This same IAEA report points out that the three reasons stated for the conversion of the fuel of research reactors are interrelated and cannot be considered individually. The concerns of the Nuclear Engineering Sciences Department at the University of Florida relating to the HEU fuel of the UFTR coincide with those of the International Atomic Energy Agency. The primary reason for going to low-enriched pin-type fuel is the concern with proliferation provoked by the highly-enriched plate fuel which has led to tighter security of nuclear facilities such as the UFTR. A second reason for changing to the pin-type fuel is because of difficulties that are being encountered in the supply of the

  2. Preliminary cost analysis of a universal package concept in the spent fuel management system

    1984-09-01

    The purpose of this study is to provide a preliminary cost assessment of a universal spent fuel package concept as it applies to the backend of the once through nuclear fuel cycle; i.e., a package that would be qualified for spent fuel storage, transportation, and disposal. To provide this preliminary cost assessment, costs for each element of the spent fuel management system have been compiled for system scenarios employing the universal package, and these costs are compared against system costs for scenarios employing the universal package, and these costs are compared against system costs for scenarios employing other types of storage, transportation, and disposal packages. The system elements considered in this study are storage at the nuclear power plant, spent fuel transportation, a Monitored Retrievable Storage (MRS) facility, and a geologic repository. In accordance with the Nuclear Waste Policy Act, most of these system elements and associated functions will be the responsibility of the Department of Energy. 10 refs., 25 figs., 22 tabs

  3. Convective parameters in fuel elements for research nuclear reactors

    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)

  4. Medical universities educational and research online services: benchmarking universities' website towards e-government.

    Farzandipour, Mehrdad; Meidani, Zahra

    2014-06-01

    Websites as one of the initial steps towards an e-government adoption do facilitate delivery of online and customer-oriented services. In this study we intended to investigate the role of the websites of medical universities in providing educational and research services following the E-government maturity model in the Iranian universities. This descriptive and cross- sectional study was conducted through content analysis and benchmarking the websites in 2012. The research population included the entire medical university website (37). Delivery of educational and research services through these university websites including information, interaction, transaction, and Integration were investigated using a checklist. The data were then analyzed by means of descriptive statistics and using SPSS software. Level of educational and research services by websites of the medical universities type I and II was evaluated medium as 1.99 and 1.89, respectively. All the universities gained a mean score of 1 out of 3 in terms of integration of educational and research services. Results of the study indicated that Iranian universities have passed information and interaction stages, but they have not made much progress in transaction and integration stages. Failure to adapt to e-government in Iranian medical universities in which limiting factors such as users' e-literacy, access to the internet and ICT infrastructure are not so crucial as in other organizations, suggest that e-government realization goes beyond technical challenges.

  5. Gender issues in the university research environment

    Alpay, E.; Hari, A.; Kambouri, M.; Ahearn, A. L.

    2010-05-01

    Recruiting and retaining females within science, engineering and technology continues to challenge many European higher education institutions. This study looks at female self-perceptions relating to effective research work and career progression. Focus groups are used to examine the attitudes and experiences of females and a questionnaire is used to explore perceptions in four main skills areas: group work; communication; personal awareness; project planning and management. The study indicates consistent female concerns on issues pertaining to effective female role models, negative work-role stereotypes and the work-life balance of an academic career. For all four skills areas, the average confidence scores of the female participants fell below those of males, but these differences were only statistically significant for perceptions on group work and communication skills and prior to an intense skills development course. Based on these findings, a student workshop on gender issues has been developed, an outline of which is presented.

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

    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

  7. Spent Fuel Performance Assessment and Research. Final Report of a Coordinated Research Project on Spent Fuel Performance Assessment and Research (SPAR-III) 2009–2014

    2015-10-01

    At the beginning of 2014, there were 437 nuclear power reactors in operation and 72 reactors under construction. To date, around 370 500 t (HM) (tonnes of heavy metal) of spent fuel have been discharged from reactors, and approximately 253 700 t (HM) are stored at various storage facilities. Although wet storage at reactor sites still dominates, the amount of spent fuel being transferred to dry storage technologies has increased significantly since 2005. For example, around 28% of the total fuel inventory in the United States of America is now in dry storage. Although the licensing for the construction of geological disposal facilities is under way in Finland, France and Sweden, the first facility is not expected to be available until 2025 and for most States with major nuclear programmes not for several decades afterwards. Spent fuel is currently accumulating at around 7000 t (HM) per year worldwide. The net result is that the duration of spent fuel storage has increased beyond what was originally foreseen. In order to demonstrate the safety of both spent fuel and the storage system, a good understanding of the processes that might cause deterioration is required. To address this, the IAEA continued the Coordinated Research Project (CRP) on Spent Fuel Performance Assessment and Research (SPAR-III) in 2009 to evaluate fuel and materials performance under wet and dry storage and to assess the impact of interim storage on associated spent fuel management activities (such as handling and transport). This has been achieved through: evaluating surveillance and monitoring programmes of spent fuel and storage facilities; collecting and exchanging relevant experience of spent fuel storage and the impact on associated spent fuel management activities; facilitating the transfer of knowledge by documenting the technical basis for spent fuel storage; creating synergy among research projects of the participating Member States; and developing the capability to assess the impact

  8. Promoting Employability Skills Development in a Research-Intensive University

    Baker, Geoff; Henson, Debra

    2010-01-01

    Purpose: This study aims to consider the place of employability in universities, with a focus on research-intensive institutions, and to outline an initiative that was introduced to promote employability skills development at the University of Nottingham. Design/methodology/approach: Following a discussion of literature on the promotion of…

  9. Connecting Physical University Spaces with Research-Based Education Strategy

    Carnell, Brent

    2017-01-01

    This paper looks at the link between enhancing education and ensuring an innovative fit-for-purpose estate. It argues that a nuanced approach and joined-up dialogue is needed between university staff whose remit covers these areas. Drawing from fifteen semi-structured interviews with students and staff at a research-intensive university in London,…

  10. Strategies for university improvement: The research profile change ...

    Universities worldwide experience continual change in order to achieve what is perceived as improvement. In these changes, there is usually an emphasis on the research function of a university, and the literature contains a number of themes in this regard. We contribute by presenting a detailed case study of a ...

  11. Starting the Conversation: University-Wide Research Data Management Policy

    Erway, Ricky

    2013-01-01

    This call for action addresses the high-level benefits of adopting a university-wide policy regarding research data management. It identifies the various university stakeholders and suggests that the library initiate a conversation among them in order to get buy-in for a proactive, rather than reactive, high-level policy for responsible data…

  12. Commercialization of University Research for Technology-Based Economic Development

    Ferguson, W. Ker

    2011-01-01

    This empirical study investigates the hypothesized relationship between US federally funded university research and development (R&D) and its resulting economic impact, as measured by the level of licensing revenue generated by US universities. The author also examines the key operating statistics of the top-ten licensing income-producing…

  13. Proposed nuclear weapons nonproliferation policy concerning foreign research reactor spent nuclear fuel: Appendix B, foreign research reactor spent nuclear fuel characteristics and transportation casks. Volume 2

    1995-03-01

    This is Appendix B of a draft Environmental Impact Statement (EIS) on a Proposed Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel. It discusses relevant characterization and other information of foreign research reactor spent nuclear fuel that could be managed under the proposed action. It also discusses regulations for the transport of radioactive materials and the design of spent fuel casks

  14. Fuel cycle industrialization program prepared by N-Fuel Research Committee, ANRE

    1978-09-01

    To meet the new situation resulting from the scaling down of nuclear power development plan in Japan, and the changes due to the new U.S. nuclear non-proliferation policy, the Nuclear Fuel Research Committee of the Agency of Natural Resources and Energy of MITI has prepared the ''Interim Report on the Nuclear Fuel Cycle''. It sets out in precise terms the methods that should be followed for establishing the nuclear fuel cycle in Japan. Major items treated in this report are; uranium ore development, promotion of uranium stockpiling, construction of domestic uranium enrichment plant, promotion of the construction of a nuclear fuel park, Pu utilization and cooperation in international movement for nuclear non-proliferation, and the establishment of measures for radioactive waste management. Discussions are made from technological, economical, and political view points. Also attached are a table of the comprehensive industrialization plan up to the year 2000 and a table of estimated nuclear fuel demand and supply in Japan.

  15. Social science to improve fuels management: a synthesis of research on assessing social acceptability of fuels treatments

    Terry C. Daniel; Michael Valdiserri; Carrie R. Daniel; Pamela Jakes; Pamela Jakes; Susan Barro

    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 for assessing the social acceptability of fuels treatments. The synthesis is structured around six important considerations for any social acceptability assessment: defining the fuels treatments being assessed; representing...

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

    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.

  17. Teacher to Researcher: Reflections on a New Action Research Program for University EFL Teachers

    Burns, Anne; Westmacott, Anne

    2018-01-01

    One of the current challenges facing many universities is how to support teachers in becoming researchers. This article discusses the experiences at a small private Chilean university of a new action research programme that was developed as a vehicle for helping teachers to become involved in research and write a research publication for…

  18. Impact of Antecedent Factors on Collaborative Technologies Usage among Academic Researchers in Malaysian Research Universities

    Mohd Daud, Norzaidi; Zakaria, Halimi

    2017-01-01

    Purpose: The purpose of this paper is to investigate the impact of antecedent factors on collaborative technologies usage among academic researchers in Malaysian research universities. Design/methodology/approach: Data analysis was conducted on data collected from 156 academic researchers from five Malaysian research universities. This study…

  19. University-Private Sector Research Partnerships in the Innovation Ecosystem

    2008-11-01

    private sector . There are several trends that PCAST considers to fall specifically within context of university- private sector research partnerships. The first is the growing imbalance between the academic research capacity and the Federal research budget. The second development is the reduction in basic research performed by the industrial sector. Private foundations are expanding their capacity to fund research, a trend expected to be important in the future. Lastly, the accelerating speed of technological development requires new methods of

  20. (ARWU) and the 'big five' South African research universities

    Shanghai Academic Ranking of World Universities (ARWU) and the 'big five' South African research ... South African Journal of Higher Education ... Some ARWU indicator scores violate the original proportionality in the source data. The notion ...

  1. Access to Knowledge Southern Africa : Universities, Open Research ...

    Journal articles. Research productivity-visibility-accessibility and scholarly communication in Southern African universities. Download PDF ... Call for new OWSD Fellowships for Early Career Women Scientists now open. In partnership with ...

  2. Minister Pratt welcomes new Canada Research Chair at Carleton University

    2004-01-01

    "The Honourable David Pratt, Minister of National Defence, and Member of Parliament for Nepean-Carleton, today congratulated Carleton University on receiving $638,405 in funding to support a new Canada Research Chair" (1 page)

  3. Challenges of doing research in sub-Saharan African universities ...

    The internationalisation of higher education, coupled with growing student ... efforts to rank universities in terms of their academic quality and productivity at national, ... scholarship, e-research, e-learning, sub-Saharan Africa, higher education ...

  4. A bibliometric analysis of leading universities in innovation research

    Christian A. Cancino

    2017-09-01

    Full Text Available The number of innovation studies with a management perspective has grown considerably over the last 25 years. This study identified the universities that are most productive and influential in innovation research. The leading innovation research journals were also studied individually to identify the most productive universities for each journal. Data from the Web of Science were analyzed. Studies that were published between 1989 and 2013 were filtered first by the keyword “innovation” and second by 18 management-related research areas. The results indicate that US universities are the most productive and influential because they account for the most publications with a high number of citations and high h-index. Following advances in the productivity of numerous European journals, however, universities from the UK and the Netherlands are the most involved in publishing in journals that specialize in innovation research.

  5. Theoretical high energy physics research at the University of Chicago

    Rosner, J.L.; Martinec, E.J.; Sachs, R.G.

    1990-09-01

    This report discusses research being done at the University of Chicago in High Energy Physics. Some topic covered are: CP violation; intermediate vector bosons; string models; supersymmetry; and rare decay of kaons

  6. Research and development into power reactor fuel performance

    Notley, M.J.F.

    1983-07-01

    The nuclear fuel in a power reactor must perform reliably during normal operation, and the consequences of abnormal events must be researched and assessed. The present highly reliable operation of the natural UO 2 in the CANDU power reactors has reduced the need for further work in this area; however a core of expertise must be retained for purposes such as training of new staff, retaining the capability of reacting to unforeseen circumstances, and participating in the commercial development of new ideas. The assessment of fuel performance during accidents requires research into many aspects of materials, fuel and fission product behaviour, and the consolidation of that knowledge into computer codes used to evaluate the consequences of any particular accident. This work is growing in scope, much is known from out-reactor work at temperatures up to about 1500 degreesC, but the need for in-reactor verification and investigation of higher-temperature accidents has necessitated the construction of a major new in-reactor test loop and the initiation of the associated out-reactor support programs. Since many of the programs on normal and accident-related performance are generic in nature, they will be applicable to advanced fuel cycles. Work will therefore be gradually transferred from the present, committed power reactor system to support the next generation of thorium-based reactor cycles

  7. Research collaboration 2011-2012: A joint publication highlighting the research partnerships between the CSIR and University of the Western Cape, University of Cape Town, Stellenbosch University

    CSIR

    2012-01-01

    Full Text Available CSIR’s partnerships with the University of the Western Cape (UWC), University of Cape Town (UCT) and Stellenbosch University (SU) seek to conduct research that improves the quality of the lives of the people of South Africa by responding...

  8. Safety assessments relating to the use of new fuels in research reactors: application to the case of FRM 2 reactor fuel

    Abou Yehia, H.; Bars, G.; Tran Dai

    2001-01-01

    After giving a brief reminder of the procedure applied in France for the licensing of the use of a new fuel type or design in a research reactor, we outline the main safety aspects associated with such a modification. Finally, by way of an example, we focus on the safety assessment relating to the IRIS irradiation device used in SILOE reactor, in particular for the qualification of the fuel dedicated to FRM II reactor of the Technical University of Munich. This qualification was carried out on a U 3 Si 2 fuel plate enriched to about 90 % in weight of 235 U and containing 1.5 g of uranium per cm 3 . The evaluation performed by the IPSN for GRS did not call into question the choice of U 3 Si 2 fuel plates for the FRM-II reactor. (authors)

  9. Hybrid rocket engine research program at Ryerson University

    Karpynczyk, J.; Greatrix, D.R. [Ryerson Polytechnic Univ., Toronto, ON (Canada). Dept. of Aerospace Engineering

    2007-07-01

    Hybrid rocket engines (HREs) are a combination of solid and liquid propellant rocket engine designs. A solid fuel grain is located in the main combustion chamber and nozzle aft, while a stored liquid or gaseous oxidizer source supplies the required oxygen content through a throttle valve, for combustion downstream in the main chamber. HREs have drawn significant interest in certain flight applications, as they can be advantageous in terms of cost, ease and safety in storage, controllability in flight, and availability of propellant constituents. Key factors that will lead to further practical usage of HREs for flight applications are their predictability and reproducibility of operational performance. This paper presented information on studies being conducted at Ryerson University aimed at analyzing and testing the performance of HREs. It discussed and illustrated the conventional HRE and analyzed engine performance considerations such as the fuel regression rate, mass flux about the fuel surface, burning rate, and zero transformation parameter. Other factors relating to HRE performance that were presented included induced forward and aft oxidizer flow swirl effects as a means for augmenting the fuel regression rate, stoichiometric grain length issues, and feed system stability. Last, the paper presented a simplified schematic diagram of a proposed thrust/test stand for HRE test firings. 2 refs., 3 figs.

  10. Fuel burnup analysis of the TRIGA Mark II reactor at the University of Pavia

    Chiesa, Davide; Clemenza, Massimiliano; Pozzi, Stefano; Previtali, Ezio; Sisti, Monica; Alloni, Daniele; Magrotti, Giovanni; Manera, Sergio; Prata, Michele; Salvini, Andrea; Cammi, Antonio; Zanetti, Matteo; Sartori, Alberto

    2016-01-01

    Highlights: • A fuel evolution model for a TRIGA Mark II reactor has been developed. • Reproduction of nearly 50 years of reactor operation. • The model was used to predict the best reactor reconfiguration. • Reactor life was extended without adding fresh fuel elements. - Abstract: A time evolution model was developed to study fuel burnup for the TRIGA Mark II reactor at the University of Pavia. The results were used to predict the effects of a complete core reconfiguration and the accuracy of this prediction was tested experimentally. We used the Monte Carlo code MCNP5 to reproduce system neutronics in different operating conditions and to analyze neutron fluxes in the reactor core. The software that took care of time evolution, completely designed in-house, used the neutron fluxes obtained by MCNP5 to evaluate fuel consumption. This software was developed specifically to keep into account some features that differentiate low power experimental reactors from those used for power production, such as the daily ON/OFF cycle and the long fuel lifetime. These effects can not be neglected to properly account for neutron poison accumulation. We evaluated the effect of 48 years of reactor operation and predicted a possible new configuration for the reactor core: the objective was to remove some of the fuel elements from the core and to obtain a substantial increase in the Core Excess reactivity value. The evaluation of fuel burnup and the reconfiguration results are presented in this paper.

  11. Outline of research program on thorium fuel supported by grant-in-aid for energy research of ministry of education, science and culture

    Shibata, Toshikazu

    1984-01-01

    Since 1980, the Research Program on Thorium Fuel has been performed under the support of Grant-in-Aid for Energy Research of the Ministry of Education, Science and Culture of Japanese Government on the university basis including several tens professors. The main results have been published in the English-written report, ''Research on Thorium Fuel (SPEY-9, 1984)''. This report describes the outline and review of the symposium held on January 31, 1984. It consists of nuclear data, reactor physics, thorium fuel, irradiation of thorium, down-stream, biological effect, molten salt reactor engineering and others. It has been the first trial to perform such a big systematic cooperative studies in nuclear field on the university basis in Japan. (author)

  12. Effect of reduced enrichment on the fuel cycle for research reactors

    Travelli, A.

    1982-01-01

    The new fuels developed by the RERTR Program and by other international programs for application in research reactors with reduced uranium enrichment (<20% EU) are discussed. It is shown that these fuels, combined with proper fuel-element design and fuel-management strategies, can provide at least the same core residence time as high-enrichment fuels in current use, and can frequently significantly extend it. The effect of enrichment reduction on other components of the research reactor fuel cycle, such as uranium and enrichment requirements, fuel fabrication, fuel shipment, and reprocessing are also briefly discussed with their economic implications. From a systematic comparison of HEU and LEU cores for the same reference research reactor, it is concluded that the new fuels have a potential for reducing the research reactor fuel cycle costs while reducing, at the same time, the uranium enrichment of the fuel

  13. Tiger Teams Technical Assistance: Reliable, Universal Open Architecture for Card Access to Dispense Alternative Fuels

    2002-03-01

    Report discusses the dilemma of incorporating consistent, convenient, universal card access (or ''pay-at-the-pump'') systems into alternative fueling stations across the country. The state of California continues to be in the forefront of implementing alternative fuels for transportation applications. Aggressive efforts to deploy alternative fuel vehicles (AFVs) in California have highlighted the need to provide adequate fueling stations and develop appropriate, user-friendly means to purchase fuel at the pump. Since these fuels are not typically provided by petroleum companies at conventional fueling stations, and acceptance of cash is often not an option, a payment method must be developed that is consistent with the way individual AFV operators are accustomed to purchasing automotive fuels--with a credit card. At the same time, large fleets like the California Department of General Services must be able to use a single fuel card that offers comprehensive fleet management services. The Gas Technology Institute's Infrastructure Working Group (IWG) and its stakeholders have identified the lack of a common card reader system as a hurdle to wider deployment of AFVs in California and the United States. In conjunction with the U.S. Department of Energy's (DOE) National Clean Cities Program, the IWG has outlined a multi-phased strategy to systematically address the barriers to develop a more ''open'' architecture that's similar to the way gasoline and diesel are currently dispensed. Under the auspices of the IWG, survey results were gathered (circa 1999) from certain fuel providers, as a means to more carefully study card reader issues and their potential solutions. Pilot programs featuring card reader systems capable of accepting wider payment options have been attempted in several regions of the United States with mixed success. In early 2001, DOE joined the National Renewable Energy Laboratory (NREL), the

  14. Proceedings of the seminar on the joint research project between JAERI and Universities. 'Actinide researches for 21st century - fusion between chemistry and engineering'. August 20-21, 1999, Japan Atomic Energy Research Inst., Tokai, Japan

    NONE

    2000-06-01

    The Seminar on the Joint Research Project between JAERI and Universities was held in Tokai, August 20-21, 1999, to discuss future perspectives of the actinide researches for the nuclear fuel cycle. The papers related to the Joint Research Project on the Backend Chemistry were presented and discussed. The present report complies the papers contributed to the Seminar. (author)

  15. Proceedings of the seminar on the joint research project between JAERI and Universities. 'Actinide researches for 21st century - fusion between chemistry and engineering'. August 20-21, 1999, Japan Atomic Energy Research Inst., Tokai, Japan

    2000-06-01

    The Seminar on the Joint Research Project between JAERI and Universities was held in Tokai, August 20-21, 1999, to discuss future perspectives of the actinide researches for the nuclear fuel cycle. The papers related to the Joint Research Project on the Backend Chemistry were presented and discussed. The present report complies the papers contributed to the Seminar. (author)

  16. Teaching and Research with Accelerators at Tarleton State University

    Marble, Daniel K.

    2009-01-01

    Tarleton State University students began performing both research and laboratory experiments using accelerators in 1998 through visitation programs at the University of North Texas, US Army Research Laboratory, and the Naval Surface Warfare Center at Carderock. In 2003, Tarleton outfitted its new science building with a 1 MV pelletron that was donated by the California Institution of Technology. The accelerator has been upgraded and supports a wide range of classes for both the Physics program and the ABET accredited Engineering Physics program as well as supplying undergraduate research opportunities on campus. A discussion of various laboratory activities and research projects performed by Tarleton students will be presented.

  17. Patentometrics As Performance Indicators for Allocating Research Funding to Universities

    Mortensen, Peter Stendahl

    This paper is part of a preliminary investigation of potential indicators on the performance of universities and other public research institutions to be used for allocating general and other research funding. The paper will describe and discuss potential patentometrics and how they can be used...... in different types of analyses and evaluations in general and relating to universities and other public research institutions. Further, the relevance and possibility of including some patentometrics in the allocation of research funding is discussed. Also, other metrics regarding academic linkages...

  18. Fuel performance of rod-type research reactor fuel using a centrifugally atomized U-Mo powder

    Ryu, Ho Jin; Park, Jong Man; Lee, Yoon Sang; Kim, Chang Kyu

    2009-01-01

    A low enriched uranium nuclear fuel for research reactors has been developed in order to replace a highly enriched uranium fuel according to the non-proliferation policy under the reduced enrichment for research and test reactors (RERTR) program. In KAERI, a rod-type U 3 Si dispersion fuel has been developed for a localization of the HANARO fuel and a U 3 Si/Al dispersion fuel of 3.15 gU/cc has been used at HANARO as a driver fuel since 2005. Although uranium silicide dispersion fuels such as U 3 Si 2 /Al and U 3 Si/Al are being used widely, high uranium density dispersion fuels (8-9 g/cm 3 ) are required for some high performance research reactors. U-Mo alloys have been considered as one of the most promising uranium alloys for a dispersion fuel due to their good irradiation performance. An international qualification program on U-Mo fuel to replace a uranium silicide dispersion fuel with a U-Mo dispersion fuel has been carried out

  19. Report on research outline in 1999 fiscal year on public collection type research of nuclear fuel cycle.

    NONE

    2000-07-01

    The Japan Nuclear Cycle Development Institute (JNC) initiated a system to promote the public collection type researches of nuclear fuel cycle since 1999, in order to intend to promote collaboration with universities and research institutes. The system aims to intend to activate researching environment in JNC by intercourse, information exchange, publication of results and so on between researchers in and out of JNC, effectively to proceed basic and fundamental R and D. Here were outlined on eleven researching theme, such as upgrading of velocity and temperature measurement of non-contact type fluid by using electromagnetic ultrasonic wave, development of temperature history memory elements for radiation environment test of a fast breeder reactor, direct glassification of salt wastes by using oxygen plasma, a method on dissolving extraction of metal oxides by using a super-critical fluid, creation of highly separable materials by assistance of computational chemistry (aiming at high order processing of high level radioactive wastes), and so on. (G.K.)

  20. Report on research outline in 1999 fiscal year on public collection type research of nuclear fuel cycle

    2000-07-01

    The Japan Nuclear Cycle Development Institute (JNC) initiated a system to promote the public collection type researches of nuclear fuel cycle since 1999, in order to intend to promote collaboration with universities and research institutes. The system aims to intend to activate researching environment in JNC by intercourse, information exchange, publication of results and so on between researchers in and out of JNC, effectively to proceed basic and fundamental R and D. Here were outlined on eleven researching theme, such as upgrading of velocity and temperature measurement of non-contact type fluid by using electromagnetic ultrasonic wave, development of temperature history memory elements for radiation environment test of a fast breeder reactor, direct glassification of salt wastes by using oxygen plasma, a method on dissolving extraction of metal oxides by using a super-critical fluid, creation of highly separable materials by assistance of computational chemistry (aiming at high order processing of high level radioactive wastes), and so on. (G.K.)

  1. Spent fuel management options for research reactors in Latin America

    2006-06-01

    Research reactors (RRs) have been operated in Latin America since the late 1950s, and a total of 23 RRs have been built in the region. At the time of writing (November 2005), 18 RRs are in operation, 4 have been shut down and 1 has been decommissioned. The number of operating RRs in Latin America represents around 6% of the existing operational RRs worldwide and around 21% of the RRs operating in developing countries. Common to all RRs in the region is a consistent record of safe and successful operation. With the purpose of carrying out a collaborative study of different aspects of the management of spent fuel from RRs, some countries from the region proposed to the IAEA in 2000 the organization of a Regional Project. The project (IAEA TC Regional Project RLA/4/018) that was approved for the biennium 2001-2002 and extended for 2003-2004 included the participation of Argentina, Brazil, Chile, Mexico and Peru. The main objectives of this project were: (a) to define the basic conditions for a regional strategy for managing spent fuel that will provide solutions compatible with the economic and technological realities of the countries involved; and (b) to determine what is needed for the temporary wet and dry storage of spent fuel from the research reactors in the countries of the Latin American region that participated in the project. This TECDOC is based on the results of TC Regional Project RLA/4/018. This project was successful in identifying and assessing a number of viable alternatives for RRSF management in the Latin American region. Options for operational and interim storage, spent fuel conditioning and final disposal have been carefully considered. This report presents the views of Latin American experts on RR spent fuel management and will be useful as reference material for the Latin American RR community, decision making authorities in the region and the public in general

  2. Experimental research on safety assurance of advanced WWER fuel cycles

    Krainov, Ju.; Kukushkin, Ju.

    2002-01-01

    The paper presents the results of experimental investigations on substantiation of implementation of a modernized butt joint for the WWER-440 reactor, carried out in the critical test facility 'P' in the RRC 'Kurchatov Institute'. The comparison results of the calculation and experimental data obtained in the physical startup of Volgodonsk NPP-1 with the WWER-1000 are also given. In the implementation of four-year fuel cycle in the WWER-440 with the average enrichment of fuel makeup 3.82% it was solved to conduct experimental research of power distribution in the vicinity of control rod butt junction. Moreover, it was assumed that adequate actions should be applied to eliminate inadmissible power jumps, if necessary. It is not available to measure their values in NPP conditions. Therefore, the power distribution near the butt joint was studied in a 19-rod bank installed in the critical test facility 'P' first for the normal design of the joint when surrounding fuel assemblies enrichment goes up. Then a set of calculation and tests was fulfilled to optimize a butt junction design. On the base of this research the composition of a butt junction was advanced by placing Hf plates into the junction. The effectiveness of modernized butt joint design was experimentally confirmed. In Volgodonsk NPP-1 with WWER-1000 the four-year fuel cycle is being implemented. During the physical startup of the reactor the measurements of the reactivity effects and coefficients were measured at the minimum controlled flux level, and the parameters of a number of critical states were recorded. The data obtained were compared with the calculation. The validity of the certified code package for forecasting the neutronic characteristics of WWER-1000 cores in the implementation of a four year fuel cycle has been supported (Authors)

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

    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.)

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

    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.)

  5. Utilization of research reactors in universities and their medical applications

    Kanda, Keiji.

    1983-01-01

    In Japan, five research reactors and a critical assembly are operated by the universities. They are opened to all university researchers, the system of which is financially supported by the Ministry of Education, Culture and Science of the Japanese government. Usually KUR is operated eight cycles per year. One cycle consists of the following four week operation: 1. Mainly for researchers from other universities; 2. Mainly for researchers in the institute; 3. Mainly for beam experiment; 4. Sort time experiment. In the weeks of 1 ∼ 3 the KUR is operated continously from Tuesday morning to Friday evening. The experiment include studies on physics, chemistry, biology, medicine, engineering etc. Recently the medical application of research reactors has become popular in Japan. The new technique of the boron neutron capture thereby has been successfully applied to brain tumors and will be to melanoma (skin cancer) in near future. (author)

  6. Building technology transfer within research universities an entrepreneurial approach

    O'Shea, Rory P

    2014-01-01

    For the past number of years, academic entrepreneurship has become one of the most widely studied topics in the entrepreneurship literature. Yet, despite all the research that has been conducted to date, there has not been a systematic attempt to analyze critically the factors which lie behind successful business spin-offs from university research. In this book, a group of academic thought-leaders in the field of technology transfer examine a number of areas critical to the promotion of start-ups on campus. Through a series of case studies, they examine current policies, structures, program initiatives and practices of fourteen international universities to develop a theory of successful academic entrepreneurship, with the aim of helping other universities to enhance the quality of their university transfer programs. This book is a valuable resource for researchers and graduate students working on innovation, entrepreneurship and technology transfer, as well as senior managers and policymakers.

  7. Fuel burnup analysis for the Moroccan TRIGA research reactor

    El Bakkari, B.; El Bardouni, T.; Nacir, B.; El Younoussi, C.; Boulaich, Y.; Boukhal, H.; Zoubair, M.

    2013-01-01

    Highlights: ► A fuel burnup analysis of the 2 MW TRIGA MARK II Moroccan research reactor was established. ► Burnup calculations were done by means of the in-house developed burnup code BUCAL1. ► BUCAL1 uses the MCNP tallies directly in the calculation of the isotopic inventories. ► The reactor life time was found to be 3360 MW h considering full power operating conditions. ► Power factors and fluxes of the in-core irradiation positions are strongly affected by burnup. -- Abstract: The fundamental advantage and main reason to use Monte Carlo methods for burnup calculations is the possibility to generate extremely accurate burnup dependent one group cross-sections and neutron fluxes for arbitrary core and fuel geometries. Yet, a set of values determined for a material at a given position and time remains accurate only in a local region, in which neutron spectrum and flux vary weakly — and only for a limited period of time, during which changes of the local isotopic composition are minor. This paper presents the approach of fuel burnup evaluation used at the Moroccan TRIGA MARK II research reactor. The approach is essentially based upon the utilization of BUCAL1, an in-house developed burnup code. BUCAL1 is a FORTRAN computer code designed to aid in analysis, prediction, and optimization of fuel burnup performance in nuclear reactors. The code was developed to incorporate the neutron absorption reaction tally information generated directly by MCNP5 code in the calculation of fissioned or neutron-transmuted isotopes for multi-fueled regions. The fuel cycle length and changes in several core parameters such as: core excess reactivity, control rods position, fluxes at the irradiation positions, axial and radial power factors and other parameters are estimated. Besides, this study gives valuable insight into the behavior of the reactor and will ensure better utilization and operation of the reactor during its life-time and it will allow the establishment of

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

    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.

  9. 75 FR 14476 - Commercialization of University Research Request for Information

    2010-03-25

    ... jobs. Two key parts of this strategy are to increase support for both the fundamental research at our... identify ways in which we can increase the economic impact of Federal investment in university R&D and the... Centers Program provides core funds to move fundamental research through proof-of-concept testing and...

  10. Highlight: Research Chair unites four West African universities in ...

    2016-04-14

    Apr 14, 2016 ... Local and regional experts including researchers, consultants, and academics convened in Cotonou, Benin, on February 26, 2015 to launch a Research Chair on EcoHealth. The Chair unites four West African universities that have pledged to reduce air pollution and non-communicable respiratory ...

  11. Gender, Performativity, and Leadership: Department Chairs in Research Universities

    Lepkowski, Christine

    2014-01-01

    Women are significantly underrepresented as administrators in higher education leadership. This qualitative study examined the leadership of department chairs at public research universities to better understand how their gender and other identities affected their leadership. The following research questions shaped the study: (1) How do department…

  12. Research Methodologies Explored for a Paradigm Shift in University Teaching.

    Venter, I. M.; Blignaut, R. J.; Stoltz, D.

    2001-01-01

    Innovative teaching methods such as collaborative learning, teamwork, and mind maps were introduced to teach computer science and statistics courses at a South African university. Soft systems methodology was adapted and used to manage the research process of evaluating the effectiveness of the teaching methods. This research method provided proof…

  13. Theoretical high energy physics research at the University of Chicago

    Rosner, J.L.; Martinec, E.J.; Sachs, R.G.

    1989-12-01

    This report contains brief discussions on theoretical High Energy Physics research done by the researchers at University of Chicago. Some topics covered are: lepton production; kaon decay; Higgs boson production; electric dipole moment of the neutron; string models; supersymmetry; and cosmic ray shower

  14. The role of universities in the US nuclear research enterprise

    Taylor, J.J.

    1991-01-01

    The vitally important role of the universities in nuclear research is embodied in the three functions of education, research, and policymaking. These three functions are discussed from the perspective of nuclear power's unique demands for quality and its pioneering interface with societal and environmental aspirations

  15. Accelerator based research facility as an inter university centre

    Mehta, G.K.

    1995-01-01

    15 UD pelletron has been operating as a user facility from July 1991. It is being utilised by a large number of universities and other institutions for research in basic Nuclear Physics, Materials Science, Atomic Physics, Radiobiology and Radiation Chemistry. There is an on-going programme for augmenting the accelerator facilities by injecting Pelletron beams into superconducting linear accelerator modules. Superconducting niobium resonator is being developed in Argonne National Laboratory as a joint collaborative effort. All other things such as cryostats, rf instrumentation, cryogenic distribution system, computer control etc are being done indigenously. Research facilities, augmentation plans and the research being conducted by the universities in various disciplines are described. (author)

  16. Research on the reactor physics using the Kyoto University Critical Assembly (KUCA)

    1986-10-01

    The Kyoto University Critical Assembly [KUCA] is a multi-core type critical assembly established in 1974, as a facility for the joint use study by researchers of all universities in Japan. Thereafter, many reactor physics experiments have been carried out using three cores (A-, B-, and C-cores) in the KUCA. In the A- and B-cores, solid moderator such as polyethylene or graphite is used, whereas light-water is utilized as moderator in the C-core. The A-core has been employed mainly in connection with the Cockcroft-Walton type accelerator installed in the KUCA, to measure (1) the subcriticality by the pulsed neutron technique for the critical safety research and (2) the neutron spectrum by the time-of-flight technique. Recently, a basic study on the tight lattice core has also launched using the A-core. The B-core has been employed for the research on the thorium fuel cycle ever since. The C-core has been employed (1) for the basic studies on the nuclear characteristics of light-water moderated high-flux research reactors, including coupled-cores, and (2) for a research related to reducing enrichment of uranium fuel used in research reactors. The C-core is being utilized in the reactor laboratory course experiment for students of ten universities in Japan. The data base of the KUCA critical experiments is generated so far on the basis of approximately 350 experimental reports accumulated in the KUCA. Besides, the assessed KUCA code system has been established through analyses on the various KUCA experiments. In addition to the KUCA itself, both of them are provided for the joint use study by researchers of all universities in Japan. (author)

  17. Dry reloading and packaging of spent fuel at TRIGA MARK I reactor of Medical University Hanover (MHH), Germany

    Haferkamp, D.

    2008-01-01

    which is protected against contamination spreading and provided with a conventional driven by a floor conveyor trolley. 4. Mobile Reloading Station placed directly on the shipping cask, containing adapter to each type of shipping cask, shielded sliding plates and provided with a loading plate for positioning of six packs into the shipping cask. 5. Auxiliary systems including: - cask lid lifting device; - video monitoring device for the shipping cask lids and loads; - air film gliders for transport of shipping casks. Finally one concludes: the dry reloading station for spent fuel packaging into the shipping casks has successfully operated for TRIGA MARK I reactor at Medical University Hanover as well as at the VKTA - Research Reactor in Rossendorf, Germany. It is available as a proven technique for the dry reloading of spent fuels into the shipping casks. (author)

  18. Are university rankings useful to improve research? A systematic review.

    Vernon, Marlo M; Balas, E Andrew; Momani, Shaher

    2018-01-01

    Concerns about reproducibility and impact of research urge improvement initiatives. Current university ranking systems evaluate and compare universities on measures of academic and research performance. Although often useful for marketing purposes, the value of ranking systems when examining quality and outcomes is unclear. The purpose of this study was to evaluate usefulness of ranking systems and identify opportunities to support research quality and performance improvement. A systematic review of university ranking systems was conducted to investigate research performance and academic quality measures. Eligibility requirements included: inclusion of at least 100 doctoral granting institutions, be currently produced on an ongoing basis and include both global and US universities, publish rank calculation methodology in English and independently calculate ranks. Ranking systems must also include some measures of research outcomes. Indicators were abstracted and contrasted with basic quality improvement requirements. Exploration of aggregation methods, validity of research and academic quality indicators, and suitability for quality improvement within ranking systems were also conducted. A total of 24 ranking systems were identified and 13 eligible ranking systems were evaluated. Six of the 13 rankings are 100% focused on research performance. For those reporting weighting, 76% of the total ranks are attributed to research indicators, with 24% attributed to academic or teaching quality. Seven systems rely on reputation surveys and/or faculty and alumni awards. Rankings influence academic choice yet research performance measures are the most weighted indicators. There are no generally accepted academic quality indicators in ranking systems. No single ranking system provides a comprehensive evaluation of research and academic quality. Utilizing a combined approach of the Leiden, Thomson Reuters Most Innovative Universities, and the SCImago ranking systems may provide

  19. Reprocessing of research reactor fuel the Dounreay option

    Cartwright, P.

    1997-08-01

    Reprocessing is a proven process for the treatment of spent U/Al Research Reactor fuel. At Dounreay 12679 elements have been reprocessed during the past 30 years. For reactors converting to LEU fuel the uranium recovered in reprocessing can be blended down to less than 20% U{sub 235}, enrichment and be fabricated into new elements. For reactors already converted to LEU it is technically possible to reprocess spent silicide fuel to reduce the U{sub 235} burden and present to a repository only stable conditioned waste. The main waste stream from reprocessing which contains the Fission products is collected in underground storage tanks where it is kept for a period of at least five years before being converted to a stable solid form for return to the country of origin for subsequent storage/disposal. Discharges to the environment from reprocessing are low and are limited to the radioactive gases contained in the spent fuel and a low level liquid waste steam. Both of these discharges are independently monitored, and controlled within strict discharge limits set by the UK Government`s Scottish Office. Transportation of spent fuel to Dounreay has been undertaken using many routes from mainland Europe and has utilised over the past few years both chartered and scheduled vessel services. Several different transport containers have been handled and are currently licensed in the UK. This paper provides a short history of MTR reprocessing at Dounreay, and provides information to show reprocessing can satisfy the needs of MTR operators, showing that reprocessing is a valuable asset in non-proliferation terms, offers a complete solution and is environmentally acceptable.

  20. Irradiated fuel by-product separation research in Canada

    Burston, M.

    1984-01-01

    Although no decision has been made to reprocess irradiated CANDU fuel, by-product separation research has recently been initiated in Canada because of its potential importance to Canadian research programs in advanced fuel cycles (especially U/Pu cycle development in the near term) and nuclear waste management. In addition, separated by-products could have a significant commercial potential. Demonstrated applications include: heat sources, gamma radiation sources, light sources, new materials for productions of other useful isotopes, etc. For illustrative purposes the calculated market value of by-products currently stored in irradiated CANDU fuel is approximately $210/kgU. Ontario Hydro has initiated a program to study the application of new separation technolgies, such as laser-based techniques and the plasma ion cyclotron resonance separation technique, to either augment and/or supplant the chemical extraction methods. The main goal is to develop new, more economical extraction methods in order to increase the magnitude of the advantages resulting from this approach to reprocessing. (author)

  1. Irradiation experience of IPEN fuel at IEA-R1 research reactor

    Perrotta, Jose A.; Neto, Adolfo; Durazzo, Michelangelo; Souza, Jose A.B. de; Frajndlich, Roberto

    1998-01-01

    IPEN/CNEN-SP produces, for its IEA-R1 Research Reactor, MTR fuel assemblies based on U 3 O 8 -Al dispersion fuel type. Since 1985 a qualification program on these fuel assemblies has been performed. Average 235 U burnup of 30% and peak burnup of 50% was already achieved by these fuel assemblies. This paper presents some results acquire, by these fuel assemblies, under irradiation at IEA-R1 Research Reactor. (author)

  2. Research in JAERI on the backend of nuclear fuel cycle

    Maeda, Mitsuru; Takeshita, Isao

    1999-01-01

    Japan's policy of the backend of nuclear fuel cycle is to reprocess spent fuels and recycle recovered plutonium and uranium, under the principle of no surplus plutonium. High-level radioactive waste separated during reprocessing will be disposed of after solidification in vitrified form, followed by the storage for 30 to 50 years and finally by ultimate disposal in a deep geological formation. The role of JAERI and the effective utilization of NUCEF would become more important. The current status of JAERI's research on backend cycle is reviewed together with the future research direction with emphases on NUCEF utilization. (1) Major objectives of safety research is to develop safety criteria and establish technical bases for licensing, to improve the safety of current or near future technology and to clarify the safety margin of licensed technology. (2) The present goal of fundamental research is to show or clarify the chemical or scientific feasibility of advanced system such as for recycling minor actinides or for incinerating long-lived nuclides. (3) Supporting research for nuclear material control is also conducted mainly for international contribution to strengthened safeguards by IAEA and to frame working of international monitoring system for CTBT. (J.P.N.)

  3. The value and cost of university research reactors

    Harling, O.K.; Bernard, J.A.

    1989-01-01

    In this paper the authors provide a brief overview of the value and costs of U.S. university research reactors (URRs). More than three dozen URRs are currently operating in an approximately equal number of states. These URRs are an important part of the U.S. capabilities in nuclear science and technology. These multipurpose research facilities are located on the campuses of universities and colleges and therefore are easily accessible to university staff and students as well as to the high-technology industries, which often are located near universities. The close proximity, i.e., convenient location, to a diverse user base is a major reason for the multifaceted applications of URRs, including basic and applied science, technology, education, and industrial applications. The URRs have an extraordinarily broad range of applicability, including medicine and the life sciences, materials science, environmental sciences, earth and planetary sciences, and nuclear energy

  4. The impact of science shops on university research and education

    Jørgensen, Michael Søgaard

    2000-01-01

    Science shops are mediating agencies at universities that give citizens and citizen groups access to the resources of the university through co-operation with students and researchers. Science shops have three aims: to support citizens and citizen groups in their efforts getting influence...... to the impact of science shops on universities and on society are discussed. A typology for the different types of knowledge requested by citizens and citizen groups through science shops is presented (documentation, knowledge building, development of new perspectives). As important aspects of the potentials......, prerequisites and limits to the impact of science shops are discussed the networking between the science shop and the researchers and teachers and with the citizens and other external actors, and the content and the structure of the curricula at the university....

  5. Shifting to non-explosive fuels for research reactors

    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

  6. University-Industry Research Collaboration: A Model to Assess University Capability

    Abramo, Giovanni; D'Angelo, Ciriaco Andrea; Di Costa, Flavia

    2011-01-01

    Scholars and policy makers recognize that collaboration between industry and the public research institutions is a necessity for innovation and national economic development. This work presents an econometric model which expresses the university capability for collaboration with industry as a function of size, location and research quality. The…

  7. The Global Climate and Energy Project at Stanford University: Fundamental Research Towards Future Energy Technologies

    Milne, Jennifer L.; Sassoon, Richard E.; Hung, Emilie; Bosshard, Paolo; Benson, Sally M.

    The Global Climate and Energy Project (GCEP), at Stanford University, invests in research with the potential to lead to energy technologies with lower greenhouse gas emissions than current energy technologies. GCEP is sponsored by four international companies, ExxonMobil, GE, Schlumberger, and Toyota and supports research programs in academic institutions worldwide. Research falls into the broad areas of carbon based energy systems, renewables, electrochemistry, and the electric grid. Within these areas research efforts are underway that are aimed at achieving break-throughs and innovations that greatly improve efficiency, performance, functionality and cost of many potential energy technologies of the future including solar, batteries, fuel cells, biofuels, hydrogen storage and carbon capture and storage. This paper presents a summary of some of GCEP's activities over the past 7 years with current research areas of interest and potential research directions in the near future.

  8. Center for Fuel Cell Research and Applications development phase. Final report

    NONE

    1998-12-01

    The deployment and operation of clean power generation is becoming critical as the energy and transportation sectors seek ways to comply with clean air standards and the national deregulation of the utility industry. However, for strategic business decisions, considerable analysis is required over the next few years to evaluate the appropriate application and value added from this emerging technology. To this end the Houston Advanced Research Center (HARC) is proposing a three-year industry-driven project that centers on the creation of ``The Center for Fuel Cell Research and Applications.`` A collaborative laboratory housed at and managed by HARC, the Center will enable a core group of six diverse participating companies--industry participants--to investigate the economic and operational feasibility of proton-exchange-membrane (PEM) fuel cells in a variety of applications (the core project). This document describes the unique benefits of a collaborative approach to PEM applied research, among them a shared laboratory concept leading to cost savings and shared risks as well as access to outstanding research talent and lab facilities. It also describes the benefits provided by implementing the project at HARC, with particular emphasis on HARC`s history of managing successful long-term research projects as well as its experience in dealing with industry consortia projects. The Center is also unique in that it will not duplicate the traditional university role of basic research or that of the fuel cell industry in developing commercial products. Instead, the Center will focus on applications, testing, and demonstration of fuel cell technology.

  9. Analysis of different research activities and description of parties within the Swedish Knowledge Centre for Renewable Transportation Fuels

    Lundgren, Joakim [Bio4Energy, Luleaa (Sweden); Wallberg, Ola [Lund Univ., Lund (Sweden)

    2012-07-01

    The Swedish Knowledge Centre for Renewable Transportation Fuels (f3) is a nationwide centre, which through cooperation and a systems approach will contribute to the development of sustainable fossil free fuels for transportation. The centre will, through joint efforts by the centre partners, perform syntheses of current research about the production of renewable fuels as well as supplementing research, such as comparative systems analyses of fuels, processes, raw materials and plant design. f3 provides a platform for collaboration between centre partners, with a common vision of sustainable fuels for transportation and common objectives. The centre partners include Sweden's most active universities and research institutes within the field, as well as a number of highly relevant industrial companies. New fuels will be an important component of a strategy to reduce both greenhouse gas emissions and our dependence on petroleum. The Swedish Government has established a vision for the Swedish transport industry to function without fossil fuels by 2030. Such a development requires a concerted response, with participation from all stake holders. Swedish researchers in various disciplines and at various colleges and institutes have a unique breadth and they are at the forefront in several areas of knowledge appropriate for a centre for renewable fuels. Through collaboration, f3 should help to link engineering and systems research and communicate results and conclusions from these research efforts. Within the f3 centre, several parties with different research activities are represented. This document is a snapshot of the different parties at the end of 2011 where the stake holders are described and their current research is highlighted. Also, the different projects conducted by the parties have been categorized and presented at the end of the document.

  10. Hydrogen and fuel cell research: Institute for Integrated Energy Systems (IESVic)

    Pitt, L.

    2006-01-01

    Vision: IESVic's mission is to chart feasible paths to sustainable energy. Current research areas of investigation: 1. Energy system analysis 2. Computational fuel cell engineering; Fuel cell parameter measurement; Microscale fuel cells 3. Hydrogen dispersion studies for safety codes 4. Active magnetic refrigeration for hydrogen liquifaction and heat transfer in metal hydrides 5. Hydrogen and fuel cell system integration (author)

  11. Scientific research on the back-end of the fuel cycle for the 21. century

    2000-01-01

    The aim of the Atalante-2000 conference is to present the major research axis concerning the nuclear fuel cycle back-end. The different topics are: - Present options concerning fuel cycle back-end; - Reprocessing of spent fuel; - Advanced separation for transmutation; - Processing and packaging of radioactive wastes; - Design and fabrication of targets for transmutation; and - Conversion of military plutonium into MOX fuels

  12. Research on Foreign Language Teaching in North America : The University of Toronto and Michigan State University

    Lauer, Joe; Yamada, Jun

    1998-01-01

    Both the Modern Language Centre at the University of Toronto's Ontario Institute for Studies in Education (OISE/UT), and the English Language Center at Michigan State University, are acknowledged as being among the best centers for applied linguistics research and education in the world. The Modern Language Centre has published important findings in the areas of second language acquisition, psycholinguistics, sociolinguistics and language curricula. Meanwhile, the English Language Center has ...

  13. Industry–University Collaboration for Research and Education

    Shalaby, B.; Hopwood, J.

    2016-01-01

    Full text: A joint partnership UNENE between industry and 12 universities was established in 2002 in anticipation of a large number of nuclear staff retiring starting 2010 and beyond. The focus of UNENE was to support nuclear related research in universities in support of the operating Candu nuclear plants, establish an M.Eng/Diploma degree to transfer the knowledge of design and licensing of the operating plants and as such ensure a sustainable supply of highly qualified personnel (HQP) for deployment by industry. This paper will address the benefits of such partnership as of 2016 in details in the area of research, education and supply of HQP to industry. (author

  14. Status of research reactor spent fuel world-wide: Database summary

    Ritchie, I.G.

    1996-01-01

    Results complied 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 industrialized 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). 4 refs, 17 figs, 4 tabs

  15. Physical protection of radioactive materials in a University Research Institute

    Boeck, H.

    1998-01-01

    Although nuclear research centers attached to universities usually do not keep large inventories of radioactive or special nuclear material, the mentioned material has still to be under strict surveillance and safeguards if applicable. One problem in such research centers is the large and frequent fluctuation of persons - mainly students, scientists or visiting guest scientists - using such materials for basic or applied research. In the present paper an overview of protective actions in such a research institute will be given and experience of more than 36 years will be presented. (author)

  16. University-Level Research Projects for High School Students

    McConnell, Mark L.

    2000-01-01

    The goal of this project was to provide an opportunity for high school students to participate in university-level research projects. In this case, students from Pinkerton Academy (Derry, New Hampshire) were invited to participate in efforts to catalog data from the COMPTEL experiment on NASA's Compton Gamma-Ray Observatory (CGRO). These activities were part of a senior level honors course at Pinkerton. Although the success of this particular program was rather limited, we feel that the general concept is a sound one. In principle, the concept of partnerships between local schools and university researchers is one that could be especially attractive to soft money researchers. Programs can be carefully designed to benefit both the students and the research program.

  17. Building Support for Research Data Management: Biographies of Eight Research Universities

    Katherine G. Akers

    2014-10-01

    Full Text Available Academic research libraries are quickly developing support for research data management (RDM, including both new services and infrastructure. Here, we tell the stories of how eight different universities have developed programs of RDM support, focusing on the prominent role of the library in educating and assisting researchers with managing their data throughout the research lifecycle. Based on these stories, we construct timelines for each university depicting key steps in building support for RDM, and we discuss similarities and dissimilarities among universities in motivation to provide RDM support, collaborations among campus units, assessment of needs and services, and changes in staffing.

  18. NREL Fuels and Engines Research: Maximizing Vehicle Efficiency and

    chemistry, conversion, and combustion to the evaluation of advanced fuels in actual engines and vehicles . With fuel chemistry, our scientific discoveries start out small. We use quantum mechanical modeling to explore how fuels with varying chemistry interact with engine and vehicle design. At our Fuel Combustion

  19. Legislation on university technology transfer and research management 2012

    2012-02-01

    This book deals with legislation on university technology transfer in 2012, which includes invention promotion act, legislation on technology transfer and promotion of industrialization, legislation on industrial education and industrial cooperation, and special legislation on venture business. It lists the legislation related research and development by government department : fundamental law of scientific technique, law on evaluation and management of domestic research development business, national science and technology council and the patent office.

  20. Online journalism meets the university: ideas for teaching and research

    Salaverría, R. (Ramón)

    2011-01-01

    During the last decade, the teaching and research on online journalism has become widespread in journalism faculties throughout the world. Such development has brought many undergraduate and graduate courses on the issue, as well as a number of networks of researchers and specialized publications in many countries. Once this initial process is over, it is time to bring the discipline of online journalism to its maturity at the university. For this aim, the author proposes to switch the curren...

  1. Proven collaboration model for impact generating research with universities

    Bezuidenhout, DF

    2010-09-01

    Full Text Available -optics, image processing and computer vision. This paper presents the research collaboration model with universities that has ensured the PRISM programme's success. It is shown that this collaboration model has resulted in a pipeline of highly-skilled people...

  2. Preparation of Social Studies Teachers at Major Research Universities.

    Dumas, Wayne

    1993-01-01

    Reports on a study of the preparation of secondary social studies teachers at major state-supported research universities. Finds relatively few institutions have followed the Holmes Group recommendations and many continue to prepare broad field social studies teachers leaving them deficient in some social science fields. (CFR)

  3. Three Essays on Bureaucracy at American Research Universities

    Taggart, Gabel

    2017-01-01

    The three essays in this dissertation each examine how aspects of contemporary administrative structure within American research universities affect faculty outcomes. Specific aspects of administrative structure tested in this dissertation include the introduction of new administrative roles, administrative intensity (i.e., relative size of…

  4. Mapping Postgraduate Research at the University of Zambia: A ...

    Mapping Postgraduate Research at the University of Zambia: A review of dissertations for the Master of Medicine Programme. ... Over half of the dissertations (76, 57.6%) addressed the determinants of the cause, risk and development of diseases; and a third dealt with management and evaluation of diseases (26 and 18, ...

  5. Linking research with the other missions of the University

    cdaffe

    leaving the problems of Africa's industrial, economic and social development ... The approach to doctoral studies is being called into question, especially as ... existing mechanisms of cooperation among universities to respond to these needs? ... research networks operating at sub-regional or continental levels, and set up ...

  6. Linking research with the other missions of the university | IDRC ...

    2010-12-15

    Dec 15, 2010 ... He could have added a third conclusion: the results of research are not sufficiently used in programming teaching and the definition of course content dispensed to students. The objective of this concept note is not to discuss all the problems facing the African university. It will be limited to just one aspect of ...

  7. Reforming the University: The Role of the Research Center.

    Sieber, Sam D.; Lazarsfeld, Paul F.

    The authors seek to show the potentiality of research organizations for the achievement of basic university goals, and to isolate the conditions that impede or promote the success of these integrative agencies. In addition, they examine the role of the managerial scholars who are in the positions of leadership since they believe this role is vital…

  8. Institutional Repositories in Indian Universities and Research Institutes: A Study

    Krishnamurthy, M.; Kemparaju, T. D.

    2011-01-01

    Purpose: The purpose of this paper is to report on a study of the institutional repositories (IRs) in use in Indian universities and research institutes. Design/methodology/approach: Repositories in various institutions in India were accessed and described in a standardised way. Findings: The 20 repositories studied covered collections of diverse…

  9. The role of college and university faculty in the fossil fuel divestment movement

    Jennie C. Stephens

    2018-05-01

    Full Text Available Colleges and universities have played a critical role in the growing social movement to divest institutional endowments from fossil fuels. While campus activism on fossil fuel divestment has been driven largely by students and alumni, faculty are also advocating to their administrators for institutional divestment from fossil fuels. This article characterizes the role of faculty by reviewing signatories to publicly available letters that endorse fossil fuel divestment. Analysis of 30 letters to administrators signed by faculty at campuses throughout the United States and Canada reveals support for divestment from 4550 faculty across all major fields of inquiry and scholarship, and all types of faculty positions. Of these signers, more than 225 have specific expertise in climate change or energy. An in-depth analysis of 18 of these letters shows that a significantly greater proportion of tenured faculty sign open letters of support for divestment than do not-yet-tenured tenure-track faculty (15.4% versus 10.7%, perhaps reflecting concerns among not-yet-tenured faculty that such support might jeopardize their career advancement. This analysis suggests that faculty support for the divestment movement is more widespread than commonly recognized; this movement is more mainstream, and broader-based, than is often recognized. Revealing the scope and scale of faculty support for fossil fuel divestment may encourage additional faculty to engage, support and endorse this growing social movement that highlights the social impact of investment decisions, and calls upon colleges and universities to align their investment practices with their academic missions and values.

  10. University of Maine Integrated Forest Product Refinery (IFPR) Technology Research

    Pendse, Hemant P.

    2010-11-23

    This project supported research on science and technology that forms a basis for integrated forest product refinery for co-production of chemicals, fuels and materials using existing forest products industry infrastructure. Clear systems view of an Integrated Forest Product Refinery (IFPR) allowed development of a compelling business case for a small scale technology demonstration in Old Town ME for co-production of biofuels using cellulosic sugars along with pulp for the new owners of the facility resulting in an active project on Integrated Bio-Refinery (IBR) at the Old Town Fuel & Fiber. Work on production of advanced materials from woody biomass has led to active projects in bioplastics and carbon nanofibers. A lease for 40,000 sq. ft. high-bay space has been obtained to establish a Technology Research Center for IFPR technology validation on industrially relevant scale. UMaine forest bioproducts research initiative that began in April 2006 has led to establishment of a formal research institute beginning in March 2010.

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

    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

  12. Description and Pathology of Research Development in Tabriz Medical University

    Alireza Farajollahi

    2009-02-01

    Full Text Available Background and purpose: Research in medical science, as in all other fields of science, is necessary in order to maintain and improve the public health. This is achievable only by researchers and faculty members. This study is attempt o identify intra-organizational factors that influence research planning and related interventions in Tabriz Medical University.Methods: In this descriptive cross-sectional study, the study group included all faculty members and masters of science (equivalent to faculties in Tabriz Medical University, of which 121 persons wereselected randomly. Lickert style questionnaires were developed to evaluate and compare the attitudes toward project approval process, knowledge about research facilities, departmental cooperationsin research, and researchers’ capabilities in project execution. Data analysis was performed using SPSS software.Results: During a 3 year period, each faculty member had, on average, supervised 5.17 dissertations, conducted 1.15 approved research projects, and had 3.4 presentations in domestic and 0.36 presentations in international conferences. Lack of time was the main problem in conducting research.Comparing faculties with and without research experience, there was significant differences in regard of access to research facilities (pthe level of research knowledge (pmotivations, job satisfaction, departmental cooperation, and expecting benefits from conductingresearch.Conclusion: According to the faculties’ views, intra-organizational problems are less important than personal factors in performing research projects; i.e. the main obstacles for research were lack of time, and lack of competence in research methodology and problem-finding. Intra-organizational factors such as delay in project approval and lack of knowledge about research priorities are classified in the next levels.Keywords: FACULTY MEMBERS, RESEARCH PROBLEMS, INTRA-ORGANIZATIONAL FACTORS

  13. Nuclear characteristics evaluation for Kyoto University Research Reactor with low-enriched uranium core

    Nakajima, Ken; Unesaki, Hironobu [Kyoto University Research Reactor Institute, Kumatori-cho Sennan-gun Osaka (Japan)

    2008-07-01

    A project to convert the fuel of Kyoto University Research Reactor (KUR) from highly enriched uranium (HEU) to low-enriched uranium (LEU) is in progress as a part of RERTR program. Prior to the operation of LEU core, the nuclear characteristics of the core have been evaluated to confirm the safety operation. In the evaluation, nuclear parameters, such as the excess reactivity, shut down margin control rod worth, reactivity coefficients, were calculated, and they were compared with the safety limits. The results of evaluation show that the LEU core is able to satisfy the safety requirements for operation, i.e. all the parameters satisfy the safety limits. Consequently, it was confirmed that the LEU fuel core has the proper nuclear characteristics for the safety operation. (authors)

  14. Research Results Transfer towards the Productive Sector via Research Collaboration in Four Colombian Public Universities

    Maria Eugenia Morales Rubiano

    2015-12-01

    Full Text Available This article shows the determining factors in the research results transfer towards the productive sector via research collaboration in four Colombian public universities. Thirty heads of units in the aforementioned universities were interviewed, which served to determine eleven cases of study and conduct interviews with thirty-five participants ranging from researchers, participant in formation and business people, in each case, it was found that especially in the last decade universities have turned to creating capacities for research collaboration as well as an openness in participants to create links that not only go in favor of enriching the productive sector but also in strengthening formation and research processes. It was concluded that there is a recent growing interest in the different actors in strengthening the bonds between the universities and the productive sector, though there may be some difficulties in the process of research collaboration due to the lack of an appropriate regulatory framework.

  15. Patenting of university and non-university public research organisations in Germany: evidence from patent applications for medical research results.

    Peter Tinnemann

    Full Text Available BACKGROUND: Patents are one of the most important forms of intellectual property. They grant a time-limited exclusivity on the use of an invention allowing the recuperation of research costs. The use of patents is fiercely debated for medical innovation and especially controversial for publicly funded research, where the patent holder is an institution accountable to public interest. Despite this controversy, for the situation in Germany almost no empirical information exists. The purpose of this study is to examine the amount, types and trends of patent applications for health products submitted by German public research organisations. METHODS/PRINCIPAL FINDINGS: We conducted a systematic search for patent documents using the publicly accessible database search interface of the German Patent and Trademark Office. We defined keywords and search criteria and developed search patterns for the database request. We retrieved documents with application date between 1988 and 2006 and processed the collected data stepwise to compile the most relevant documents in patent families for further analysis. We developed a rationale and present individual steps of a systematic method to request and process patent data from a publicly accessible database. We retrieved and processed 10194 patent documents. Out of these, we identified 1772 relevant patent families, applied for by 193 different universities and non-university public research organisations. 827 (47% of these patent families contained granted patents. The number of patent applications submitted by universities and university-affiliated institutions more than tripled since the introduction of legal reforms in 2002, constituting almost half of all patent applications and accounting for most of the post-reform increase. Patenting of most non-university public research organisations remained stable. CONCLUSIONS: We search, process and analyse patent applications from publicly accessible databases

  16. Japanese perspectives and research on packaging, transport and storage of spent fuel

    Saegusa, T.; Ito, C.; Yamakawa, H.; Shirai, K.

    2004-01-01

    The Japanese policy on spent fuel is reprocessing. Until, reprocessed, spent fuel shall be stored properly. This paper overviews current status of transport and storage of spent fuel with related research in Japan. The research was partly carried out under a contract of Ministry of Economy, Trade and Industry of the Japanese government

  17. EXPERIMENTAL RESEARCHES OF THERMO-PHYSICAL AND PHYSICOCHEMICAL INTERNALS OF BIO-DIESEL FUEL

    V. N. Goryachkin; A. V. Ivaschenko

    2010-01-01

    The conducted researches are related to transfer of diesel engines to biodiesel fuel. The technique and results of an experimental research of thermo-physical and physical-and-chemical properties of biodiesel fuel as well as mixes of biodiesel fuel with the petroleum one are presented.

  18. EXPERIMENTAL RESEARCHES OF THERMO-PHYSICAL AND PHYSICOCHEMICAL INTERNALS OF BIO-DIESEL FUEL

    V. N. Goryachkin

    2010-11-01

    Full Text Available The conducted researches are related to transfer of diesel engines to biodiesel fuel. The technique and results of an experimental research of thermo-physical and physical-and-chemical properties of biodiesel fuel as well as mixes of biodiesel fuel with the petroleum one are presented.

  19. The use of radiochemical techniques in fuel cell research

    Meier, H.

    1975-01-01

    The utilization of metal chelates as catalysts in fuel cell research gives rise to special problems which cannot be solved by the usual methods, but may be well clarified by isotope technical methods. The electrocatalytic efficiency of polymer iron phthalocyanine (on carbon carriers) can be proved by the plotting of potential-current density curves. Two questions, however, remain unanswered: a) What is the solubility behaviour of the catalyst, and b) is there an additional stabilizing interaction between the metal chelate catalyst and the carbon electrode. To answer the first question, the iron phthalocyanine was labelled with Fe-59 and the dissolving time of the complexed Fe ions measured; the results were compared with the potential time behaviour of the oxygen cathodes. To check the interactions between phthalocyamine catalysts and carbon carrier, Moessbauer spectroscopy was used. The evidence obtained suggest the application of isotope technical methods to an ever greater extent than up to now in fuel cell and battery research. (RB/LH) [de

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

    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

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

    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

  2. Selection of fuel design for conversion and upgradation of Pakistan Research Reactor (PARR-1)

    Arshad, M.

    1991-01-01

    The Pakistan Research Reactor (PARR-1) is being converted from the use of Highly Enriched Uranium (HEU) to Low Enriched Uranium (LEU) fuel and its power is also being upgraded. In order to select new fuel for the converted and upgraded core ten different fuel element designs were analyzed and their relative performance was compared. Results of this study were later used to select appropriate design of the new fuel for PARR-1. This paper describes the computational methodology utilized for the analysis of various fuel element designs. Criteria for selecting the new fuel element are discussed and guidelines forming the selection basis of the new fuel design are given. (author)

  3. University of Louisville Research and Energy Independence Program

    Sunkara, Mahendra K. [Univ. of Louisville, KY (United States)

    2016-02-16

    The development of domestic, environmentally friendly and sustainable sources of energy and liquid fuel is a critical need for the United States (US). Kentucky (KY) is rich in natural energy and agricultural resources that could provide sustainable energy for the state and for the nation. New technology is needed to capture, store, and distribute this sustainable energy in KY. Development of KY’s sustainable energy resources will create economic benefit for the citizens of KY and can serve as a model for other states in the US. Existing technologies for solar energy collection and storage are practical for regions with high and consistent solar intensity, such as the southwest US. Solar energy is plentiful in KY, but is less intense and less regular. As such, novel innovative technology is needed to capture, store, and distribute this energy. KY also has plentiful biomass resources that can be converted to renewable fuels. In addition, the state offers low energy rates, which are conducive for any type of manufacturing industry. A manufacturing R&D center at the University of Louisville (UofL) can help attract high-tech manufacturing industries to the city of Louisville and the state of KY.

  4. Report of researches by common utilization of facilities in Kyoto University Research Reactor Institute, first half of fiscal year 1982

    1983-01-01

    The technical report of the Kyoto University Research Reactor Institute is published any time to immediately report on the results of the functional tests of various experimental facilities, the test results for the products made for trial, radiation control, the situation of waste treatment, the data required for research and experiment such as the reports of study meetings, the conspicuous results obtained amid researches, new processes, and the discussion on other papers and reports. In this report, the title, the names of reporters and the summary of 47 researches carried out by the common utilization of the facilities in the Kyoto University Research Reactor Institute are collected. The themes of the researches are such as diffusion of impurities ion-implanted in silicon into natural oxide films, origin of igneous rocks by trace element distribution study, element distribution in black ore and its accompanying rocks and origin of black ore, reprocessing of molten salt fuel of thorium group, forerunning martensite transformation of Fe-Pt invar alloy, change of nucleic acid component to recoil tritium at cryogenic temperature, gamma irradiation effect of KC1 containing Pb 2+ , radiation effect on cadmium halide crystals and impurity metallic ions and others. (Kako, I.)

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

    Vikis, A.C.; Garisto, F.; Lemire, R.J.; Paquette, J.; Sagert, N.H.; Saluja, P.P.S.; Sunder, S.; Taylor, P.

    1988-01-01

    This publication reviews chemical research in support of the Canadian Nuclear Fuel Waste Management Program. The overall objective of this research is to develop the fundamental understanding required to demonstrate the suitability of waste immobilization media and processes, and to develop the chemical information required to predict the long-term behaviour of radionuclides in the geosphere after the waste form and the various engineered barriers containing it have failed. Key studies towards the above objective include experimental and theoretical studies of uranium dioxide oxidation/dissolution; compilation of thermodynamic databases and an experimental program to determine unavailable thermodynamic data; studies of hydrothermal alteration of minerals and radionuclide interactions with such minerals; and a study examining actinide colloid formation, as well as sorption of actinides on groundwater colloids

  6. Management of spent fuel from research and prototype power reactors and residues from post-irradiation examination of fuel

    1989-09-01

    The safe and economic management of spent fuel is important for all countries which have nuclear research or power reactors. It involves all aspects of the handling, transportation, storage, conditioning and reprocessing or final disposal of the spent fuel. In the case of spent fuel management from power reactors the shortage of available reprocessing capacity and the rising economic interest in the direct disposal of spent fuel have led to an increasing interest in the long term storage and management of spent fuel. The IAEA has played a major role in coordinating the national activities of the Member States in this area. It was against this background that the Technical Committee Meeting on ''Safe Management of Spent Fuel From Research Reactors, Prototype Power Reactors and Fuel From Commercial Power Reactors That Has Been Subjected to PIE (Post Irradiated Examination)'' (28th November - 1st December 1988) was organised. The aims of the current meeting have been to: 1. Review the state-of-the-art in the field of management of spent fuel from research and prototype power reactors, as well as the residues from post irradiation examination of commercial power reactor fuel. The emphasis was to be on the safe handling, conditioning, transportation, storage and/or disposal of the spent fuel during operation and final decommissioning of the reactors. Information was sought on design details, including shielding, criticality and radionuclide release prevention, heat removal, automation and remote control, planning and staff training; licensing and operational practices during each of the phases of spent fuel management. 2. Identify areas where additional research and development are needed. 3. Recommend areas for future international cooperation in this field. Refs, figs and tabs

  7. Three-peat NREL Intern Pushes Boundaries of Early-Stage Fuels Research on

    -Stage Fuels Research on Way to Master's Degree January 4, 2018 Woman preparing a fuel evaluation in a . Mission & Programs Awards History Leadership Community Education Center Economic Impact Environment

  8. Basic Research Needs for Clean and Efficient Combustion of 21st Century Transportation Fuels

    McIlroy, A.; McRae, G.; Sick, V.; Siebers, D. L.; Westbrook, C. K.; Smith, P. J.; Taatjes, C.; Trouve, A.; Wagner, A. F.; Rohlfing, E.; Manley, D.; Tully, F.; Hilderbrandt, R.; Green, W.; Marceau, D.; O' Neal, J.; Lyday, M.; Cebulski, F.; Garcia, T. R.; Strong, D.

    2006-11-01

    To identify basic research needs and opportunities underlying utilization of evolving transportation fuels, with a focus on new or emerging science challenges that have the potential for significant long-term impact on fuel efficiency and emissions.

  9. Reprocessing ability of high density fuels for research and test reactors

    Gay, A.; Belieres, M.

    1997-01-01

    The development of a new high density fuel is becoming a key issue for Research Reactors operators. Such a new fuel should be a Low Enrichment Uranium (LEU) fuel with a high density, to improve present in core performances. It must be compatible with the reprocessing in an industrial plant to provide a steady back-end solution. Within the framework of a work group CEA/CERCA/COGEMA on new fuel development for Research Reactors, COGEMA has performed an evaluation of the reprocessing ability of some fuel dispersants selected as good candidates. The results will allow US to classify these fuel dispersants from a reprocessing ability point of view. (author)

  10. Industry-university collaboration for research and education

    Shalaby, B.A.; Snell, V.G.; Rouben, B.

    2015-01-01

    University Network for Excellence in Nuclear Engineering also known as UNENE is a joint partnership between the nuclear industry and thirteen universities. UNENE has been legally registered as of 2002 as a not for profit organization. The establishment of this network was prompted by industry to address anticipated retirement of a large number of professionals from industry starting in early 2000 onwards and thus the loss of nuclear knowledge and experience within industry. UNENE was created to provide a sustainable supply of highly qualified personnel to industry, support nuclear research within various universities and provide a course based Master's Degree in nuclear engineering to enhance the knowledge of young professionals within the industry in the science and technology of the CANDU nuclear power system. The paper describes the current UNENE, its research objectives, key outcomes of research programs to date and its contribution to industry needs in maintaining an economic and safe power plant performance of its nuclear fleet. The paper addresses achievements within the education program and the new 4-course diploma program recently introduced to enhance core expertise of young industry professionals. Also publications and national and international collaborations in various aspects of research have significantly contributed to Canada's position in nuclear science and research worldwide. Such collaborations are also addressed. (author)

  11. G.A.T.S. and universities: implications for research.

    Packham, David E

    2003-01-01

    The likely impact of applying the General Agreement on Trade in Services (GATS) to higher education are examined. GATS aims to "open up" services to competition: no preference can be shown to national or government providers. The consequences for teaching are likely to be that private companies, with degree-awarding powers, would be eligible for the same subsidies as public providers. Appealing to the inadequate recently introduced "benchmark" statements as proof of quality, they would provide a "bare bones" service at lower cost. Public subsidies would go: education being reduced to that minimum which could be packaged in terms of verifiable "learning outcomes". The loss of "higher" aspirations, such education of critically-minded citizens of a democratic and civilized society would impoverish the university's research culture which demands honesty and openness to public scrutiny. Most university research is substantially supported by public subsidy. Under GATS discipline, commercial providers of research services could be entitled to similar public subsidies. Publicly funded fundamental research would fade, leaving university research totally dependent for funds upon the good will of industry and commerce. Present problems, such as the suppression of unwelcome results and the use of questionable results to manipulate public opinion, would considerably increase. The public would lose a prime source of trustworthy knowledge, needed in political discourse, legal disputation, consumer protection and in many other contexts.

  12. Industry-university collaboration for research and education

    Shalaby, B.A.; Snell, V.G.; Rouben, B. [Univ. Network of Excellence in Nuclear Energy (UNENE), Ontario (Canada)

    2015-09-15

    University Network for Excellence in Nuclear Engineering also known as UNENE is a joint partnership between the nuclear industry and thirteen universities. UNENE has been legally registered as of 2002 as a not for profit organization. The establishment of this network was prompted by industry to address anticipated retirement of a large number of professionals from industry starting in early 2000 onwards and thus the loss of nuclear knowledge and experience within industry. UNENE was created to provide a sustainable supply of highly qualified personnel to industry, support nuclear research within various universities and provide a course based Master's Degree in nuclear engineering to enhance the knowledge of young professionals within the industry in the science and technology of the CANDU nuclear power system. The paper describes the current UNENE, its research objectives, key outcomes of research programs to date and its contribution to industry needs in maintaining an economic and safe power plant performance of its nuclear fleet. The paper addresses achievements within the education program and the new 4-course diploma program recently introduced to enhance core expertise of young industry professionals. Also publications and national and international collaborations in various aspects of research have significantly contributed to Canada's position in nuclear science and research worldwide. Such collaborations are also addressed. (author)

  13. Industry-university collaboration for research and education

    Shalaby, B.A.; Snell, V.G.; Rouben, B., E-mail: basma.shalaby@rogers.com [University Network of Excellence in Nuclear Energy, Hamilton, ON (Canada)

    2015-07-01

    University Network for Excellence in Nuclear Engineering also known as UNENE is a joint partnership between the nuclear industry and thirteen universities. UNENE has been legally registered as of 2002 as a not for profit organization. The establishment of this network was prompted by industry to address anticipated retirement of a large number of professionals from industry starting in early 2000 onwards and thus the loss of nuclear knowledge and experience within industry. UNENE was created to provide a sustainable supply of highly qualified personnel to industry, support nuclear research within various universities and provide a course based Master's Degree in nuclear engineering to enhance the knowledge of young professionals within the industry in the science and technology of the CANDU nuclear power system. The paper describes the current UNENE, its research objectives, key outcomes of research programs to date and its contribution to industry needs in maintaining an economic and safe power plant performance of its nuclear fleet. The paper addresses achievements within the education program and the new 4-course diploma program recently introduced to enhance core expertise of young industry professionals. Also publications and national and international collaborations in various aspects of research have significantly contributed to Canada's position in nuclear science and research worldwide. Such collaborations are also addressed. (author)

  14. Conducting Research from Small University Observatories: Investigating Exoplanet Candidates

    Moreland, Kimberly D.

    2018-01-01

    Kepler has to date discovered 4,496 exoplanet candidates, but only half are confirmed, and only a handful are thought to be Earth sized and in the habitable zone. Planet verification often involves extensive follow-up observations, which are both time and resource intensive. The data set collected by Kepler is massive and will be studied for decades. University/small observatories, such as the one at Texas State University, are in a good position to assist with the exoplanet candidate verification process. By preforming extended monitoring campaigns, which are otherwise cost ineffective for larger observatories, students gain valuable research experience and contribute valuable data and results to the scientific community.

  15. Experimental study on the safety of Kyoto University Research Reactor at natural circulation cooling mode

    Zhang, Jian; Shen, Xiuzhong; Fujihara, Yasuyuki; Sano, Tadafumi; Yamamoto, Toshihiro; Nakajima, Ken

    2015-01-01

    Highlights: • The natural circulation cooling capacity of Kyoto University Research Reactor (KUR) was experimentally investigated. • The distributions of the outlet temperature of the fuel elements under natural circulation operations were measured. • The average temperature rise and the average natural circulation flow velocity in core were calculated. • The safety of KUR under all of the normal operations with natural circulation cooling mode has been analyzed. • The natural circulation flow after the reactor shutdown was confirmed. - Abstract: In this study, the natural circulation cooling capacity of Kyoto University Research Reactor (KUR) is experimentally investigated by measuring the inlet and outlet temperatures of the core under natural circulation operation at various thermal powers ranging from 10 kW to 100 kW and the shutdown state. In view of the uneven power distribution and the resultant inconsistent coolant outlet temperature in the core, eight measuring points located separately in the outlet of the fuel elements were chosen to investigate the distribution of the outlet temperature of the core. The natural circulation cooling capacity represented by the average natural circulation flow velocity in the core is calculated from the temperature difference between the outlet and inlet temperature of the core. The measured outlet temperature of the fuel elements shows a cross-sectional distribution agreeing with the distribution of the thermal output of the fuel elements in the core. Since the measured outlet temperatures decrease quickly in the flow direction in a small local region above the outlet of the core, the mixing of the hot water out of the core with the cold water around the core outlet is found to happen in the small region not more than 5 cm far from the core outlet. The natural circulation flow velocity in the core increases non-linearly with the thermal power. The safety of KUR has been analysed by conservatively estimating the

  16. Conference on energy research at historically black universities

    1980-01-01

    A conference was convened to present and discuss significant research and development in Historically Black Institutions (current and past); areas that show potential for inter-institutional collaboration and the sharing of facilities; existing capabilities to sustain funded research activities and future potential for expansion and enhancement; and appropriate arrangements for maximum interaction with industry and government agencies. Papers were presented at small group meetings in various energy research areas, and abstracts of the projects or programs are presented. The Solar Energy small group provided contributions in the areas of photovoltaics, biomass, solar thermal, and wind. Research reported on by the Fossil Fuel small group comprises efforts in the areas of fluidized bed combustion of coal, coal liquefaction, and oil shale pyrolysis. Five research programs reported on by the Conservation Research small group involve a summer workshop for high school students on energy conservation; use of industrial waste heat for a greenhouse; solar energy and energy conservation research and demonstration; energy efficiency and management; and a conservation program targeted at developing a model for educating low income families. The Environment Impact groups (2) presented contributions on physical and chemical impacts and biological monitors and impacts. The Policy Research group presented four papers on a careful analysis of the Equity issues; one on a model for examining the economic issue in looking at the interaction between energy technology and the state of the economy; and a second paper examined the institutional constraints on environmental oriented energy policy. Six additional abstracts by invited participants are presented. (MCW)

  17. The University of Stuttgart IKE/University of Arizona student research program

    Seale, R.L.

    1988-01-01

    The University of Stuttgart's Institut fuer Kernenergetik und Energiesysteme (IKE) and the University of Arizona have had a joint program in which graduate students from the IKE spend 1 yr on the University of Arizona campus. This program started in 1982 largely as the result of an initiative begun by K.H. Hoecker, then director of IKE. Since 1985, Alfred Voss has been director and the program has continued without interruption. Under the program, the Deutscher Akademisher Austauschdienst, a government agency of the Federal Republic of Germany has funded scholarships for students from IKE, which provide support for 1 yr during which they attend the University of Arizona as visiting student scholars and engage in a research project under the direction of one of our faculty, which satisfies a part of the requirements for the Ingenieur-Diplom Fachrichtung Maschinenbau. The students get credit for their research from the University of Stuttgart. The topics have a broad range and include software development, artificial intelligence, radiation transport, and energy management studies

  18. Exploring Knowledge Processes Based on Teacher Research in a School-University Research Network of a Master's Program

    Cornelissen, Frank; van Swet, Jacqueline; Beijaard, Douwe; Bergen, Theo

    2013-01-01

    School-university research networks aim at closer integration of research and practice by means of teacher research. Such practice-oriented research can benefit both schools and universities. This paper reports on a multiple-case study of five participants in a school-university research network in a Dutch master's program. The research question…

  19. Conditioning spent fuels from research nuclear reactor in ceramic dies

    Russo, D.O; Rodriguez, D.S; Mateos, P; Heredia, A; Sangilippo, M; Sterba, M

    2002-01-01

    The problem of immobilizing nuclear wastes is a complex one and is vitally important in the nuclear fuels cycle. In the case of spent elements from research reactors, the presence of large amounts of aluminum makes the procedure more complex and, therefore, onerous. There are various alternatives proposed for processing these materials. Two methods were studied in the Nuclear Materials Division for obtaining, as a final product, a vitreous block that could be place definitively in a geological repository. The processes are briefly, as follows: 1.By mechanical and chemical processes eliminating all the exterior aluminum from the fuel plates and then placing the product which we will call 'meat' (with some additional treatment and mixing with the amount needed to produce a natural uranium compound or weakened by decreasing the isotope enrichment in U-235) in a vitreous matrix. 2.Mechanically eliminate the aluminum from the exterior frame (as shown below) by shearing and cutting off the sectors containing only the Al, but leaving the rest of the aluminum, a big part of which is still present (4511.03), then doing the same procedure as in the case above: mixing with a natural uranium compound or weakening and vitrifying this mixture. In both cases, the vitrification can be carried out by fusion as well as by sintering. Given that these methods imply a big increase in volume together with a big mass of uranium and an even bigger amount of glass we decided to study an alternative. The proposed process involves synthesizing the mixtures obtained from the pre-treatment of the fuel plates (as described later) with natural isotope uranium oxide in order to obtain a block with the appropriate properties for its final disposal in a deep geological repository (CW)

  20. Main results and status of the development of LEU fuel for Russian research reactors

    Vatulin, A.; Morozov, A.; Suprun, V.; Dobrikova, I.

    2005-01-01

    VNIINM develops low enrichment uranium (LEU) fuel on base U-Mo alloys and a novel design of pin-type fuel elements. The development is carried out both for existing reactors, and for new advanced designs of reactors. The work is carried on the following main directions: - irradiate LEU U-Mo dispersion fuel (the uranium density up to 6,0 g/cm 3 ) in two Russian research reactors: MIR (RIAR, Dimitrovgrad) as pin type fuel mini-elements and in WWR-M (PINP, Gatchina) within full-scaled fuel assembly (FA) with pin type fuel elements; - finalize development of design and fabrication process of IRT type FA with pin type fuel elements; - develop methods of reducing of U-Mo fuel --Al matrix interaction under irradiation; - develop fabricating methods of fuel elements on base of monolithic U-Mo fuel. The paper generally reviews the results of calculation, design and technology investigations accomplished by now. (author)

  1. Status of research reactor fuel development in KAERI

    Kim, Chang-Kyu; Ryu, Woo-Seok; Park, Jong-Man; Lee, Don-Bae; Kim, Ki-Hwan; Kuk, Il-Hyun

    1996-01-01

    The development of uranium silicide dispersion fuel fabrication technology has been carried out in KAERI. LEU fuel bundle was prepared for irradiation test. In order to compare the performance of atomized and comminuted U 3 Si dispersed fuels, the bundle of two kinds of fuel elements were prepared. Irradiation test will be performed in the OR-hole of HANARO in the near future. U 3 Si 2 atomization technology has been improved by using ceramic crucible and nozzle. Irradiation test for atomized U 3 Si 2 plate type fuel will be carried out in cooperation with ANL by using HANARO in connection with RERTR advanced fuel development. (author)

  2. Research program and uses of the solution fueled reactor SILENE

    Barbry, F.; Ratel, R.

    1985-09-01

    Designed and operated by the Nuclear Protection and Safety Institute of the CEA, SILENE is an original small sized reactor fueled with an uranyl nitrate solution. The reactor is capable to operate in three modes: ''Pulse'' operation (high power levels up to 1000 Megawatts during several millisecond), ''Free evolution'' operation (simulation of criticality accident excursions), ''Steady state'' operation in a power range of 0.01 W to 1 kW. The core can be surrounded by appropriate shields (lead, polyethylene) to vary the leakage radiations and the gamma to neutron dose ratio. It's possible to insert in the central cavity of the annular core vessel some capsules, devices or samples to be submitted to very high radiations levels. The research activities are mainly devoted towards nuclear safety studies: the criticality accident studies, and the behavior of oxide fuels under transient conditions. Some examples of tests are presented. As to other applications of the SILENE facility, the main studies now in progress deal with: designing and calibration of Health physics intrumentation, neutron and gamma dosimetry, and, radiobiology. Once the characteristics of radiation field are qualified by calculations and experimental techniques, SILENE will be proposed as a reference source [fr

  3. Studies on fuel failure detection in Rikkyo Research Reactor

    Matsuura, T.; Hayashi, S.H.; Harasawa, S.; Tomura, K.

    1992-01-01

    Studies on fuel failure detection have been made since 1986 in Rikkyo Research Reactor. One of the methods is the monitoring of the trace concentration of fission products appearing in the air on the surface of the water tank of the reactor. The interested radionuclides here are 89 Rb and 138 Cs, which are the daughter nuclides of the FP rare gas nuclides, 89 Kr and 138 Xe, respectively and have the half lives of 15.2 min and 32.2 min respectively. They are detected on a filter paper attached on a conventional dust sampler, by sucking the air of the surface of the water for 15 ∼ 30 min during reactor operation (100 kW). In this presentation are reported the results of an attempt to increase the sensitivity of detecting these nuclides by introducing nitrogen gas bubbles into the water. The bubbling of the gas increased the sensitivity as much as several times compared with the case without bubbling. These measurements are giving us the 'background' concentration, the order of which is almost unchanged for these several years, --in 10 -6 Bq/cm 3 . The origin of these nuclides is considered to be not from the fuel but from the uranium contained as an impurity in the reactor material in the core. (author)

  4. Alternative Fuel Research in Fischer-Tropsch Synthesis

    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.

  5. State of the art: Multi-fuel reformers for automotive fuel cell applications. Problem identification and research needs

    Westerholm, R. [Stockholm Univ. (Sweden). Dept. of Analytical Chemistry; Pettersson, L.J. [Royal Inst. of Tech., Stockholm (Sweden). Dept. of Chemical Engineering and Technology

    1999-12-01

    On an assignment from the Transport and Communications Research Board (KFB) a literature study and a study trip to the USA and Great Britain have been performed. The literature study and the study trip was made during late spring and autumn 1999.The purpose of the project was to collect available information about the chemical composition of the product gas from a multi-fuel reformer for a fuel cell vehicle. It was furthermore to identify problems and research needs. The report recommends directions for future major research efforts. The results of the literature study and the study trip led to the following general conclusions: With the technology available today it does not seem feasible to develop a highly efficient and reliable multi-fuel reformer for automotive applications, i. e. for applications where all types of fuels ranging from natural gas to heavy diesel fuels can be used. The potential for developing a durable and reliable system is considerably higher if dedicated fuel reformers are used.The authors propose that petroleum-derived fuels should be designed for potential use in mobile fuel cell applications. In the present literature survey and the site visit discussions we found that there are relatively low emissions from fuel cell engines compared to internal combustion engines. However, the major research work on reformers/fuel cells have been performed during steady-state operation. Emissions during start-up, shutdown and transient operation are basically unknown and must be investigated in more detail. The conclusions and findings in this report are based on open/available information, such as discussions at site visits, reports, scientific publications and symposium proceedings.

  6. Overview of current research and development programmes for fuel in Japan

    Shiozawa, S.

    1991-01-01

    The Research and Development (R and D) programmes for HTGR fuel have been performed since 1969 by Japan Atomic Energy Research Institute (JAERI) as a leading organization in Japan. The R and D covers all fields necessary for the construction of the High Temperature Engineering Test Reactor (HTTR), which is the first HTGR in Japan. This R and D includes fuel fabrication, fuel property data, irradiation performance under normal operating conditions, safety-related research and fuel inspection technology. The R and D for the HTTR has been completed from a licensing point of view. Some R and D including future advanced fuel development continue. 2 figs, 3 tabs

  7. Building Interdisciplinary Qualitative Research Networks: Reflections on Qualitative Research Group (QRG) at the University of Manitoba

    Roger, Kerstin Stieber; Halas, Gayle

    2012-01-01

    As qualitative research methodologies continue to evolve and develop, both students and experienced researchers are showing greater interest in learning about and developing new approaches. To meet this need, faculty at the University of Manitoba created the Qualitative Research Group (QRG), a community of practice that utilizes experiential…

  8. Studies and research concerning BNFP: LWR spent fuel storage

    Shallo, F.A.

    1978-08-01

    This report describes potential spent fuel storage expansion programs using the Barnwell Nuclear Fuel Plant--Fuel Receiving and Storage Station (BNFP-FRSS) as a model. Three basic storage arrangements are evaluated with cost and schedule estimates being provided for each configuration. A general description of the existing facility is included with emphasis on the technical and equipment requirements which would be necessary to achieve increased spent fuel storage capacity at BNFP-FRSS

  9. Unique educational opportunities at the Missouri University research reactor

    Ketring, A.R.; Ross, F.K.; Spate, V.

    1997-01-01

    Since the Missouri University Research Reactor (MURR) went critical in 1966, it has been a center where students from many departments conduct their graduate research. In the past three decades, hundreds of graduate students from the MU departments of chemistry, physics, anthropology, nuclear engineering, etc., have received masters and doctoral degrees based on research using neutrons produced at MURR. More recently, the educational opportunities at MURR have been expanded to include undergraduate students and local high school students. Since 1989 MURR has participated in the National Science Foundation-funded Research Experience for Undergraduates (REU) program. As part of this program, undergraduate students from universities and colleges throughout the United States come to MURR and get hands-on research experience during the summer. Another program, started in 1994 by the Nuclear Analysis Program at MURR, allows students from a local high school to conduct a neutron activation analysis (NAA) experiment. We also conduct tours of the center, where we describe the research and educational programs at MURR to groups of elementary school children, high school science teachers, state legislators, professional organizations, and many other groups

  10. International guidelines for fire protection at nuclear installations including nuclear fuel plants, nuclear fuel stores, teaching reactors, research establishments

    The guidelines are recommended to designers, constructors, operators and insurers of nuclear fuel plants and other facilities using significant quantities of radioactive materials including research and teaching reactor installations where the reactors generally operate at less than approximately 10 MW(th). Recommendations for elementary precautions against fire risk at nuclear installations are followed by appendices on more specific topics. These cover: fire protection management and organization; precautions against loss during construction alterations and maintenance; basic fire protection for nuclear fuel plants; storage and nuclear fuel; and basic fire protection for research and training establishments. There are numerous illustrations of facilities referred to in the text. (U.K.)

  11. Recent emissions research in southwestern shrub and grassland fuels

    David R. Weise; Wayne Miller; David R. Cocker; Heejung Jung; Seyedehsan Hosseini; Marko Princevac; Robert J. Yokelson; Ian Burling; Sheryl Akagi; Shawn Urbanski; WeiMin Hao

    2015-01-01

    While it is currently challenging to use prescribed burning in chaparral and other southwestern shrub fuel types due to many constraints, any such activities require smoke management planning. Information on fuels and emissions from chaparral were limited and based on older sampling systems. The DoD SERDP program funded a project to measure fuels and smoke emissions in...

  12. International topical meeting. Research Reactor Fuel Management (RRFM) and meeting of the International Group on Reactor Research (IGORR)

    NONE

    2007-07-01

    Nuclear research and test reactors have been in operation for over 60 years, over 270 research reactors are currently operating in more than 50 countries. This meeting is dedicated to different aspects of research reactor fuels: new fuels for new reactors, the conversion to low enriched uranium fuels, spent fuel management and computational tools for core simulation. About 80 contributions are reported in this document, they are organized into 7 sessions: 1) international topics and overview on new projects and fuel, 2) new projects and upgrades, 3) fuel development, 4) optimisation and research reactor utilisation, 5) innovative methods in research reactors physics, 6) safety, operation and research reactor conversion, 7) fuel back-end management, and a poster session. Experience from Australian, Romanian, Libyan, Syrian, Vietnamese, South-African and Ghana research reactors are reported among other things. The Russian program for research reactor spent fuel management is described and the status of the American-driven program for the conversion to low enriched uranium fuels is presented. (A.C.)

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

    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.)

  14. Relation Analysis of Knowledge Management, Research, and Innovation in University Research Groups

    Heyder Paez-Logreira

    2016-12-01

    Full Text Available Knowledge is a competitive advantage for companies. Knowledge Management helps to keep this competitiveness. Universities face with challenges in research, innovation and international competitiveness. The purpose of this paper includes studying Knowledge Management Models, and Innovation Models apply to Research Groups of Universities, through an analysis of relation in inter-organizational level. Some researchers and leaders of research groups participated in a survey about knowledge management and innovation. Here we show the relationship between knowledge management, innovation and research, including processes and operations performed by universities around these. We organize the results in three dimensions: Knowledge Management perception, the relationship between Knowledge Management and Innovation, and Strategic Knowledge organization. Too, we identify a generality of good practices, challenges, and limitations on Research Groups for Knowledge Management.

  15. Research reactor usage at the Idaho National Engineering Laboratory in support of university research and education

    Woodall, D.M.; Dolan, T.J.; Stephens, A.G.

    1990-01-01

    The Idaho National Engineering Laboratory is a US Department of Energy laboratory which has a substantial history of research and development in nuclear reactor technologies. There are a number of available nuclear reactor facilities which have been incorporated into the research and training needs of university nuclear engineering programs. This paper addresses the utilization of the Advanced Reactivity Measurement Facility (ARMF) and the Coupled Fast Reactivity Measurement Facility (CFRMF) for thesis and dissertation research in the PhD program in Nuclear Science and Engineering by the University of Idaho and Idaho State University. Other reactors at the INEL are also being used by various members of the academic community for thesis and dissertation research, as well as for research to advance the state of knowledge in innovative nuclear technologies, with the EBR-II facility playing an essential role in liquid metal breeder reactor research. 3 refs

  16. Basic research in support of innovative fuels design for the Generation IV systems (F-BRIDGE project)

    Valot, Carole; Bertolus, Marjorie; Konings, Rudy; Somers, Joe; Groot, Sander de

    2010-01-01

    F-BRIDGE (Basic Research in support of Innovative Fuels Design for the GEN IV systems) is a 4-year project which started in 2008. It seeks to bridge the gap between basic research and technological applications for generation IV nuclear reactor systems. One of the challenges for the next generation of reactors is to significantly increase the efficiency in designing innovative fuels. The object of the F-BRIDGE project is to complement the empirical approach by a physically-based description of fuel and cladding materials to enable a rationalization of the design process and a better selection of promising fuel systems. Advanced modelling and separate effects experiments are carried out in order to obtain more exact physical descriptions of ceramic fuels and cladding, at relevant scales from the atomic to the macroscopic scale. Research is also focused on assessing and improving 'sphere-pac' fuel, a composite-ceramics concept which has shown promise. The project activities can be broken down into four main areas: (i) Basic research investigations using a multi-scale approach in both experimentation and modelling to enable the generation of missing basic data, the identification of relevant mechanisms and the development of appropriate models; (ii) Transfer between technological issues and basic research by bringing together within the same project materials scientists, engineers and end-users; (iii) Assessment of the drawbacks and benefits of the sphere-pac fuel application to various Generation IV systems; (iv) Education and training to promote research in the field of fuel materials, to ensure the exchange of results and ideas among the participants and to link the project with other related European or international initiatives. The project relies on the complementary expertise of 19 partners: nuclear and non nuclear research organisations, universities, a nuclear engineering company, as well as technology and project management consultancy small and medium

  17. Geoscience Education Research, Development, and Practice at Arizona State University

    Semken, S. C.; Reynolds, S. J.; Johnson, J.; Baker, D. R.; Luft, J.; Middleton, J.

    2009-12-01

    Geoscience education research and professional development thrive in an authentically trans-disciplinary environment at Arizona State University (ASU), benefiting from a long history of mutual professional respect and collaboration among STEM disciplinary researchers and STEM education researchers--many of whom hold national and international stature. Earth science education majors (pre-service teachers), geoscience-education graduate students, and practicing STEM teachers richly benefit from this interaction, which includes team teaching of methods and research courses, joint mentoring of graduate students, and collaboration on professional development projects and externally funded research. The geologically, culturally, and historically rich Southwest offers a superb setting for studies of formal and informal teaching and learning, and ASU graduates the most STEM teachers of any university in the region. Research on geoscience teaching and learning at ASU is primarily conducted by three geoscience faculty in the School of Earth and Space Exploration and three science-education faculty in the Mary Lou Fulton Institute and Graduate School of Education. Additional collaborators are based in the College of Teacher Education and Leadership, other STEM schools and departments, and the Center for Research on Education in Science, Mathematics, Engineering, and Technology (CRESMET). Funding sources include NSF, NASA, US Dept Ed, Arizona Board of Regents, and corporations such as Resolution Copper. Current areas of active research at ASU include: Visualization in geoscience learning; Place attachment and sense of place in geoscience learning; Affective domain in geoscience learning; Culturally based differences in geoscience concepts; Use of annotated concept sketches in learning, teaching, and assessment; Student interactions with textbooks in introductory courses; Strategic recruitment and retention of secondary-school Earth science teachers; Research-based professional

  18. University's role in research on superconducting power transmission

    Forsyth, E.B.

    1974-01-01

    Power transmission by superconducting cables appears to have enormous potential for the utility industry. It has still to be demonstrated that it will become a viable and economically competitive technology, however, development aimed at this goal by major research establishments has already exposed numerous research problems suitable for investigation by well qualified university departments without requiring large expenditures for equipment. What is missing in an organizational structure to relate work to the primary goals, monitor progress and influence the funding decisions of the major agencies. This does not seem difficult to set up, but continued success will require a long-term commitment from the participants

  19. Research on neutron radiography in Research Reactor Institute, Kyoto University and activities related to it

    Fujine, Shigenori; Yoneda, Kenji

    1994-01-01

    The research on neutron radiography in Research Reactor Institute, Kyoto University was begun in 1974 using the E-2 experimental hole which was designed for neutron irradiation. It was reconstructed for the excellent performance as neutron radiography facility by fixing aluminum plugs, a collimator and so on. The research activities thereafter are briefly described. In 1989, the cold neutron facility was installed in the graphite thermal neutron facility, and the experiment on cold neutron radiography became feasible. The reactor in Kyoto University is of the thermal output of 5 MW, and is put to the joint utilization by universities and research institutes in whole Japan. The experimental items carried out so far are enumerated. At present, the main subjects of research are the development of the standard for establishing image evaluation method, the analysis of gas-liquid two-phase flow, the construction of the data base for the literatures and images of neutron radiography, the application of cold neutron radiography, the development of the imaging method using fast neutrons and so on. The thermal neutron radiography and the cold neutron radiography facilities of Kyoto University research reactor are described. The research and activities at Kyoto University research reactor and the investigation of problems are reported. (K.I.) 56 refs

  20. Dissemination research: the University of Wisconsin Population Health Institute.

    Remington, Patrick L; Moberg, D Paul; Booske, Bridget C; Ceraso, Marion; Friedsam, Donna; Kindig, David A

    2009-08-01

    Despite significant accomplishments in basic, clinical, and population health research, a wide gap persists between research discoveries (ie, what we know) and actual practice (ie, what we do). The University of Wisconsin Population Health Institute (Institute) researchers study the process and outcomes of disseminating evidence-based public health programs and policies into practice. This paper briefly describes the approach and experience of the Institute's programs in population health assessment, health policy, program evaluation, and education and training. An essential component of this dissemination research program is the active engagement of the practitioners and policymakers. Each of the Institute's programs conducts data collection, analysis, education, and dialogue with practitioners that is closely tied to the planning, implementation, and evaluation of programs and policies. Our approach involves a reciprocal exchange of knowledge with non-academic partners, such that research informs practice and practice informs research. Dissemination research serves an important role along the continuum of research and is increasingly recognized as an important way to improve population health by accelerating the translation of research into practice.

  1. North Carolina State University Nuclear Structure Research at the Triangle Universities Nuclear Laboratory. Progress report

    Seagondollar, L.W.; Waltner, A.W.; Mitchell, G.E.; Tilley, D.R.; Gould, C.R.

    1975-01-01

    A summary is presented of nuclear structure research completed at the Triangle Universities Nuclear Lab for the period 9/1/74 to 8/31/75. Included are abstracts and titles for studies of electromagnetic transitions in low-medium mass nuclei, high resolution studies, accelerator induced x-ray investigations, and energy related neutron and charged particle cross section measurements. (U.S.)

  2. Research Managers at Jamaica's National University Are Strategically Deploying a Modest Research Development Fund in Support of Impactful Research

    Ivey, Paul W.; Henry, Martin

    2016-01-01

    The purpose of this paper is to highlight, using examples, how the University of Technology, Jamaica (UTech, Jamaica) is strategically using a modest internal research development fund, which is managed by the research managers in its research and innovation management office, to support impactful research projects. Critical reflection and the…

  3. Race for a Better Fuel Begins with NREL Researchers | News | NREL

    produced at NREL registers an estimated octane rating of 107. NREL's fuel is better suited for race cars by Dennis Schroeder Look! Up in the Sky! In addition to race cars, the 85% triptane could find a use Race for a Better Fuel Begins with NREL Researchers Race for a Better Fuel Begins with NREL

  4. Development of nuclear fuel materials for research reactor

    Kim, Chang Kyu; Park, H. D.; Kim, K. H.; Lee, J. T.; Ryu, W. S.; Hwang, W.; Kim, H. N.; Kim, H. I.; Kwon, H. I.; Park, C.; Lee, B. C.; Park, J. M.; Lee, C. S.; Chae, H. T.; Im, N. J.; Cho, M. S.; Im, I. C.; Nam, C.; Lee, D. B.; Goh, Y. M.; Kim, J. D.; Ahn, H. S.; Woo, Y. M.; Chang, S. J.; Cho, H. D.

    1997-09-01

    This project has aimed at the development of U 3 Si dispersion fuel for the localization of HANARO fuel and the application of atomization process to advanced RERTR fuel development. The design criteria were established through the modified computer codes. Design documents were prepared and issued. The acceptable co-extrusion cladding was achieved. The electron beam welding technology has been developed and the sealing of the end plug and cladding was accomplished without defects. The atomization fuel meats have about 200% higher elongation and about 20% higher than comminution fuel meats. The thermal compatibility test showed that atomization fuel have about 30% higher stability that the comminution fuel. The pressure drops of 18 rods fuel assembly and 36 rods fuel assembly were measured to have 213 kPa and 205 kPa respectively. Apparent wear was not found in endurance test. The irradiation fuel was designed and fabricated by using low enriched uranium metal following the developed Q/A system. The safety analysis of irradiation fuel assembly was performed through linear power calculation by using MCNP4A code and centerline temperature calculation by using DIFAIR code. The quality assurance system has been established. The quality inspection technologies were developed. By acquiring the license, low enriched uranium of 100 kg as well as depleted uranium can be used. U 3 Si 2 -Al fuel swelled less than comminution fuel irrespective of temperature and fuel fraction in a compatibility test. The atomized U-10wt.%Mo powder were found to have gamma phase of isotropic structure. Gamma structure remained with a little swelling without any structure change at 400 deg C for 100 hours. Irradiation miniplate and test rig were designed preliminary manufactured. Thermal hydraulic and linear power calculations were performed by using PLTEMP and MCNP4A computer codes respectively. The hydraulic test showed that the pressure drop met the HANARO requirement. The vibration

  5. Early detection of coolant boiling in research reactors with MTR-type fuel

    Kozma, R.; Turkcan, E.; Verhoef, J.P.

    1992-10-01

    A reactor core monitoring system having the function of early detection of boiling in the coolant channels of research reactors with MTR-type fuel is introduced. The system is based on the on-line analysis of signals of various ex-core and in-core neutron detectors. Early detection of coolant boiling cannot be accomplished by the evaluation of the DC components of these detectors in a number of practically important cases of boiling anomaly. It is shown that the noise component of the available neutron detector signals can be used for the detection of boiling in these cases. Experiments have been carried out at a boiling setup in the research reactor HOR of the Interfaculty Reactor Institute, Technical University of Delft, The Netherlands. (author). 8 refs., 11 figs

  6. Economical analysis to utilize MTR fuel elements using silicides in research reactors

    Bergallo, Juan E.; Novara, Oscar E.; Adelfang, Pablo

    2000-01-01

    According to international programs on reducing enrichment in research reactors and the necessity to maintain their operation, new fuel elements have been developed in order to meet both objectives. Thus, U-Si alloy fuel elements for research reactors are becoming of greater interest for the international markets. It became necessary to make an economic study about the convenience of introducing this type of fuel elements in the RA-3 reactor and to know the potentiality of this fuel. The economical behavior of the reactor operation has been evaluated comparing the actual U 3 O 8 nuclear fuel cycle with U 3 Si 2 nuclear fuels. Results obtained show that the main economical factor to determine the change of fuels is the cost of fabrication, and the change is advisable up to an 80% difference. The other factors related to the cost of nuclear fuel cycle are not relevant or have real minor impacts. (author)

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

    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

  8. INFORMATION SUPPORT OF INNOVATION RESEARCH PROJECTS OF THE UNIVERSITY

    Popov E. Yu.

    2015-06-01

    Full Text Available The article presents and illustrates by the example of the Novosibirsk State University a methodical approach to the development of information support of innovative research projects of the university, its historical background and their components. The basis of the external side of the approach is the system-innovative bibliometric analysis of foreign and Russian economic, scientific and technical literature. The author provides the method and the results of analysis of publication activity indicators for the sources presented in the Scientific Electronic Library (www.elibrary.ru for the period of 1991-2005 and 2006-2015 (April years. This analysis includes the specific words and word combinations included in the article title. This analysis allowed us to give a quantitative evaluation of motion vectors for universities researches and innovations. The internal side of the methodical approach includes a special system of planning, accounting and control of financial support of scientific activities of the NSU. The description of the system contains the details of historical background, patterns of interaction of participants, key documents and indicators, algorithms for cost calculation, and software. The foundation of a group of laboratories in NSU under the supervision of the world's leading scientists is considered as an important result of the proposed approach. A brief description of these laboratories is given.

  9. The Universities and JAERI joint research project. The achievements and prospects

    Ohashi, Hiroshi; Nakamura, Takashi; Yamaguchi, Sadaei

    1999-01-01

    The universities and JAERI joint research project has been carried out since 13 years ago on an equivalent basis with the universities and JAERI and co-ownership of the results. This paper consists of the history and results of research project and evaluation. The significance, characteristics, themes and problems of the project are arranged. The main results and the future of the project are explained. Two large projects such as the backend chemical project and the high-degree application of radiation project have been studied. The backend chemical project consisted of four themes; the nuclear chemical researches for TRU recycle, the solid chemical research of nuclear fuel and waste, new separation method for reprocessing and waste disposal and the fundamental chemical researches for disposal waste. The high-degree application of radiation project have eight themes; effects of ion beam on organism, slow positron generation and its application to materials, ion irradiation effects on polymer materials, nuclear spectroscopy and nuclear physics of isotope using online isotope separator, shield and behavior of accelerator radiation, materials analysis by ion beam, effects of nuclear transformation product by nuclear fusion reactor radiation damage and biofunction analysis of plant using positron release nuclide. (S.Y.)

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

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

    1989-01-01

    We analyzed the impacts of transportation of research reactor spent fuel from US and foreign reactors for the US Department of Energy's (DOE) Office of Defense Programs. Two separate shipment programs were 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). 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. The risks of transporting spent nuclear fuel and other radioactive materials by all modes have been analyzed extensively. 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

  11. Fuel Cells: Power System Option for Space Research

    Shaneeth, M.; Mohanty, Surajeet

    2012-07-01

    Fuel Cells are direct energy conversion devices and, thereby, they deliver electrical energy at very high efficiency levels. Hydrogen and Oxygen gases are electrochemically processed, producing clean electric power with water as the only by product. A typical, Fuel Cell based power system involve a Electrochemical power converter, gas storage and management systems, thermal management systems and relevant control units. While there exists different types of Fuel cells, Proton Exchange Membrane (PEM) Fuel Cells are considered as the most suitable one for portable applications. Generally, Fuel Cells are considered as the primary power system option in space missions requiring high power ( > 5kW) and long durations and also where water is a consumable, such as manned missions. This is primarily due to the advantage that fuel cell based power systems offer, in terms of specific energy. Fuel cells have the potential to attain specific energy > 500Wh/kg, specific power >500W/kg, energy density > 400Whr/L and also power density > 200 W/L. This apart, a fuel cell system operate totally independent of sun light, whereas as battery based system is fully dependent on the same. This uniqueness provides added flexibility and capabilities to the missions and modularity for power system. High power requiring missions involving reusable launch vehicles, manned missions etc are expected to be richly benefited from this. Another potential application of Fuel Cell would be interplanetary exploration. Unpredictable and dusty atmospheres of heavenly bodies limits sun light significantly and there fuel cells of different types, eg, Bio-Fuel Cells, PEMFC, DMFCs would be able to work effectively. Manned or unmanned lunar out post would require continuous power even during extra long lunar nights and high power levels are expected. Regenerative Fuel Cells, a combination of Fuel Cells and Electrolysers, are identified as strong candidate. While application of Fuel Cells in high power

  12. The importance of university research in maintaining the nuclear option

    Bruschi, H.J.; Hochreiter, L.E.

    1991-01-01

    The role of the university in maintaining and revitalizing the nuclear option should have four goals. First, it must attract highly skilled students who have an interest in math and science and help foster their interest in nuclear science and engineering. Next, it must present a state-of-the-art educational program that contains meaningful research to maintain these students. The third goal of nuclear engineering departments is to provide the nontechnical student a fair assessment of benefits and risks associated with commercial nuclear power relative to other sources of electricity. Lastly, it must effectively communicate to all students a compelling vision of nuclear power as a vital energy resource that will grow. The most difficult role for the university is to successfully convey a future for those in the nuclear science and engineering program

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

    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.)

  14. In Their Own Words: Research Misconduct from the Perspective of Researchers in Malaysian Universities.

    Olesen, Angelina P; Amin, Latifah; Mahadi, Zurina

    2017-12-16

    Published data and studies on research misconduct, which focuses on researchers in Malaysia, is still lacking, therefore, we decided that this was an area for investigation. This study provides qualitative results for the examined issues through series of in-depth interviews with 21 researchers and lecturers in various universities in Malaysia. The aims of this study were to investigate the researchers' opinions and perceptions regarding what they considered to be research misconduct, their experience with such misconduct, and the factors that contribute to research misconduct. Our findings suggest that the most common research misconducts that are currently being witnessed in Malaysian universities are plagiarism and authorship disputes, however, researchers seldom report incidents of research misconduct because it takes too much time, effort and work to report them, and some are just afraid of repercussions when they do report it. This suggests possible loopholes in the monitoring system, which may allow some researchers to bypass it and engage in misconduct. This study also highlights the structural and individual factors as the most influential factors when it comes to research misconduct besides organizational, situational and cultural factors. Finally, this study highlights the concerns of all participants regarding the 'publish or perish' pressure that they believe would lead to a hostile working environment, thus enhancing research misconduct, as researchers tend to think about their own performance rather than that of whole team or faculty. Consequently this weakens the interpersonal relationships among researchers, which may compromise the teaching and supervision of junior researchers and research students.

  15. Applied research and service activities at the University of Missouri Research Reactor Facility (MURR)

    Alger, D.M.

    1987-01-01

    The University Of Missouri operates MURR to provide an intense source of neutron and gamma radiation for research and applications by experimenters from its four campuses and by experimenters from other universities, government and industry. The 10 MW reactor, which has been operating an average of 155 hours per week for the past eight years, produces thermal neutron fluxes up to 6-7x10 14 n/cm 2 -s in the central flux trap and beamport source fluxes of up to 1.2x10 14 n/cm 2 -s. The mission of the reactor facility, to promote research, education and service, is the same as the overall mission of the university and therefore, applied research and service supported by industrial firms have been welcomed. The university recognized after a few years of reactor operation that in order to build utilization, it would be necessary to develop in-house research programs including people, equipment and activity so that potential users could more easily and quickly obtain the results needed. Nine research areas have been developed to create a broadly based program to support the level of activity needed to justify the cost of operating the facility. Applied research and service generate financial support for about one-half of the annual budget. The applied and service programs provide strong motivation for university/industry association in addition to the income generated. (author)

  16. Experience on wet storage spent fuel sipping at IEA-R1 Brazilian research reactor

    Perrotta, J.A.; Terremoto, L.A.A.; Zeituni, C.A.

    1998-01-01

    The IEA-R1 research reactor of the Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP) is a pool type reactor of B and W design, that has been operating since 1957 at a power of 2 MW. Irradiated (spent) fuels have been stored at the facility during the various years of operation. At present there are 40 spent fuel assemblies at dry storage, 79 spent fuel assemblies at wet storage and 30 fuel assemblies in the core. The oldest fuels are of United States origin, made with U-Al alloy, both of LEU and HEU MTR fuel type. Many of these fuel assemblies have corrosion pits along their lateral fuel plates. These pits originate by galvanic corrosion between the fuel plate and the stainless steel storage racks. As a consequence of the possibility of sending the irradiated old fuels back the U.S.A., sipping tests were performed with the spent fuel assemblies. The reason for this was to evaluate their 137 Cs leaking rate, if any. This work describes the procedure and methodology used to perform the sipping tests with the fuel assemblies at the storage pool, and presents the results obtained for the 137 Cs sipping water activity for each fuel assembly. A correlation is made between the corrosion pits and the activity values measured. A 137 Cs leaking rate is determined and compared to the criteria established for canning spent fuel assemblies before shipment

  17. ONLINE JOURNALISM MEETS THE UNIVERSITY: ideas for teaching and research

    Ramón Salaverría

    2011-12-01

    Full Text Available During the last decade, the teaching and research on online journalism has become widespread in journalism faculties throughout the world. Such development has brought many undergraduate and graduate courses on the issue, as well as a number of networks of researchers and specialized publications in many countries. Once this initial process is over, it is time to bring the discipline of online journalism to its maturity at the university. For this aim, the author proposes to switch the current training model, which basically shows how to manage digital tools, to another broader one that teaches journalism principles and skills in an online environment. Regarding research, he suggests not to limit it to descriptive studies, but to develop also more analytical works that could better serve both the academic community and the online media professionals.

  18. Online journalism meets the university: ideas for teaching and research

    Ramón Salaverría

    2011-12-01

    Full Text Available During the last decade, the teaching and research on online journalism has become widespread in journalism faculties throughout the world. Such development has brought many undergraduate and graduate courses on the issue, as well as a number of networks of researchers and specialized publications in many countries. Once this initial process is over, it is time to bring the discipline of online journalism to its maturity at the university. For this aim, the author proposes to switch the current training model, which basically shows how to manage digital tools, to another broader one that teaches journalism principles and skills in an online environment. Regarding research, he suggests not to limit it to descriptive studies, but to develop also more analytical works that could better serve both the academic community and the online media professionals.

  19. European Universities' Guidance on Research Integrity and Misconduct.

    Aubert Bonn, Noémie; Godecharle, Simon; Dierickx, Kris

    2017-02-01

    Research integrity is imperative to good science. Nonetheless, many countries and institutions develop their own integrity guidance, thereby risking incompatibilities with guidance of collaborating institutions. We retrieved guidance for academic integrity and misconduct of 18 universities from 10 European countries and investigated accessibility, general content, principles endorsed, and definitions of misconduct. Accessibility and content differ substantially between institutions. There are general trends of common principles of integrity and definitions of misconduct, yet differences remain. Parallel with previous research, we distinguish different approaches in integrity guidance; one emphasizes broad values of integrity, and the other details negative behaviors of misconduct. We propose that a balance between both approaches is necessary to preserve trust, meaning, and realism of guidance on research integrity.

  20. The research management profession within universities in small island states

    Christian Bonnici

    2016-11-01

    Full Text Available The past fifty years have witnessed a widespread increase in the study of small states, including island studies; and the rise of the research management profession and its associated literature. Within a small island state context, the profession cannot be taken for granted, owing to smallness and other inherent characteristics of small island states. These characteristics may potentially re-shape the profession in a unique fashion and may influence the manner in which the roles of university research managers and administrators evolve in a small island state. So far, studies investigating the profession in the context of islands and small states have been lacking. This paper aims to instigate a discussion that hopefully inspires further studies about how the research manager’s role and profession may be re-shaped within small island states.

  1. The development of a research data policy at Wageningen University & Research: best practices as a framework

    Zeeland, van Hilde; Ringersma, J.

    2017-01-01

    The current case study describes the development of a Research Data Management policy at Wageningen University & Research, the Netherlands. To develop this policy, an analysis was carried out of existing frameworks and principles on data management (such as the FAIR principles), as well as of

  2. Nuclear liability and research reactor fuel. A plant supplier's view

    Roegler, H.-J.; Hetzmann, A.

    2000-01-01

    Contracts on Research Reactors are normally entered into by the owner and - very often - later user and the supplier of such plants. They are not concluded by the fuel supplier, except fuel supplier and plant supplier are identical. Thus, the fuel supplier mostly has no direct influence into the contract negotiations and the clauses which are eventually agreed upon between the parties. So has any other subcontractor for any other system or component. Any such subsupplier can and will negotiate a subsidiary supply contract (subcontract) with the supplier of the plant. The supplier drafts the related clauses so as to pass on to the subsupplier as many risks out of his contracts as possible. The subsupplier, on the other hand, tries to protect himself, tries to limit the risks he takes over, e.g. to the worth of his subcontract maximum. A critical issue in such negotiations is those concerning the risks the supplier had to accept and the subsupplier, although he may be responsible later for the risk changing to reality; i.e. the occurrence of a loss, cannot be hold liable for in full because the subcontract limits his liability, e.g. to the subcontract value or a certain delay penalty. A typical example for this conflict are delays of the entire project caused by one subsupplier. A very specific case in this context is the so-called nuclear liability. Nuclear liability means being hold responsible for the consequences or damages originating from a nuclear event in the plant. Those consequences or damages may be suffered by third parties, which are neither the owner/operator nor the supplier and result in a liability to such party (third party liability). Several of the aspects below may be related to the nuclear liability issue: The supplier often has its registered office not in the country where the plant is; The supplier may have far bigger assets than the owner/operator. The legal system of the supplier's country may be more favourable for enforcing claims of

  3. Scientific and Ethical Reflections on Academic Corruption in Universities: On the Science Research Evaluation System in China's Universities

    Xiaochun, Wu; Dan, Jia

    2007-01-01

    A study of the science research activities in China's institutions of higher learning in recent years indicates that there is a major connection between the current instances of corruption in scientific research at colleges and universities and the evaluations system for scientific research implemented at many of the colleges and universities.…

  4. Towards Research University through Ambidexterity Practice: A Lecturer Perspective

    Retno Kusumastuti

    2017-05-01

    Full Text Available The concept of ambidexterity in organization theory refers to an organization's ability to innovate in explorative manners (Duncan, 1980. Ambidexterity can be identified into structural ambidexterity and contextual ambidexterity (Tushman, O'Reilly, 1990. In small medium enterprises, for example, innovation activities take contextual form since most owners act both as entrepreneurs and business leaders (Kusumastuti, et.al., 2015, while in established corporations innovation activities generally occur in structural form. Thus research takes academic institution as its locus, within which innovation activities are mandatory for all civitas academica (academic community. The study uses mixed method for collecting data through questionnaires and in-depth interviews. It shows that university has the capacity to provide context in institutional support and remuneration system as a means stimulate lecturers and researchers to be more innovative. The scheme also provided structure at the university and faculty level as tools to coordinate and integrate research projects. The organizational learning at the individual level reflects the pattern of contextual ambidexterity process.

  5. Water reactor fuel research at the Joint Research Centre of the Commission of the European Union

    Markgraf, J [HFR Unit, Inst. for Advanced Materials, Petten (Netherlands)

    1997-12-01

    The JRC programmes 1995-1998 are in progress within 8 JRC Institutes located within different research centres situated in five member states of the European Union. Except for the area of reactor safety and waste management, there are no JRC research programmes related to water reactor fuel directly. However, the JRC is providing support on basis of contracts and cooperations to bilateral and international R and D programmes through access to its large test facilities like the High Flux Reactor at the JRC Petten and the hot cell facilities of the Transuranium Institute at the JRC Karlsruhe. Access is available to customers from all over the world. 3 tabs.

  6. Crowdfunding To Support University Research and Public Outreach

    Jackson, Brian

    2016-10-01

    Crowdfunding involves raising (usually small) monetary contributions from a large number of people, often performed via the internet. Several universities have adopted this model to support small-dollar, high-profile projects and provide the seed money for research efforts. By contrast with traditional scientific funding, crowdfunding provides a novel way to engage the public in the scientific process and sometimes involves donor rewards in the form of acknowledgments in publications and direct involvement in the research itself.In addition to Kickstarter.com and Indiegogo.com that support a range of enterprises, there are several organizations tailored to scientific research and development, including Experiment.com and the now-defunct PetriDish.org. Private companies are also available to help universities establish their own crowd-funding platforms. At Boise State University, we recently engaged the services of ScaleFunder to launch the PonyUp platform (https://ponyup.boisestate.edu/), inaugurated in Fall 2015 with requests of support for projects ranging from the health effects of organic food during pregnancy to censuses of hummingbirds.In this presentation, I'll discuss my own crowdfunding project to support the rehabilitation of Boise State's on-campus observatory. As the first project launched on PonyUp, it was an enormous success -- we met our original donation goal of $8k just two weeks into the four-week campaign and so upped the goal to $10k, which we achieved two weeks later. In addition to the very gratifying monetary support of the broader Boise community, we received personal stories from many of our donors about their connections to Boise State and the observatory. I'll talk about our approach to social and traditional media platforms and discuss how we leveraged an unlikely cosmic syzygy to boost the campaign.

  7. Strategies for Research, Education, and Innovation, A University's Considerations

    Møller, Jacob Steen

    2004-01-01

    Engineering (BYG•DTU) at The Technical University of Denmark (DTU) to this challenge are described: The Department has been reorganised and a new strategy has been adopted. The strategy was developed in collaboration with industry partners. The Strategy focuses on a) analysis and design of safe and economic......It is argued that the building and construction sector will maintain and even increase its economic and societal importance. In spite of this the private R&D effort in the sector is relatively modest, which in turn makes public research more important. The responds of the Department of Civil...

  8. Use of university research reactors to teach control engineering

    Bernard, J.A.

    1991-01-01

    University research reactors (URRs) have provided generations of students with the opportunity to receive instruction and do hands-on work in reactor dynamics, neutron scattering, health physics, and neutron activation analysis. Given that many URRs are currently converting to programmable control systems, the opportunity now exists to provide a similar learning experience to those studying systems control engineering. That possibility is examined here with emphasis on the need for the inclusion of experiment in control engineering curricula, the type of activities that could be performed, and safety considerations

  9. Oklahoma State University proposed Advanced Technology Research Center. Environmental Assessment

    NONE

    1995-06-01

    The Department of Energy (DOE) has prepared an Environmental Assessment (EA) evaluating the construction and equipping of the proposed Advanced Technology Research Center (ATRC) at Oklahoma State University (OSU) in Stillwater, Oklahoma. Based on the analysis in the EA, the DOE has determined that the proposed action does not constitute a major federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act (NEPA) of 1969. Therefore, the preparation of an Environmental Impact Statement is not required.

  10. Radiopharmaceuticals developed at the University of Missouri research reactor

    Ketring, A.R.; Ehrhardt, G.J.; Day, D.E.

    1997-01-01

    The University of Missouri Research Reactor (MURR) has put a great deal of effort in the last two decades into development of radiotherapeutic beta emitters as nuclear medicine radiotherapeutics for malignancies. This paper describes the development of two of these drugs, 153 Sm ethylenediaminetetra-methylene phosphonic acid (EDTMP) (Quadramet trademark) and 90 Y glass microspheres (TheraSphere trademark). Samarium-153 EDTMP is a palliative used to treat the pain of metastatic bone cancer without the side effects of narcotic pain killers. Yttrium-90 glass microspheres are delivered via hepatic artery catheter to embolize the capillaries of liver tumors and deliver a large radiation dose for symptom palliation and life prolonging purposes

  11. Research activities of the nuclear graphite research group at the University of Manchester, UK

    Marsden, B.J.; Fok, A.S.L.; Marrow, J.; Mummery, P.

    2004-01-01

    In 2001 the Nuclear Safety Division (NSD) of the UK Health and Safety Executive (HSE) decided to underwrite the Nuclear Graphite Research Group (NGRG) at the University of Manchester, UK with the aim of providing a source of independent research and advice to the HSE (NSD). Since then the group has rapidly expanded to 16 members and attracted considerable funding from the nuclear power industry and the regulator for a wide range of research and consultancy work. It is now also part of the Material Performance Centre within the BNFL Universities Research Alliance. Extensive collaboration exists between the group and other nuclear research institutes, both in the UK and overseas. This paper briefly describes some of the research programmes being carried out by the NGRG at Manchester. (author)

  12. Norfolk State University Research Experience in Earth System Science

    Chaudhury, Raj

    2002-01-01

    The truly interdisciplinary nature of Earth System Science lends itself to the creation of research teams comprised of people with different scientific and technical backgrounds. In the annals of Earth System Science (ESS) education, the lack of an academic major in the discipline might be seen as a barrier to the involvement of undergraduates in the overall ESS-enterprise. This issue is further compounded at minority-serving institutions by the rarity of departments dedicated to Atmospheric Science, Oceanography or even the geosciences. At Norfolk State University, a Historically Black College, a six week, NASA-supported, summer undergraduate research program (REESS - Research Experience in Earth System Science) is creating a model that involves students with majors in diverse scientific disciplines in authentic ESS research coupled with a structured education program. The project is part of a wider effort at the University to enhance undergraduate education by identifying specific areas of student weaknesses regarding the content and process of science. A pre- and post-assessment test, which is focused on some fundamental topics in global climate change, is given to all participants as part of the evaluation of the program. Student attitudes towards the subject and the program's approach are also surveyed at the end of the research experience. In 2002, 11 undergraduates participated in REESS and were educated in the informed use of some of the vast remote sensing resources available through NASA's Earth Science Enterprise (ESE). The program ran from June 3rd through July 12, 2002. This was the final year of the project.

  13. Detection of fission products release in the research reactor 'RA' spent fuel storage pool

    Matausek, M.V.; Vukadin, Z.; Pavlovic, S.; Maksin, T.; Idakovic, Z.; Marinkovic, N.

    1997-05-01

    Spent fuel resulting from 25 years of operating the 6.5/10 MW thermal heavy water moderated and cooled research reactor RA at the VINCA Institute is presently all stored in the temporary spent fuel storage pool in the basement of the reactor building. In 1984, the reactor was shut down for refurbishment, which for a number of reasons has not yet been completed. Recent investigations show that independent of the future status of the research reactor, safe disposal of the so far irradiated fuel must be the subject of primary concern. The present status of the research reactor RA spent fuel storage pool at the VINCA Institute presents a serious safety problem. Action is therefore initiated in two directions. First, safety of the existing spent fuel storage should be improved. Second, transferring spent fuel into another, presumably dry storage space should be considered. By storing the previously irradiated fuel of the research reactor RA in a newly built storage space, sufficient free space will be provided in the existing spent fuel storage pool for the newly irradiated fuel when the reactor starts operation again. In the case that it would be decided to decommission the research reactor RA, the newly built storage space would provide safe disposal for the fuel irradiated so far

  14. The neutron beam intensity increase by in-core fuel management enhancement in multipurpose research reactors

    Martinc, R.; Vukadin, Z.; Konstantinovic, J.

    1986-01-01

    The exploitation characteristics of an existing multipurpose research reactor can be increased not only by great reconstruction, but also, to the considerable extent, by the in-core fuel management sophistication. The optimisation of the in-core fuel management procedure in such reactors is governed (among others) by the identified reactor utilisation goals, i.e. by weighting factors dedicated to different utilisation goals, which are often (regarding the in-core fuel management procedure) highly controversial. In this work the best solution for in-core fuel management is sought, with the highest weighting factor dedicated to the neutron beam usage, rather than sample irradiation in the reactor core. The term in-core fuel management includes: the core configuration, the locations of the fresh fuel inflow zone and spent fuel excite zone, and the fuel transfers between these two zones (author)

  15. Code structure for U-Mo fuel performance analysis in high performance research reactor

    Jeong, Gwan Yoon; Cho, Tae Won; Lee, Chul Min; Sohn, Dong Seong [Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of); Lee, Kyu Hong; Park, Jong Man [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    A performance analysis modeling applicable to research reactor fuel is being developed with available models describing fuel performance phenomena observed from in-pile tests. We established the calculation algorithm and scheme to best predict fuel performance using radio-thermo-mechanically coupled system to consider fuel swelling, interaction layer growth, pore formation in the fuel meat, and creep fuel deformation and mass relocation, etc. In this paper, we present a general structure of the performance analysis code for typical research reactor fuel and advanced features such as a model to predict fuel failure induced by combination of breakaway swelling and pore growth in the fuel meat. Thermo-mechanical code dedicated to the modeling of U-Mo dispersion fuel plates is being under development in Korea to satisfy a demand for advanced performance analysis and safe assessment of the plates. The major physical phenomena during irradiation are considered in the code such that interaction layer formation by fuel-matrix interdiffusion, fission induced swelling of fuel particle, mass relocation by fission induced stress, and pore formation at the interface between the reaction product and Al matrix.

  16. Assessment of fuel damage of pool type research reactor in the case of fuel plates blockage

    Jalil, Jafari; Samad, Khakshournia [AEOI, Karegar Ave. School of R and D of Nuclear Reactors and Accelerators, Teheran (Iran, Islamic Republic of); D' Auria, F. [Pisa Univ., DIMNP (Italy)

    2007-07-01

    Tehran Research Reactor (TRR) is a pool type 5 MW research reactor. It is assumed that external objects or debris that may fall down to reactor core cause obstruction of coolant flow through one of the fuel assemblies. Thermal hydraulic analysis of this event, using the RELAP5 system code has been studied. The reported transient is related to the partial and total obstruction of a single Fuel Element (FE) cooling channel of 27 FE equilibrium core of TRR. Such event constitutes a severe accident for this type of reactor since it may lead to local dryout and eventually to loss of the FE integrity. Two scenarios are analysed to emphasize the severity of the accident. The first one is a partial blockage of an average FE considering four different obstruction levels: 25%, 50%, 75% and 97% of nominal flow area. The second one is an extreme scenario consisting of total blockage of the same FE. This study constitutes the first step of a larger work which consists of performing a 3-dimensional simulation using the Best Estimate coupled code technique. However, as a first approach the instantaneous reactor power is derived through the point kinetic calculation included in the RELAP5 code. Main results obtained from the RELAP5 calculations are as following. First, in the case of flow blockage under 97% of the nominal flow area of an average FE, only an increase of the coolant and clad temperatures is observed without any consequences for the integrity of the FE. The mass flow rate remains sufficient to cool the clad safely. Secondly, in the case of total obstruction of the nominal flow area, it is seen that transient turns out to be a severe accident due to the dryout conditions are reached shortly and melting of the cladding occurs. Thirdly, the use of the point kinetic approach leads to conservative results. A best estimate simulation of such kind of transients requires the use of 3-dimensional kinetic calculations, which could be done using the current Coupled Codes

  17. Proceedings of the international meeting on development, fabrication and application of reduced enrichment fuels for research and test reactors

    1983-08-01

    Separate abstracts were prepared for each of the papers presented in the following areas: (1) Reduced Enrichment Fuels for Research and Test Reactors (RERTR) Program Status; (2) Fuel Development; (3) Fuel Demonstrations; (4) General Topics; and (5) Specific Reactor Applications

  18. Universities innovation and technology commercialization challenges and solutions from the perspectives of Malaysian research universities

    Rasli, Amran; Kowang, Tan Owee

    2017-11-01

    The roles of universities in the context of a nation's shift towards sustainable competitive advantage have changed drastically recently. Universities are now expected to contribute to the creation of new knowledge-based industries, i.e. to support knowledge-based economic growth through the creation of industrially-relevant knowledge/innovation and their commercialization, and to attract global MNCs in new emerging industries; and foster entrepreneurial mindset to support the future knowledge economy where stable job opportunities are no longer guaranteed. As such, there is a need to inculcate the spirit of enterprise as compared to the past where high economic growth has provided graduates with good career prospects as salaried employees, particularly in MNC subsidiaries and the government. The shift requires a bigger role in supporting innovation and commercialization, i.e. to venture beyond its traditional function of teaching, research and publication by incorporating a technology commercialization role which will inevitably help the institution to improve its global ranking. However, there are many national and operational obstacles that impede the progression of research and development to commercialization and entrepreneurship. The main challenges include: (I) lack of connectivity between the industry and academia; (2) myopic perception of the market; (3) inability to evaluate viability from ideas to innovations and beyond; (4) lack of support for investment in new technologies, and (5) lack of positive culture among academic researchers. To overcome the aforementioned obstacles, priority in developing a complete commercialization ecosystem has become a national agenda for most emerging economies.

  19. Progress in researches on MOX fuel pellet producing technology in China

    Hu Xiaodan

    2010-01-01

    Being the key section of nuclear-fuel cycle, the producing technology of MOX(UO 2 -PuO 2 ) fuel had driven to maturity in France, England, Russia, Belgium, etc. MOX fuel had been applied in FBR and LWR successfully in those countries. With the rapidly developing of nuclear-generated power, the MOX fuel for FBR and LWR was active demanded in China. However, the producing technology of MOX fuel developed slowly. During the period of 'the seventh five year's project', MOX fuel pellet was produced by mechanically mixed method and oxalate deposited method, respectively. Parts of cool performance of MOX fuel pellet produced by oxalate deposited method reached the qualification of fuel for FBR. During the period of 'the ninth five year's project' and 'the tenth five year's project', the technical route of producing MOX fuel was determined, and the test line of producing MOX fuel was built preliminarily. In the same time, the producing technology and analyzing technology of MOX fuel pellet by mechanically mixed was studied roundly, and the representative analogue pellet(UO 2 -CeO 2 ) was produced. That settled the supporting technology for the commercial process and research of MOX fuel rod and MOX fuel module. (authors)

  20. Qualification of high-density fuel manufacturing for research reactors at CNEA

    Adelfang, P.; Alvarez, L.; Boero, N.; Calabrese, R.; De La Fuente, M.; Echenique, P.; Markiewicz, M.; Pasqualini, E.; Ruggirello, G.; Taboada, H. [CNEA, Buenos Aires (Argentina)

    2001-07-01

    CNEA, the National Atomic Energy Commission of Argentina, is at the present a qualified supplier of uranium oxide fuel for research reactors. A new objective in this field is to develop and qualify the manufacturing of LEU high-density fuel for this type of reactors. According with the international trend Silicide fuel and U-xMo fuel are included in our program as the most suitable options. The facilities to complete the qualification of high-density MTR fuels, like the manufacturing plant installations, the reactor, the pool side fuel examination station and the hot cells are fully operational and equipped to perform all the activities required within the program. The programs for both type of fuels include similar activities: development and set up of the fuel material manufacturing technology, set up of fuel plate manufacturing, fabrication and irradiation of miniplates, fabrication and irradiation of full scale fuel elements, post-irradiation examination and feedback for manufacturing improvements. For silicide fuels most of these steps have already been completed. For U-xMo fuel the activities also include the development of alternative ways to obtain U-xMo powder, feasibility studies for large-scale manufacturing and the economical assessment. Set up of U-xMo fuel plate manufacturing is also well advanced and the fabrication of the first full scale prototype is foreseen during this year. (author)