WorldWideScience

Sample records for research facility technical

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

    International Nuclear Information System (INIS)

    Wootton, A.J.

    1995-08-01

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

  2. Paul Scherrer Institute Scientific and Technical Report 2000. Volume VI: Large Research Facilities

    International Nuclear Information System (INIS)

    Foroughi, Fereydoun; Bercher, Renate; Buechli, Carmen; Zumkeller, Lotty

    2001-01-01

    The PSI Department Large Research Facilities (GFA) joins the efforts to provide an excellent research environment to Swiss and foreign research groups on the experimental facilities driven by our high intensity proton accelerator complex. Its divisions care for the running, maintenance and enhancement of the accelerator complex, the primary proton beamlines, the targets and the secondary beams as well as the neutron spallation source SINQ. The division for technical support and coordination provides for technical support to the research facility complementary to the basic logistic available from the department for logistics and marketing. Besides running the facilities, the staff of the department is also involved in theoretical and experimental research projects. Some of them address basic scientific questions mainly concerning the properties of micro- or nanostructured materials: experiments as well as large scale computer simulations of molecular dynamics were performed to investigate nonclassical materials properties. Others are related to improvements or extensions of the capabilities of our facilities. We also report on intriguing results from applications of the neutron capture radiography, the prompt gamma activation method and the isotope production facility at SINQ

  3. Paul Scherrer Institute Scientific and Technical Report 2000. Volume VI: Large Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Foroughi, Fereydoun; Bercher, Renate; Buechli, Carmen; Zumkeller, Lotty [eds.

    2001-07-01

    The PSI Department Large Research Facilities (GFA) joins the efforts to provide an excellent research environment to Swiss and foreign research groups on the experimental facilities driven by our high intensity proton accelerator complex. Its divisions care for the running, maintenance and enhancement of the accelerator complex, the primary proton beamlines, the targets and the secondary beams as well as the neutron spallation source SINQ. The division for technical support and coordination provides for technical support to the research facility complementary to the basic logistic available from the department for logistics and marketing. Besides running the facilities, the staff of the department is also involved in theoretical and experimental research projects. Some of them address basic scientific questions mainly concerning the properties of micro- or nanostructured materials: experiments as well as large scale computer simulations of molecular dynamics were performed to investigate nonclassical materials properties. Others are related to improvements or extensions of the capabilities of our facilities. We also report on intriguing results from applications of the neutron capture radiography, the prompt gamma activation method and the isotope production facility at SINQ.

  4. Technical safety requirements for the Annular Core Research Reactor Facility (ACRRF)

    International Nuclear Information System (INIS)

    Boldt, K.R.; Morris, F.M.; Talley, D.G.; McCrory, F.M.

    1998-01-01

    The Technical Safety Requirements (TSR) document is prepared and issued in compliance with DOE Order 5480.22, Technical Safety Requirements. The bases for the TSR are established in the ACRRF Safety Analysis Report issued in compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports. The TSR identifies the operational conditions, boundaries, and administrative controls for the safe operation of the facility

  5. Proposal on application of Russian technical facilities for International Mars Research Program for 2009 2015

    Science.gov (United States)

    Polishchuk, Georgy; Pichkhadze, Konstantin; Vorontsov, Victor; Pavel, Kazmerchuk

    2006-07-01

    Recently International Mars Research Program is widely discussed. Well-known initiative of President of the USA, recent progress of American and European scientists and engineers in implementation of “Mars Odyssey” and “Mars-Express” projects and Russian proposals on cooperation and participation in “Phobos Sample Return” mission declare every intention to join efforts in the ambitious Martian Program realization. The final goal of the program for nearly 15 20 years is landing of a man on the Martian surface. Before this event happens another critical stage will be Martian soil sample return. Within the next 10 years, apparently, a major task will be scale research by means of various types of technical facilities. A crucial issue for this research will be creation of research station network which would allow collecting information about planetary conditions at far-remote points. By this time within the frame of “Phobos Sample Return Program” to be launched in 2009 it is planned to deliver some meteorological mini-landers developed by the Russian and Finnish specialists on the Martian surface. From this point view it is also interesting to use balloons capable to cover considerable distance. Such proposals have been made by Russian side for “Scout” mission. European “Aurora” program also anticipates application of wide range of technical means to explore the Martian atmosphere and surface including inflatable devices. Thus, for the International Mars Exploration Program, it seems to be very prospective to use apart from launch vehicles, upper stages etc. such technical means as mini-stations, Mars rovers, penetrators, balloons, etc.

  6. Paul Scherrer Institute Scientific and Technical Report 1999. Volume VI: Large Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Foroughi, Fereydoun; Bercher, Renate; Buechli, Carmen; Meyer, Rosa [eds.

    2000-07-01

    The department GFA (Grossforschungsanlagen, Large Research Facilities) has been established in October 1998. Its main duty is operation, maintenance and development of the PSI accelerators, the spallation neutron source and the beam transport systems for pions and muons. A large effort of this group concerns the planning and co-ordination of new projects like e.g. the assembly of the synchrotron light source (SLS), design studies of a new proton therapy facility, the ultracold neutron source and a new intensive secondary beam line for low energy muons. A large fraction of this report is devoted to research especially in the field of materials Science. The studies include large scale molecular dynamics computer simulations on the elastic and plastic behavior of nanostructured metals, complemented by experimental mechanical testing using micro-indentation and miniaturized tensile testing, as well as microstructural characterisation and strain field mapping of metallic coatings and thin ceramic layers, the latter done with synchrotron radiation.

  7. Paul Scherrer Institute Scientific and Technical Report 1999. Volume VI: Large Research Facilities

    International Nuclear Information System (INIS)

    Foroughi, Fereydoun; Bercher, Renate; Buechli, Carmen; Meyer, Rosa

    2000-01-01

    The department GFA (Grossforschungsanlagen, Large Research Facilities) has been established in October 1998. Its main duty is operation, maintenance and development of the PSI accelerators, the spallation neutron source and the beam transport systems for pions and muons. A large effort of this group concerns the planning and co-ordination of new projects like e.g. the assembly of the synchrotron light source (SLS), design studies of a new proton therapy facility, the ultracold neutron source and a new intensive secondary beam line for low energy muons. A large fraction of this report is devoted to research especially in the field of materials Science. The studies include large scale molecular dynamics computer simulations on the elastic and plastic behavior of nanostructured metals, complemented by experimental mechanical testing using micro-indentation and miniaturized tensile testing, as well as microstructural characterisation and strain field mapping of metallic coatings and thin ceramic layers, the latter done with synchrotron radiation

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

    Energy Technology Data Exchange (ETDEWEB)

    Wootton, A.J.

    1994-07-01

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

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

    International Nuclear Information System (INIS)

    Wootton, A.J.

    1994-07-01

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

  10. Paul Scherrer Institute Scientific and Technical Report 2001. Volume VI: Large Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Bercher, R.; Buechli, C.; Zumkeller, L. (eds.)

    2002-03-01

    While the main effort in the past ten years was directed towards increasing the beam current from 100 to 2000 {mu}A and installation of additional user facilities like SINQ to satisfy new needs, we are now concentrating on stable operation at these high beam intensities. Unfortunately, 'stable operation' is not clearly defined. A few years ago, the accelerator physicists considered 80% beam on time excellent but the users complained about poor performance. Today we achieve a yearly mean beam on time of almost 90% at 1.7 mA and we have achieved 95% to 98% of the scheduled beam time for periods of weeks. These numbers seem to be satisfactory for the users. Despite this achievement, we try hard to further reduce the number of serious and long breakdowns, which are the main cause of the reduced yearly mean availability. Furthermore, breakdowns that necessitate long repair times are extremely detrimental for many experiments, which have only been allocated a few days of beam time. As a result of our discussions, we launched a number of activities, which include design and construction of improved power supplies, intensifying preventive maintenance, procuring vital spare parts, and reducing repair times through careful preparation. In addition, we were given permission to strengthen the accelerator staff with highly qualified physicists in order to study and solve several pending problems. We are aware that the planned measures will by no means be fast and will require considerable financial and personnel support. A long-standing issue concerning the improvement of the machine performance is the replacement of the aluminum cavities in the main ring accelerator by new high power copper cavities. The studies and tests on a model cavity are finished and we have ordered a prototype cavity, which will arrive in fall 2002 and be installed in the ring after a rigorous test phase in 2004. A list of scientific publications in 2000 is also provided.

  11. Paul Scherrer Institute Scientific and Technical Report 2001. Volume VI: Large Research Facilities

    International Nuclear Information System (INIS)

    Bercher, R.; Buechli, C.; Zumkeller, L.

    2002-03-01

    While the main effort in the past ten years was directed towards increasing the beam current from 100 to 2000 μA and installation of additional user facilities like SINQ to satisfy new needs, we are now concentrating on stable operation at these high beam intensities. Unfortunately, 'stable operation' is not clearly defined. A few years ago, the accelerator physicists considered 80% beam on time excellent but the users complained about poor performance. Today we achieve a yearly mean beam on time of almost 90% at 1.7 mA and we have achieved 95% to 98% of the scheduled beam time for periods of weeks. These numbers seem to be satisfactory for the users. Despite this achievement, we try hard to further reduce the number of serious and long breakdowns, which are the main cause of the reduced yearly mean availability. Furthermore, breakdowns that necessitate long repair times are extremely detrimental for many experiments, which have only been allocated a few days of beam time. As a result of our discussions, we launched a number of activities, which include design and construction of improved power supplies, intensifying preventive maintenance, procuring vital spare parts, and reducing repair times through careful preparation. In addition, we were given permission to strengthen the accelerator staff with highly qualified physicists in order to study and solve several pending problems. We are aware that the planned measures will by no means be fast and will require considerable financial and personnel support. A long-standing issue concerning the improvement of the machine performance is the replacement of the aluminum cavities in the main ring accelerator by new high power copper cavities. The studies and tests on a model cavity are finished and we have ordered a prototype cavity, which will arrive in fall 2002 and be installed in the ring after a rigorous test phase in 2004. A list of scientific publications in 2000 is also provided

  12. Research Facilities | Wind | NREL

    Science.gov (United States)

    Research Facilities Research Facilities NREL's state-of-the-art wind research facilities at the Research Facilities Photo of five men in hard hards observing the end of a turbine blade while it's being tested. Structural Research Facilities A photo of two people silhouetted against a computer simulation of

  13. Basic Research Firing Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Basic Research Firing Facility is an indoor ballistic test facility that has recently transitioned from a customer-based facility to a dedicated basic research...

  14. Research in Technical Colleges

    Science.gov (United States)

    MacLennan, A.

    2008-01-01

    Purpose: The purpose of this paper is to list and demonstrate areas in which research needs to be carried out, or questions answered, in order to raise the quality of technical education. Design/methodology/approach: The area of technical education expanded very rapidly in the late 1950s, and there was little comprehensive knowledge regarding the…

  15. Guide to research facilities

    Energy Technology Data Exchange (ETDEWEB)

    1993-06-01

    This Guide provides information on facilities at US Department of Energy (DOE) and other government laboratories that focus on research and development of energy efficiency and renewable energy technologies. These laboratories have opened these facilities to outside users within the scientific community to encourage cooperation between the laboratories and the private sector. The Guide features two types of facilities: designated user facilities and other research facilities. Designated user facilities are one-of-a-kind DOE facilities that are staffed by personnel with unparalleled expertise and that contain sophisticated equipment. Other research facilities are facilities at DOE and other government laboratories that provide sophisticated equipment, testing areas, or processes that may not be available at private facilities. Each facility listing includes the name and phone number of someone you can call for more information.

  16. Environmental Toxicology Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Fully-equipped facilities for environmental toxicology researchThe Environmental Toxicology Research Facility (ETRF) located in Vicksburg, MS provides over 8,200 ft...

  17. High Combustion Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — At NETL's High-Pressure Combustion Research Facility in Morgantown, WV, researchers can investigate new high-pressure, high-temperature hydrogen turbine combustion...

  18. Geodynamics Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This GSL facility has evolved over the last three decades to support survivability and protective structures research. Experimental devices include three gas-driven...

  19. Magnetics Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Magnetics Research Facility houses three Helmholtz coils that generate magnetic fields in three perpendicular directions to balance the earth's magnetic field....

  20. Transonic Experimental Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Transonic Experimental Research Facility evaluates aerodynamics and fluid dynamics of projectiles, smart munitions systems, and sub-munitions dispensing systems;...

  1. Flexible Electronics Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Flexible Electronics Research Facility designs, synthesizes, tests, and fabricates materials and devices compatible with flexible substrates for Army information...

  2. High Exposure Facility Technical Description

    Energy Technology Data Exchange (ETDEWEB)

    Carter, Gregory L.; Stithem, Arthur R.; Murphy, Mark K.; Smith, Alex K.

    2008-02-12

    The High Exposure Facility is a collimated high-level gamma irradiator that is located in the basement of the 318 building. It was custom developed by PNNL back in 1982 to meet the needs for high range radiological instrument calibrations and dosimeter irradiations. At the time no commercially available product existed that could create exposure rates up to 20,000 R/h. This document is intended to pass on the design criteria that was employed to create this unique facility, while maintaining compliance with ANSI N543-1974, "General Safety Standard for Installations Using Non-Medical X-Ray and Sealed Gamma-Ray Sources, Energies up to 10 MeV."

  3. Field Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Field Research Facility (FRF) located in Duck, N.C. was established in 1977 to support the U.S. Army Corps of Engineers' coastal engineering mission. The FRF is...

  4. Concrete Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This is a 20,000-sq ft laboratory that supports research on all aspects of concrete and materials technology. The staff of this facility offer wide-ranging expertise...

  5. Frost Effects Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Full-scale study in controlled conditionsThe Frost Effects Research Facility (FERF) is the largest refrigerated warehouse in the United States that can be used for a...

  6. Combustion Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — For more than 30 years The Combustion Research Facility (CRF) has served as a national and international leader in combustion science and technology. The need for a...

  7. Geophysical Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Geophysical Research Facility (GRF) is a 60 ft long × 22 ft wide × 7 ft deep concrete basin at CRREL for fresh or saltwater investigations and can be temperature...

  8. Radiological Research Accelerator Facility

    International Nuclear Information System (INIS)

    Goldhagen, P.; Marino, S.A.; Randers-Pehrson, G.; Hall, E.J.

    1986-01-01

    The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which can be used to generate a variety of well-characterized radiation beams for research in radiobiology and radiological physics. It is part of the Radiological Research Laboratory (RRL), and its operation is supported as a National Facility by the US Department of Energy. RARAF is available to all potential users on an equal basis, with priorities based on the recommendations of a Scientific Advisory Committee. Facilities and services are provided to users, but the research projects themselves must be supported separately. This chapter presents a brief description of current experiments being carried out at RARAF and of the operation of the Facility from January through June, 1986. Operation of the Facility for all of 1985 was described in the 1985 Progress Report for RARAF. The experiments described here were supported by various Grants and Contracts from NIH and DOE and by the Statens Stralskyddsinstitut of Sweden

  9. Annual report of Department of Research Reactor and Tandem Accelerator, JFY2012. Operation, utilization and technical development of JRR-3, JRR-4, NSRR, Tandem Accelerator and RI Production Facility

    International Nuclear Information System (INIS)

    Murayama, Yoji; Ishii, Tetsuro; Nakamura, Kiyoshi; Uno, Yuki; Ishikuro, Yasuhiro; Kawashima, Kazuhito; Ishizaki, Nobuhiro; Matsumura, Taichi; Nagahori, Kazuhisa; Odauchi, Shouji; Maruo, Takeshi

    2014-03-01

    The Department of Research Reactor and Tandem Accelerator is in charge of the operation, utilization and technical development of JRR-3(Japan Research Reactor No.3), JRR-4(Japan Research Reactor No.4), NSRR(Nuclear Safety Research Reactor), Tandem Accelerator and RI Production Facility. This annual report describes a summary of activities of services and technical developments carried out in the period between April 1, 2012 and March 31, 2013. The activities were categorized into five service/development fields: (1) Operation and maintenance of research reactors and tandem accelerator, (2) Utilization of research reactors and tandem accelerator, (3) Upgrading of utilization techniques of research reactors and tandem accelerator, (4) Safety administration for department of research reactor and tandem accelerator, (5) International cooperation. Also contained are lists of publications, meetings, granted permissions on laws and regulations concerning atomic energy, number of staff members dispatched to Fukushima for the technical assistance, outcomes in service and technical developments and so on. (author)

  10. Technical Cybersecurity Controls for Nuclear Facilities

    International Nuclear Information System (INIS)

    Oh, Jinseok; Ryou, Jaecheol; Kim, Youngmi; Jeong, Choonghei

    2014-01-01

    To strengthen cybersecurity for nuclear facilities, many countries take a regulatory approach. For example, US Government issued several regulations . Title 10, of the Code of Federal Regulations, Section 73.54, 'Protection of Digital Computer and Communication Systems and Networks (10 CFR 73.54) for cybersecurity requirements and Regulatory Guide 5.71 (RG. 5.71) for cybersecurity guidance and so on. In the case of Korea, Korean Government issued '8.22 Cybersecurity of I and C systems (KINS/RG-NO8.22). In particular, Reg. 5.71 provides a list of security controls to address the potential cyber risks to a nuclear facilities. Implementing and adopting security controls, we can improve the level of cybersecurity for nuclear facilities. RG 5.71 follows the recommendation of NIST SP 800-53. NIST standard provides security controls for IT systems. And NRC staff tailored the controls in NIST standards to unique environments of nuclear facilities. In this paper, we are going to analysis and compare NRC RG 5.71 and NIST SP800-53, in particular, for technical security controls. If RG 5.71 omits the specific security control that is included in SP800-53, we would review that omitting is adequate or not. If RG 5.71 includes the specific security control that is not included in SP800-53, we would also review the rationale. And we are going to some security controls to strengthen cybersecurity of nuclear facilities. In this paper, we compared and analyzed of two regulation in technical security controls. RG 5.71 that is based on NIST standard provides well-understood security controls for nuclear facility. But some omitting from NIST standard can threaten security state of nuclear facility

  11. Technical Cybersecurity Controls for Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Jinseok; Ryou, Jaecheol [Chungnam National Univ., Daejeon (Korea, Republic of); Kim, Youngmi; Jeong, Choonghei [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2014-05-15

    To strengthen cybersecurity for nuclear facilities, many countries take a regulatory approach. For example, US Government issued several regulations . Title 10, of the Code of Federal Regulations, Section 73.54, 'Protection of Digital Computer and Communication Systems and Networks (10 CFR 73.54) for cybersecurity requirements and Regulatory Guide 5.71 (RG. 5.71) for cybersecurity guidance and so on. In the case of Korea, Korean Government issued '8.22 Cybersecurity of I and C systems (KINS/RG-NO8.22). In particular, Reg. 5.71 provides a list of security controls to address the potential cyber risks to a nuclear facilities. Implementing and adopting security controls, we can improve the level of cybersecurity for nuclear facilities. RG 5.71 follows the recommendation of NIST SP 800-53. NIST standard provides security controls for IT systems. And NRC staff tailored the controls in NIST standards to unique environments of nuclear facilities. In this paper, we are going to analysis and compare NRC RG 5.71 and NIST SP800-53, in particular, for technical security controls. If RG 5.71 omits the specific security control that is included in SP800-53, we would review that omitting is adequate or not. If RG 5.71 includes the specific security control that is not included in SP800-53, we would also review the rationale. And we are going to some security controls to strengthen cybersecurity of nuclear facilities. In this paper, we compared and analyzed of two regulation in technical security controls. RG 5.71 that is based on NIST standard provides well-understood security controls for nuclear facility. But some omitting from NIST standard can threaten security state of nuclear facility.

  12. Annual report of Department of Research Reactor and Tandem Accelerator, JFY2014. Operation, Utilization and Technical Development of JRR-3, JRR-4, NSRR, Tandem Accelerator and RI Production Facility

    International Nuclear Information System (INIS)

    Osa, Akihiko; Imahashi, Masaki; Hirane, Nobuhiko; Motome, Yuiko; Tayama, Hidekazu; Tamura, Itaru; Harada, Yuko; Sakata, Mami; Kadokura, Masakazu; Takita, Chiharu

    2017-02-01

    The Department of Research Reactor and Tandem Accelerator is in charge of the operation, utilization and technical development of JRR-3 (Japan Research Reactor No.3), JRR-4 (Japan Research Reactor No.4), NSRR (Nuclear Safety Research Reactor), Tandem Accelerator and RI Production Facility. This annual report describes the activities of our department in fiscal year of 2014. We carried out the operation and maintenance, utilization, upgrading of utilization techniques, safety administration, and international cooperation. Also contained are lists of publications, meetings, granted permissions on laws and regulations concerning atomic energy, outcomes in service and technical developments and so on. (author)

  13. Annual report of Department of Research Reactor and Tandem Accelerator, JFY2013. Operation, Utilization and Technical Development of JRR-3, JRR-4, NSRR, Tandem Accelerator and RI Production Facility

    International Nuclear Information System (INIS)

    Kashima, Yoichi; Murayama, Yoji; Nakamura, Kiyoshi; Uno, Yuki; Hirane, Nobuhiko; Ohuchi, Hitoshi; Ishizaki, Nobuhiro; Matsumura, Taichi; Nagahori, Kazuhisa; Harada, Yuko; Kadokura, Masakazu; Machi, Sumire; Takita, Chiharu

    2015-02-01

    The Department of Research Reactor and Tandem Accelerator is in charge of the operation, utilization and technical development of JRR-3(Japan Research Reactor No.3), JRR-4(Japan Research Reactor No.4), NSRR(Nuclear Safety Research Reactor), Tandem Accelerator and RI Production Facility. This annual report describes the activities of our department in fiscal year of 2013. We carried out the operation and maintenance, utilization, upgrading of utilization techniques, safety administration and international cooperation. Also contained are lists of publications, meetings, granted permissions on laws and regulations concerning atomic energy, outcomes in service and technical developments and so on. (author)

  14. Centrifuge facilities at Technical University of Denmark

    DEFF Research Database (Denmark)

    Leth, Caspar Thrane; Krogsbøll, Anette Susanne; Hededal, Ole

    2008-01-01

    The geotechnical group at the Danish Technical University (DTU) operates a geotechnical beam centrifuge. The centrifuge was build in 1976 and has been upgraded through the years, latest with onboard data and control systems. The centrifuge concept involves an increased gravity field in which...... the physical model is placed and tested. The capabilities of the centrifuge at DTU makes it possible to obtain a scale factor of 75-85 in the tests which equals a soil volume in prototype scale of ø40m and a depth of 36 m. The centrifuge facilities at DTU have through the years been used for testing various...... geotechnical issues, such as suction anchors, tension piles in clay, active earth pressures on sheet piles and group effects for lateral loaded piles. The paper describes physical modelling in general, the centrifuge, present setups and shows samples of obtained results....

  15. Technical Facilities Management, Loan Pool, and Calibration

    Science.gov (United States)

    Smith, Jacob

    2011-01-01

    My work at JPL for the SURF program began on June 11, 2012 with the Technical Facilities Management group (TFM). As well as TFM, I worked with Loan Pool and Metrology to help them out with various tasks. Unlike a lot of other interns, I did not have a specific project rather many different tasks to be completed over the course of the 10 weeks.The first task to be completed was to sort through old certification reports in 6 different boxes to locate reports that needed to be archived into a digital database. There were no reports within these boxes that needed to be archived but rather were to be shredded. The reports went back to the early 1980's and up to the early 2000's. I was looking for reports dated from 2002 to 2012

  16. Technical specifications for the Pajarito Site Critical Experiments Facility

    International Nuclear Information System (INIS)

    Malenfant, R.E.; Paxton, H.C.

    1980-12-01

    This document is to satisfy the requirement for technical specifications spelled out in DOE Manual Chapter 0540, Safety of DOE-Owned Reactors. Technical specifications are defined in Sec. 0540-048, and the requirement for them appears in Sec. 0540-015. The following technical specifications update the document, Technical Specifications for the Pajarito Site Critical Experiments Facility

  17. Technical Merits and Leadership in Facility Management

    National Research Council Canada - National Science Library

    Shoemaker, Jerry

    1997-01-01

    .... The document is divided into six chapters; the introduction, facility management and leadership, building systems, facility operations, facility maintenance strategies, and the conclusion and final analysis...

  18. Technical Evaluation of Oak Ridge Filter Test Facility

    CERN Document Server

    Kriskovich, J R

    2002-01-01

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

  19. NetView technical research

    Science.gov (United States)

    1993-01-01

    This is the Final Technical Report for the NetView Technical Research task. This report is prepared in accordance with Contract Data Requirements List (CDRL) item A002. NetView assistance was provided and details are presented under the following headings: NetView Management Systems (NMS) project tasks; WBAFB IBM 3090; WPAFB AMDAHL; WPAFB IBM 3084; Hill AFB; McClellan AFB AMDAHL; McClellan AFB IBM 3090; and Warner-Robins AFB.

  20. Shock Thermodynamic Applied Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Shock Thermodynamic Applied Research Facility (STAR) facility, within Sandia’s Solid Dynamic Physics Department, is one of a few institutions in the world with a...

  1. Sandia Combustion Research: Technical review

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This report contains reports from research programs conducted at the Sandia Combustion Research Facility. Research is presented under the following topics: laser based diagnostics; combustion chemistry; reacting flow; combustion in engines and commercial burners; coal combustion; and industrial processing. Individual projects were processed separately for entry onto the DOE databases.

  2. Atmospheric Research 2011 Technical Highlights

    Science.gov (United States)

    2012-01-01

    The 2011 Technical Highlights describes the efforts of all members of Atmospheric Research. Their dedication to advancing Earth Science through conducting research, developing and running models, designing instruments, managing projects, running field campaigns, and numerous other activities, is highlighted in this report.

  3. Technical merits and leadership in facility management

    OpenAIRE

    Shoemaker, Jerry J

    1997-01-01

    After almost ten years of experience and formal education in design, construction, and facility operations and maintenance, the challenges and complexity of facility management still seem overwhelming and intangible. This document explores those complexities and challenges, and presents several philosophies and strategies practiced in facility management. The document is divided into six chapters; the introduction, facility management and leadership, building systems, facility operations, fac...

  4. Preliminary technical data summary defense waste processing facility stage 2

    International Nuclear Information System (INIS)

    1980-12-01

    This Preliminary Technical Data Summary presents the technical basis for design of Stage 2 of the Staged Defense Waste Processing Facility (DWPF). Process changes incorporated in the staged DWPF relative to the Alternative DWPF described in PTDS No. 3 (DPSTD-77-13-3) are the result of ongoing research and development and are aimed at reducing initial capital investment and developing a process to efficiently immobilize the radionuclides in Savannah River Plant (SRP) high-level liquid waste. The radionuclides in SRP waste are present in sludge that has settled to the bottom of waste storage tanks and in crystallized salt and salt solution (supernate). Stage 1 of the DWPF receives washed, aluminum dissolved sludge from the waste tank farms and immobilizes it in a borosilicate glass matrix. The supernate is retained in the waste tank farms until completion of Stage 2 of the DWPF at which time it is filtered and decontaminated by ion exchange in the Stage 2 facility. The decontaminated supernate is concentrated by evaporation and mixed with cement for burial. The radioactivity removed from the supernate is fixed in borosilicate glass along with the sludge. This document gives flowsheets, material and curie balances, material and curie balance bases, and other technical data for design of Stage 2 of the DWPF. Stage 1 technical data are presented in DPSTD-80-38

  5. Robotics Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — This 60 feet x 100 feet structure on the grounds of the Fort Indiantown Gap Pennsylvania National Guard (PNG) Base is a mixed-use facility comprising office space,...

  6. Engine Environment Research Facility (EERF)

    Data.gov (United States)

    Federal Laboratory Consortium — Description: This facility supports research and development testing of the behavior of turbine engine lubricants, fuels and sensors in an actual engine environment....

  7. Materials Engineering Research Facility (MERF)

    Data.gov (United States)

    Federal Laboratory Consortium — Argonne?s Materials Engineering Research Facility (MERF) enables engineers to develop manufacturing processes for producing advanced battery materials in sufficient...

  8. Reference design for a centralized spent sealed sources facility. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    International Nuclear Information System (INIS)

    1995-07-01

    To assist Member States in establishing facilities in which the most frequently occurring spent sealed sources can be safely conditioned, the IAEA has financed the development of a generic design for a Spent Sealed Sources Facility (SSS Facility). The purpose of this TECDOC is to provide enough general information about the functions and capabilities of the SSS Facility to enable the reader to understand what the facility can do to contribute towards the management of spent sealed sources without providing all the technical and/or design information available. Sufficient information is provided to enable the reader to judge how and to what extent such a facility can contribute to national radioactive waste management infrastructure. 2 refs, 5 figs, 1 tab

  9. Reference design for a centralized spent sealed sources facility. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    To assist Member States in establishing facilities in which the most frequently occurring spent sealed sources can be safely conditioned, the IAEA has financed the development of a generic design for a Spent Sealed Sources Facility (SSS Facility). The purpose of this TECDOC is to provide enough general information about the functions and capabilities of the SSS Facility to enable the reader to understand what the facility can do to contribute towards the management of spent sealed sources without providing all the technical and/or design information available. Sufficient information is provided to enable the reader to judge how and to what extent such a facility can contribute to national radioactive waste management infrastructure. 2 refs, 5 figs, 1 tab.

  10. Technical Merits and Leadership in Facility Management

    National Research Council Canada - National Science Library

    Shoemaker, Jerry

    1997-01-01

    After almost ten years of experience and formal education in design, construction, and facility operations and maintenance, the challenges and complexity of facility management still seem overwhelming and intangible...

  11. LAMPF: a nuclear research facility

    International Nuclear Information System (INIS)

    Livingston, M.S.

    1977-09-01

    A description is given of the recently completed Los Alamos Meson Physics Facility (LAMPF) which is now taking its place as one of the major installations in this country for the support of research in nuclear science and its applications. Descriptions are given of the organization of the Laboratory, the Users Group, experimental facilities for research and for applications, and procedures for carrying on research studies

  12. Navy Fuel Research Facility

    Data.gov (United States)

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

  13. Proceedings of the IEA-technical workshop for an international fusion materials irradiation facility. IEA-implementing agreement for a programme of research and development on fusion materials

    International Nuclear Information System (INIS)

    Ehrlich, K.; Lindau, R.

    1995-07-01

    The workshop was initiated to deal with the following objectives: (1) Critical review of the requirements for IFMIF from the user's point of view; (2) Definition of a baseline concept for the CDA-study; (3) Formation of working groups for main fields of activities; (4) Identification of tasks and critical issues for main components; (5) Development of a working break-down structure, distribution of work and milestones for CDA-activities; (6) Documentation of main results. According to the enclosed agenda the mission for a Conceptual Design Study, the requirements for an intense neutron source from the user's point of view and the baseline concept for an accelerator-driven D-Li neutron source were discussed in several plenary sessions. In three subgroups (SG 1 Accelerators, SG2 Lithium Target and SG3 Users and Test Cell) technical concepts for the different components and facilities were discussed in detail, critical issues and tasks for the concept study were identified. Finally, the sharing of tasks to the different national parties, questions of organisation of the work, flow of information and definition of milestones was agreed upon. The detailled summary reports of the subgroups and the contributions of the plenary sessions are presented in the proceedings. (orig./HP)

  14. Detonation Engine Research Facility (DERF)

    Data.gov (United States)

    Federal Laboratory Consortium — Description: This facility is configured to safely conduct experimental pressuregain combustion research. The DERF is capable of supporting up to 60,000 lbf thrust...

  15. the effects of unavailability of technical storage facilities

    African Journals Online (AJOL)

    unavailability of the technical storage facilities to the marketing of fruits and vegetables for economic ... vegetables are important profitable small-scale juice enterprises (Thomson,. 1990). ..... Knott's handbook for vegetables growers. 2nd ed.

  16. The Radiological Research Accelerator Facility

    International Nuclear Information System (INIS)

    Hall, E.J.; Marino, S.A.

    1990-07-01

    The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) -- formerly the Radiological Research Laboratory (RRL) -- of Columbia University, and its operation is supported as a National Facility by the US Department of Energy (DOE). Fifteen different experiments were run during these 12 months, approximately the same as the previous two years. Brief summaries of each experiment are included. Accelerator usage is summarized and development activities are discussed. 7 refs., 4 tabs

  17. Research Institute for Technical Careers

    Science.gov (United States)

    Glenn, Ronald L.

    1996-01-01

    The NASA research grant to Wilberforce University enabled us to establish the Research Institute for Technical Careers (RITC) in order to improve the teaching of science and engineering at Wilberforce. The major components of the research grant are infrastructure development, establishment of the Wilberforce Intensive Summer Experience (WISE), and Joint Research Collaborations with NASA Scientists. (A) Infrastructure Development. The NASA grant has enabled us to improve the standard of our chemistry laboratory and establish the electronics, design, and robotics laboratories. These laboratories have significantly improved the level of instruction at Wilberforce University. (B) Wilberforce Intensive Summer Experience (WISE). The WISE program is a science and engineering bridge program for prefreshman students. It is an intensive academic experience designed to strengthen students' knowledge in mathematics, science, engineering, computing skills, and writing. (C) Joint Collaboration. Another feature of the grant is research collaborations between NASA Scientists and Wilberforce University Scientists. These collaborations have enabled our faculty and students to conduct research at NASA Lewis during the summer and publish research findings in various journals and scientific proceedings.

  18. Functional criteria for emergency response facilities. Technical report (final)

    International Nuclear Information System (INIS)

    1981-02-01

    This report describes the facilities and systems to be used by nuclear power plant licensees to improve responses to emergency situations. The facilities include the Technical Support Center (TSC), Onsite Operational Support Center (OSC), and Nearsite Emergency Operations Facility (EOF), as well as a brief discussion of the emergency response function of the control room. The data systems described are the Safety Parameter Display System (SPDS) and Nuclear Data Link (NDL). Together, these facilities and systems make up the total Emergency Response Facilities (ERFs). Licensees should follow the guidance provided both in this report and in NUREG-0654 (FEMA-REP-1), Revision 1, for design and implementation of the ERFs

  19. Technical requirement of experiments and facilities for fusion nuclear technology

    International Nuclear Information System (INIS)

    Abdou, M.; Tillak, M.; Gierszwski, P.; Grover, J.; Puigh, R.; Sze, D.K.; Berwald, D.

    1986-06-01

    The technical issues and requirements of experiments and facilities for fusion nuclear technology (FNT) have been investigated. The nuclear subsystems addressed are: a) blanket, b) radiation shield, c) tritium processing system, and d) plasma interactive components. Emphasis has been placed on the important and complex development problems of the blanket. A technical planning process for FNT has been developed and applied, including four major elements: 1) characterization of issues, 2) quantification of testing requirements, 3) evaluation of facilities, and 4) development of a test plan to identify the role, timing, characteristics and costs of major experiments and facilities

  20. Technical evaluation of proposed Ukrainian Central Radioactive Waste Processing Facility

    International Nuclear Information System (INIS)

    Gates, R.; Glukhov, A.; Markowski, F.

    1996-06-01

    This technical report is a comprehensive evaluation of the proposal by the Ukrainian State Committee on Nuclear Power Utilization to create a central facility for radioactive waste (not spent fuel) processing. The central facility is intended to process liquid and solid radioactive wastes generated from all of the Ukrainian nuclear power plants and the waste generated as a result of Chernobyl 1, 2 and 3 decommissioning efforts. In addition, this report provides general information on the quantity and total activity of radioactive waste in the 30-km Zone and the Sarcophagus from the Chernobyl accident. Processing options are described that may ultimately be used in the long-term disposal of selected 30-km Zone and Sarcophagus wastes. A detailed report on the issues concerning the construction of a Ukrainian Central Radioactive Waste Processing Facility (CRWPF) from the Ukrainian Scientific Research and Design institute for Industrial Technology was obtained and incorporated into this report. This report outlines various processing options, their associated costs and construction schedules, which can be applied to solving the operating and decommissioning radioactive waste management problems in Ukraine. The costs and schedules are best estimates based upon the most current US industry practice and vendor information. This report focuses primarily on the handling and processing of what is defined in the US as low-level radioactive wastes

  1. The Radiological Research Accelerator Facility

    International Nuclear Information System (INIS)

    Hall, E.J.; Marino, S.A.

    1991-05-01

    The Radiological Research Accelerator Facility (RARAF) is based on 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) -- formerly the Radiological Research Laboratory (RRL) -- of Columbia University, and its operation is supported as a National Facility by the US Department of Energy (DOE). As such, RARAF is available to all potential users on an equal basis, and scientists outside the CRR are encouraged to submit proposals for experiments at RARAF. The operation of the Van de Graaff is supported by the DOE, but the research projects themselves must be supported separately. Brief summaries of research experiments are included. Accelerator usage is summarized and development activities are discussed. 8 refs., 8 tabs

  2. The INEL Tritium Research Facility

    International Nuclear Information System (INIS)

    Longhurst, G.R.

    1990-01-01

    The Tritium Research Facility (TRF) at the Idaho National Engineering Laboratory (INEL) is a small, multi-user facility dedicated to research into processes and phenomena associated with interaction of hydrogen isotopes with other materials. Focusing on bench-scale experiments, the main objectives include resolution of issues related to tritium safety in fusion reactors and the science and technology pertinent to some of those issues. In this report the TRF and many of its capabilities will be described. Work presently or recently underway there will be discussed, and the implications of that work to the development of fusion energy systems will be considered. (orig.)

  3. The INEL Tritium Research Facility

    Energy Technology Data Exchange (ETDEWEB)

    Longhurst, G.R. (Idaho National Engineering Lab., Idaho Falls (USA))

    1990-06-01

    The Tritium Research Facility (TRF) at the Idaho National Engineering Laboratory (INEL) is a small, multi-user facility dedicated to research into processes and phenomena associated with interaction of hydrogen isotopes with other materials. Focusing on bench-scale experiments, the main objectives include resolution of issues related to tritium safety in fusion reactors and the science and technology pertinent to some of those issues. In this report the TRF and many of its capabilities will be described. Work presently or recently underway there will be discussed, and the implications of that work to the development of fusion energy systems will be considered. (orig.).

  4. The Radiological Research Accelerator Facility

    International Nuclear Information System (INIS)

    Hall, E.J.

    1992-05-01

    The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) -- formerly the Radiological Research Laboratory (RRL) -- of Columbia University, and its operation is supported as a National Facility by the US Department of Energy (DOE). As such, RARAF is available to all potential users on an equal basis, and scientists outside the CRR are encouraged to submit proposals for experiments at RARAF. The operation of the Van de Graaff is supported by the DOE, but the research projects themselves must be supported separately. Experiments performed from May 1991--April 1992 are described

  5. The Radiological Research Accelerator Facility

    International Nuclear Information System (INIS)

    Hall, E.J.; Marino, S.A.

    1993-05-01

    The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generate a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Center for Radiological Research (CRR) - formerly the Radiological Research Laboratory of Columbia University, and its operation is supported as a National Facility by the US Department of Energy (DOE). As such, RARAF is available to all potential users on an equal basis and scientists outside the CRR are encouraged to submit proposals for experiments at RARAF. The operation of the Van de Graaff is supported by the DOE, but the research projects themselves must be supported separately. This report provides a listing and brief description of experiments performed at RARAF during the May 1, 1992 through April 30, 1993

  6. The Radiological Research Accelerator Facility:

    International Nuclear Information System (INIS)

    Hall, E.J.; Goldhagen, P.

    1988-07-01

    The Radiological Research Accelerator Facility (RARAF) is based on a 4-MV Van de Graaff accelerator, which is used to generated a variety of well-characterized radiation beams for research in radiobiology, radiological physics, and radiation chemistry. It is part of the Radiological Research Laboratory (RRL) of Columbia University, and its operation is supported as a National Facility by the U.S. Department of Energy. As such, RARAF is available to all potential users on an equal basis, and scientists outside the RRL are encouraged to submit proposals for experiments at RARAF. Facilities and services are provided to users, but the research projects themselves must be supported separately. RARAF was located at BNL from 1967 until 1980, when it was dismantled and moved to the Nevis Laboratories of Columbia University, where it was then reassembled and put back into operation. Data obtained from experiment using RARAF have been of pragmatic value to radiation protection and to neutron therapy. At a more fundamental level, the research at RARAF has provided insight into the biological action of radiation and especially its relation to energy distribution in the cell. High-LET radiations are an agent of special importance because they can cause measurable cellular effects by single particles, eliminating some of the complexities of multievent action and more clearly disclosing basic features. This applies particularly to radiation carcinogenesis. Facilities are available at RARAF for exposing objects to different radiations having a wide range of linear energy transfers (LETs)

  7. Technical Safety Requirements for the Gamma Irradiation Facility (GIF)

    CERN Document Server

    Mahn, J A E M J G

    2003-01-01

    This document provides the Technical Safety Requirements (TSR) for the Sandia National Laboratories Gamma Irradiation Facility (GIF). The TSR is a compilation of requirements that define the conditions, the safe boundaries, and the administrative controls necessary to ensure the safe operation of a nuclear facility and to reduce the potential risk to the public and facility workers from uncontrolled releases of radioactive or other hazardous materials. These requirements constitute an agreement between DOE and Sandia National Laboratories management regarding the safe operation of the Gamma Irradiation Facility.

  8. Technical specifications for the Oak Ridge Critical Experiments Facility

    International Nuclear Information System (INIS)

    Stinnett, R.M.

    1986-01-01

    These Technical Specifications for the Oak Ridge Critical Experiments Facility (CEF) delineate limiting conditions of operation for the facility. The CEF is used primarily for testing the High Flux Isotope Reactor (HFIR) fuel assemblies. Specifically, the Criticality Testing Unit, Liquid (CTUL), located in the CEF, is used for the HFIR fuel assembly test. The test is performed to satisfy the surveillance requirements of the HFIR Technical Specifications. The test is used to determine the water-submerged shutdown margin for each fuel assembly. 11 refs

  9. F/H effluent treatment facility. Technical data summary

    International Nuclear Information System (INIS)

    Ryan, J.P.; Stimson, R.E.

    1984-12-01

    This document provides the technical basis for the design of the facility. Some of the sections are described with options to permit simplification of the process, depending on the effluent quality criteria that the facility will have to meet. Each part of the F/HETF process is reviewed with respect to decontamination and concentration efficiency, operability, additional waste generation, energy efficiency, and compatability with the rest of the process

  10. Research Needs: Career and Technical Education

    Science.gov (United States)

    Kosloski, Michael F., Jr.; Ritz, John M.

    2016-01-01

    Research is an important component of each professional field. This study sought to determine topics that needed further research in the school subjects known as career and technical education. It determined topics that needed to be researched related to high school career and technical education (CTE) and the preparation for teaching CTE in…

  11. Trends in Career and Technical Education Research

    Science.gov (United States)

    Rojewski, Jay W.; Asunda, Paul; Kim, Soo Jung

    2008-01-01

    The purpose of this literature review was to identify current trends and issues in research focusing on career and technical education (CTE). The primary sources of literature for this review included all research articles published in three refereed scholarly journals--"Career and Technical Education Research," "Journal of Career and Technical…

  12. Technical concept for a Greater Confinement Disposal test facility

    International Nuclear Information System (INIS)

    Hunter, P.H.

    1982-01-01

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

  13. Report on International Spaceborne Imaging Spectroscopy Technical Committee Calibration and Validation Workshop, National Environment Research Council Field Spectroscopy Facility, University of Edinburgh

    Science.gov (United States)

    Ong, C,; Mueller, A.; Thome, K.; Bachmann, M.; Czapla-Myers, J.; Holzwarth, S.; Khalsa, S. J.; Maclellan, C.; Malthus, T.; Nightingale, J.; hide

    2016-01-01

    Calibration and validation are fundamental for obtaining quantitative information from Earth Observation (EO) sensor data. Recognising this and the impending launch of at least five sensors in the next five years, the International Spaceborne Imaging Spectroscopy Technical Committee instigated a calibration and validation initiative. A workshop was conducted recently as part of this initiative with the objective of establishing a good practice framework for radiometric and spectral calibration and validation in support of spaceborne imaging spectroscopy missions. This paper presents the outcomes and recommendations for future work arising from the workshop.

  14. The internationalisation of research facilities

    International Nuclear Information System (INIS)

    Sabine, T.M.

    1999-01-01

    Full text: During the past twenty five years arrangements have been made for sharing the use of major national research facilities amongst the world community of neutron users. The administrative requirements are simple. Scientists are invited to apply for measurement time. The scientific merit of the application is assessed by a committee appointed by the host organisation. If the application is considered to have sufficient merit time is allocated. The only costs to the user are transport and living expenses. These arrangements have advantages for users and for hosts. The user can apply for time on the most suitable instrument. The host in the user country is freed from the responsibility of supplying all instruments. It can specialise in those instruments in which it has particular expertise. The host retains, through its committee, complete control over the use of instruments. The amount of time allocated to international users is dependent on the national demand. The result is efficient use of national facilities. An equally important result is the interaction between members of the international scientific community. Australian scientists routinely use overseas facilities however Australia has refused to join the international group. There is international resentment to this attitude. We have, for example powder diffraction facilities which others wish to use. We have no small-angle scattering facilities and must do our experiments at international centres. I will argue that we should join the international community now. The capacity of the replacement reactor will be far greater than the internal Australian requirements. We will become the natural host for users from countries in the Asian region. To enable us to make a smooth transition to this stage we should immediately advertise an international program for HIFAR

  15. Technical Safety Requirements for the Waste Storage Facilities May 2014

    Energy Technology Data Exchange (ETDEWEB)

    Laycak, D. T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2014-04-16

    This document contains the Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Building 693 (B693) Yard Area of the Decontamination and Waste Treatment Facility (DWTF) at LLNL. The TSRs constitute requirements for safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analyses for the Waste Storage Facilities (DSA) (LLNL 2011). The analysis presented therein concluded that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts of waste from other DOE facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities.

  16. Technical Safety Requirements for the Waste Storage Facilities May 2014

    International Nuclear Information System (INIS)

    Laycak, D. T.

    2014-01-01

    This document contains the Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Building 693 (B693) Yard Area of the Decontamination and Waste Treatment Facility (DWTF) at LLNL. The TSRs constitute requirements for safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analyses for the Waste Storage Facilities (DSA) (LLNL 2011). The analysis presented therein concluded that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts of waste from other DOE facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities.

  17. Ozone Layer Research and Technical Resources

    Science.gov (United States)

    Access information on research and technical resources related to ozone layer science. This page provides links to research efforts led by organizations such as the National Oceanic and Atmospheric Administration, the United Nations Environment Program, an

  18. Research facility access & science education

    Energy Technology Data Exchange (ETDEWEB)

    Rosen, S.P. [Univ. of Texas, Arlington, TX (United States); Teplitz, V.L. [Southern Methodist Univ., Dallas, TX (United States). Physics Dept.

    1994-10-01

    As Congress voted to terminate the Superconducting Super Collider (SSC) Laboratory in October of 1993, the Department of Energy was encouraged to maximize the benefits to the nation of approximately $2 billion which had already been expended to date on its evolution. Having been recruited to Texas from other intellectually challenging enclaves around the world, many regional scientists, especially physicists, of course, also began to look for viable ways to preserve some of the potentially short-lived gains made by Texas higher education in anticipation of {open_quotes}the SSC era.{close_quotes} In fact, by November, 1993, approximately 150 physicists and engineers from thirteen Texas universities and the SSC itself, had gathered on the SMU campus to discuss possible re-uses of the SSC assets. Participants at that meeting drew up a petition addressed to the state and federal governments requesting the creation of a joint Texas Facility for Science Education and Research. The idea was to create a facility, open to universities and industry alike, which would preserve the research and development infrastructure and continue the educational mission of the SSC.

  19. Emergency response facility technical data system of Taiwan Power Company

    International Nuclear Information System (INIS)

    Lin, E.; Liang, T.M.

    1987-01-01

    Taiwan Power Company (Taipower) has developed its emergency response facility program since 1981. This program is integrated with the following activities to enhance the emergency response capability of nuclear power plants: (1) survey of the plant instrumentation based on the requirements of R.G. 1.97; (2) improvement of plant specific emergency operating procedures based on the emergency response guidelines developed by the Owners group; (3) implementation of the detailed control room design review with the consideration of human engineering and task analysis; and (4) organization, staff and communication of emergency planning of nuclear power plant. The emergency response facility programs of Taipower are implemented in Chinshan (GE BWR4/MARK I), Kuosheng (GE BWR6/MARK III) and Maanshan (W PWR). The major items included in each program are: (1) to establish new buildings for On-Site Technical Support Center, Near-Site Emergency Operation Facility; (2) to establish an Emergency Executive Center at Taipower headquarters; (3) to establish the communication network between control room and emergency response facilities; and (4) to install a dedicated Emergency Response Facility Technical Data System (ERFTDS) for each plant. The ERFTDS provides the functions of data acquisition, data processing, data storage and display in meeting with the requirements of NUREG 0696. The ERFTDS is designed with plant specific requirements. These specific requirements are expected to be useful not only for the emergency condition but also for normal operation conditions

  20. Technical viability and development needs for waste forms and facilities

    Energy Technology Data Exchange (ETDEWEB)

    Pegg, I.; Gould, T.

    1996-05-01

    The objective of this breakout session was to provide a forum to discuss technical issues relating to plutonium-bearing waste forms and their disposal facilities. Specific topics for discussion included the technical viability and development needs associated with the waste forms and/or disposal facilities. The expected end result of the session was an in-depth (so far as the limited time would allow) discussion of key issues by the session participants. The session chairs expressed allowance for, and encouragement of, alternative points of view, as well as encouragement for discussion of any relevant topics not addressed in the paper presentations. It was not the intent of this session to recommend or advocate any one technology over another.

  1. Realizing Sustainability in Facilities Management: a pilot study at the Technical University of Denmark

    DEFF Research Database (Denmark)

    Nielsen, Susanne Balslev; Møller, Jacob Steen; Jäschke, Stefan

    2012-01-01

    , qualitative research and the preliminary analysis of a single, pilot case study of The Technical University of Denmark. Progress with the other complementary cases will be included in the presentation. The cases should be supplemented by more research on sustainable facilities management. Originality......, stakeholder interviews, focus groups, usability evaluations and practice-research workshops. The Technical University of Denmark (DTU) is the pilot case of an international collaboration, and more studies are planned to follow. Findings: The paper presents a framework for qualitative research on Sustainable...... Facilities Management (SFM), which can guide future research on Sustainability in FM and increase comparability between case studies. The research identifies the challenges and opportunities for integrating ecological, social and economical sustainability in university FM. The paper presents the analysis...

  2. Human Research Ethics Committees in Technical Universities

    NARCIS (Netherlands)

    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

  3. Technical specifications: Health Physics Research Reactor

    International Nuclear Information System (INIS)

    1986-03-01

    These technical specifications define the key limitations that must be observed for safe operation of the Health Physics Research Reactor (HPRR) and an envelope of operation within which there is assurance that these limits will not be exceeded

  4. General problems specific to hot nuclear materials research facilities

    International Nuclear Information System (INIS)

    Bart, G.

    1996-01-01

    During the sixties, governments have installed hot nuclear materials research facilities to characterize highly radioactive materials, to describe their in-pile behaviour, to develop and test new reactor core components, and to provide the industry with radioisotopes. Since then, the attitude towards the nuclear option has drastically changed and resources have become very tight. Within the changed political environment, the national research centres have defined new objectives. Given budgetary constraints, nuclear facilities have to co-operate internationally and to look for third party research assignments. The paper discusses the problems and needs within experimental nuclear research facilities as well as industrial requirements. Special emphasis is on cultural topics (definition of the scope of nuclear research facilities, the search for competitive advantages, and operational requirements), social aspects (overageing of personnel, recruitment, and training of new staff), safety related administrative and technical issues, and research needs for expertise and state of the art analytical infrastructure

  5. CSNI Technical Opinion Papers No. 15 - Ageing management of nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Nocture, Pierre; Daubard, Jean-Paul; Lhomme, Veronique; Martineau, Dominique; Blundell, Neil; Conte, Dorothee; Dobson, Martin; Gmal, Bernhard; Hiltz, Thomas; Ueda, Yoshinori

    2012-01-01

    Managing the ageing of fuel cycle facilities (FCFs) means, as for other nuclear installations, ensuring the availability of required safety functions throughout their service life while taking into account the changes that occur with time and use. This technical opinion paper identifies a set of good practices by benchmarking strategies and good practices on coping with physical ageing and obsolescence from the facility design stage until decommissioning. It should be of particular interest to nuclear safety regulators, fuel cycle facilities operators and fuel cycle researchers [fr

  6. Atmospheric Research 2012 Technical Highlights

    Science.gov (United States)

    Lau, William K -M.

    2013-01-01

    This annual report, as before, is intended for a broad audience. Our readers include colleagues within NASA, scientists outside the Agency, science graduate students, and members of the general public. Inside are descriptions of atmospheric research science highlights and summaries of our education and outreach accomplishments for calendar year 2012.The report covers research activities from the Mesoscale Atmospheric Processes Laboratory, the Climate and Radiation Laboratory, the Atmospheric Chemistry and Dynamics Laboratory, and the Wallops Field Support Office under the Office of Deputy Director for Atmospheres, Earth Sciences Division in the Sciences and Exploration Directorate of NASAs Goddard Space Flight Center. The overall mission of the office is advancing knowledge and understanding of the Earths atmosphere. Satellite missions, field campaigns, peer-reviewed publications, and successful proposals are essential to our continuing research.

  7. Atmospheric Research 2014 Technical Highlights

    Science.gov (United States)

    Platnick, Steven

    2015-01-01

    Atmospheric research in the Earth Sciences Division (610) consists of research and technology development programs dedicated to advancing knowledge and understanding of the atmosphere and its interaction with the climate of Earth. The Division's goals are to improve understanding of the dynamics and physical properties of precipitation, clouds, and aerosols; atmospheric chemistry, including the role of natural and anthropogenic trace species on the ozone balance in the stratosphere and the troposphere; and radiative properties of Earth's atmosphere and the influence of solar variability on the Earth's climate. Major research activities are carried out in the Mesoscale Atmospheric Processes Laboratory, the Climate and Radiation Laboratory, the Atmospheric Chemistry and Dynamics Laboratory, and the Wallops Field Support Office. The overall scope of the research covers an end-to-end process, starting with the identification of scientific problems, leading to observation requirements for remote-sensing platforms, technology and retrieval algorithm development; followed by flight projects and satellite missions; and eventually, resulting in data processing, analyses of measurements, and dissemination from flight projects and missions. Instrument scientists conceive, design, develop, and implement ultraviolet, infrared, optical, radar, laser, and lidar technology to remotely sense the atmosphere. Members of the various Laboratories conduct field measurements for satellite sensor calibration and data validation, and carry out numerous modeling activities. These modeling activities include climate model simulations, modeling the chemistry and transport of trace species on regional-to-global scales, cloud resolving models, and developing the next-generation Earth system models. Satellite missions, field campaigns, peer-reviewed publications, and successful proposals are essential at every stage of the research process to meeting our goals and maintaining leadership of the

  8. Atmospheric Research 2016 Technical Highlights

    Science.gov (United States)

    Platnick, Steven

    2017-01-01

    Atmospheric research in the Earth Sciences Division (610) consists of research and technology development programs dedicated to advancing knowledge and understanding of the atmosphere and its interaction with the climate of Earth. The Divisions goals are to improve understanding of the dynamics and physical properties of precipitation, clouds, and aerosols; atmospheric chemistry, including the role of natural and anthropogenic trace species on the ozone balance in the stratosphere and the troposphere; and radiative properties of Earth's atmosphere and the influence of solar variability on the Earth's climate. Major research activities are carried out in the Mesoscale Atmospheric Processes Laboratory, the Climate and Radiation Laboratory, the Atmospheric Chemistry and Dynamics Laboratory, and the Wallops Field Support Office. The overall scope of the research covers an end-to-end process, starting with the identification of scientific problems, leading to observation requirements for remote-sensing platforms, technology and retrieval algorithm development; followed by flight projects and satellite missions; and eventually, resulting in data processing, analyses of measurements, and dissemination from flight projects and missions. Instrument scientists conceive, design, develop, and implement ultraviolet, infrared, optical, radar, laser, and lidar technology to remotely sense the atmosphere. Members of the various laboratories conduct field measurements for satellite sensor calibration and data validation, and carry out numerous modeling activities. These modeling activities include climate model simulations, modeling the chemistry and transport of trace species on regional-to-global scales, cloud resolving models, and developing the next-generation Earth system models. Satellite missions, field campaigns, peer-reviewed publications, and successful proposals are essential at every stage of the research process to meeting our goals and maintaining leadership of the

  9. Human research ethics committees in technical universities.

    Science.gov (United States)

    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.

  10. Stockbridge Antenna Measurement and Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Stockbridge Antenna Measurement Facility is located 23 miles southwest of AFRL¹s Rome Research Site. This unique measurement facility is designed to evaluate the...

  11. Proceedings of the IEA-technical workshop on the test cell system for an international fusion materials irradiation facility, Karlsruhe, Germany, July 3-6, 1995. IEA-implementing agreement for a programme of research and development on fusion materials

    International Nuclear Information System (INIS)

    Moeslang, A.; Lindau, R.

    1995-09-01

    After a Conceptual Design Activity (CDA) study on an International Fusion Material Irradiation Facility (IFMIF) has been launched under the auspices of the IEA, working groups and relevant tasks have been defined and agreed in an IEA-workshop that was held September 26-29 1994 at Karlsruhe. For the Test Cell System 11 tasks were identified which can be grouped into the three major fields neutronics, test matrix/users and test cell engineering. In order to discuss recently achieved results and to coordinate necessary activities for an effective design integration, a technical workshop on the Test Cell System was initiated. This workshop was organized on July 3-6 1995 by the Institute for Materials Research I at the Forschungszentrum Karlsruhe and attended by 20 specialists working in the fields neutronics, fusion materials R and D and test cell engineering in the European Union, Japan, and the United States of America. The presentations and discussions during this workshop have shown together with the elaborated lists of action items, that has been achieved in all three fields, and that from the future IFMIF experimental program for a number of materials a database covering widerspread loading conditions up to DEMO-reactor relevant end-of-life damage levels can be expected. (orig.)

  12. Technical Review of the Laboratory Biosphere Closed Ecological System Facility

    Science.gov (United States)

    Dempster, W.; van Thillo, M.; Alling, A.; Allen, J.; Silverstone, S.; Nelson, M.

    The "Laboratory Biosphere", a new closed ecological system facility in Santa Fe, New Mexico (USA) has been constructed and became operational in May 2002. Built and operated by the Global Ecotechnics consortium (Biosphere Technologies and Biosphere Foundation with Biospheric Design Inc., and the Institute of Ecotechnics), the research apparatus for intensive crop growth, biogeochemical cycle dynamics and recycling of inedible crop biomass comprises a sealed cylindrical steel chamber and attached variable volume chamber (lung) to prevent pressures caused by the expansion and contraction of the contained air. The cylindrical growing chamber is 3.7m (12 feet) long and 3.7m (12 foot) diameter, giving an internal volume of 34 m3 (1200 ft 3 ). The two crop growth beds cover 5.5 m2, with a soil depth of 0.3m (12 inches), with 12 x 1000 watt high-pressure sodium lights capable of variable lighting of 40-70 mol per m2 per day. A small soil bed reactor in the chamber can be activated to help with metabolism of chamber trace gases. The volume of the attached variable volume chamber (lung) can range between 0-11 m3 (0-400 ft 3 ). Evapotranspired and soil leachate water are collected, combined and recycled to water the planting beds. Sampling ports enable testing of water quality of leachate, condensate and irrigation water. Visual inspection windows provide views of the entire interior and growing beds. The chamber is also outfitted with an airlock to minimize air exchange when people enter and work in the chamber. Continuous sensors include atmospheric CO2 and oxygen, temperature, humidity, soil moisture, light level and water levels in reservoirs. Both "sniffer" (air ports) and "sipper" (water ports) will enable collection of water or air samples for detailed analysis. This paper reports on the development of this new soil-based bioregenerative life support closed system apparatus and its technical challenges and capabilities.

  13. Technical Safety Requirements for the Waste Storage Facilities

    International Nuclear Information System (INIS)

    Larson, H L

    2007-01-01

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage

  14. Technical Safety Requirements for the Waste Storage Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Larson, H L

    2007-09-07

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage

  15. 75 FR 74026 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2010-11-30

    ... DEPARTMENT OF ENERGY Biomass Research and Development Technical Advisory Committee AGENCY.... SUMMARY: This notice announces an open meeting of the Biomass Research and Development Technical Advisory... participation. This notice announces the meeting of the Biomass Research and Development Technical Advisory...

  16. Cold Vacuum Drying (CVD) Facility Technical Safety Requirements

    International Nuclear Information System (INIS)

    KRAHN, D.E.

    2000-01-01

    The Technical Safety Requirements (TSRs) for the Cold Vacuum Drying Facility define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation during receipt of multi-canister overpacks (MCOs) containing spent nuclear fuel. removal of free water from the MCOs using the cold vacuum drying process, and inerting and testing of the MCOs before transport to the Canister Storage Building. Controls required for public safety, significant defense in depth, significant worker safety, and for maintaining radiological and toxicological consequences below risk evaluation guidelines are included

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

    International Nuclear Information System (INIS)

    Hunter, P.H.

    1982-01-01

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

  18. Inertial fusion research: Annual technical report, 1985

    International Nuclear Information System (INIS)

    Larsen, J.T.; Terry, N.C.

    1986-03-01

    This report describes the inertial confinement fusion (ICF) research activities undertaken at KMS Fusion (KMSF) during 1985. It is organized into three main technical sections; the first covers fusion experiments and theoretical physics, the second is devoted to progress in materials development and target fabrication, and the third describes laser technology research. These three individual sections have been cataloged separately

  19. Research in technical communication in the Netherlands

    NARCIS (Netherlands)

    Jansen, C.J.M.

    1994-01-01

    In the Netherlands, research in technical communication is a part of research in 'functional text,' which has concrete goals that must be achieved by lay readers. Three recent studies focus on the use of and failure to use software manuals, the minimalist approach and learning styles, and the effect

  20. Reference design for a centralized waste processing and storage facility. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-01

    The objective of this report is to present the generic reference design of a centralized waste processing and storage facility (WPSF) intended for countries producing small but significant quantities of liquid and solid radioactive wastes. These wastes are generated through the use of radionuclides for research, medical, industrial and other institutional activities in IAEA Member States that have not yet developed the infrastructure for a complete nuclear fuel cycle. The WPSF comprises two separate buildings. The first, for receiving and processing waste from the producers, includes the necessary equipment and support services for treating and conditioning the waste. The second building acts as a simple but adequate warehouse for storing a ten year inventory of the conditioned waste. In developing the design, it was a requirement of the IAEA that options for waste management techniques for each of the waste streams should be evaluated, in order to demonstrate that the reference design is based on the most appropriate technology. Refs, figs and tabs.

  1. Reference design for a centralized waste processing and storage facility. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

    International Nuclear Information System (INIS)

    1994-12-01

    The objective of this report is to present the generic reference design of a centralized waste processing and storage facility (WPSF) intended for countries producing small but significant quantities of liquid and solid radioactive wastes. These wastes are generated through the use of radionuclides for research, medical, industrial and other institutional activities in IAEA Member States that have not yet developed the infrastructure for a complete nuclear fuel cycle. The WPSF comprises two separate buildings. The first, for receiving and processing waste from the producers, includes the necessary equipment and support services for treating and conditioning the waste. The second building acts as a simple but adequate warehouse for storing a ten year inventory of the conditioned waste. In developing the design, it was a requirement of the IAEA that options for waste management techniques for each of the waste streams should be evaluated, in order to demonstrate that the reference design is based on the most appropriate technology. Refs, figs and tabs

  2. Technical Safety Requirements for the Waste Storage Facilities

    International Nuclear Information System (INIS)

    Laycak, D.T.

    2010-01-01

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2009). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting

  3. Technical Safety Requirements for the Waste Storage Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Laycak, D T

    2008-06-16

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the 'Documented Safety Analysis for the Waste Storage Facilities' (DSA) (LLNL 2008). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas

  4. Surface Fire Hazards Analysis Technical Report-Constructor Facilities

    International Nuclear Information System (INIS)

    Flye, R.E.

    2000-01-01

    The purpose of this Fire Hazards Analysis Technical Report (hereinafter referred to as Technical Report) is to assess the risk from fire within individual fire areas to ascertain whether the U.S. Department of Energy (DOE) fire safety objectives are met. The objectives identified in DOE Order 420.1, Change 2, Facility Safety, Section 4.2, establish requirements for a comprehensive fire and related hazards protection program for facilities sufficient to minimize the potential for: The occurrence of a fire or related event; A fire that causes an unacceptable on-site or off-site release of hazardous or radiological material that will threaten the health and safety of employees, the public, or the environment; Vital DOE programs suffering unacceptable interruptions as a result of fire and related hazards; Property losses from a fire and related events exceeding defined limits established by DOE; and Critical process controls and safety class systems being damaged as a result of a fire and related events

  5. A monitored retrievable storage facility: Technical background information

    International Nuclear Information System (INIS)

    1991-07-01

    The US government is seeking a site for a monitored retrievable storage facility (MRS). Employing proven technologies used in this country and abroad, the MRS will be an integral part of the federal system for safe and permanent disposal of the nation's high-level radioactive wastes. The MRS will accept shipments of spent fuel from commercial nuclear power plants, temporarily store the spent fuel above ground, and stage shipments of it to a geologic repository for permanent disposal. The law authorizing the MRS provides an opportunity for a state or an Indian tribe to volunteer to host the MRS. The law establishes the Office of the Nuclear Waste Negotiator, who is to seek a state or an Indian tribe willing to host an MRS at a technically-qualified site on reasonable terms, and is to negotiate a proposed agreement specifying the terms and conditions under which the MRS would be developed and operated at that site. This agreement can ensure that the MRS is acceptable to -- and benefits -- the host community. The proposed agreement must be submitted to Congress and enacted into law to become effective. This technical background information presents an overview of various aspects of a monitored retrievable storage facility, including the process by which it will be developed

  6. Technical issues in licensing low-level radioactive waste facilities

    Energy Technology Data Exchange (ETDEWEB)

    Junkert, R. [California Dept. of Health Services, CA (United States)

    1993-03-01

    The California Department of Health Service spent two years in the review of an application for a low-level radioactive waste disposal facility in California. During this review period a variety of technical issues had to be evaluated and resolved. One of the first issues was the applicability and use of NRC guidance documents for the development of LLW disposal facilities. Other technical issues that required intensive evaluations included surface water hydrology, seismic investigation, field and numerical analysis of the unsaturated zone, including a water infiltration test. Source term verification became an issue because of one specific isotope that comprised more than 90% of the curies projected for disposal during the operational period. The use of trench liners and the proposed monitoring of the unsaturated zone were reviewed by a highly select panel of experts to provide guidance on the need for liners and to ensure that the monitoring system was capable of monitoring sufficient representative areas for radionuclides in the soil, soil gas, and soil moisture. Finally, concerns about the quality of the preoperational environmental monitoring program, including data, sample collection procedures, laboratory analysis, data review and interpretation and duration of monitoring caused a significant delay in completing the licensing review.

  7. Branch technical position for performance assessment of low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Campbell, A.C.; Abramson, L.; Byrne, R.M.

    1994-01-01

    The U.S. Nuclear Regulatory Commission has developed a Draft Branch Technical Position on Performance Assessment of Low-Level Radioactive Waste Disposal Facilities. The draft technical position addresses important issues in performance assessment modeling and provides a framework and technical basis for conducting and evaluating performance assessments in a disposal facility license application. The technical position also addresses specific technical policy issues and augments existing NRC guidance pertaining to LLW performance assessment

  8. Inertial fusion research. Annual technical report, 1984

    International Nuclear Information System (INIS)

    Larsen, J.T.; Terry, N.C.

    1985-03-01

    This report contains research progress during this period on each of the following 5 areas: (1) parametric instabilities, (2) cryogenic implosion experiments, (3) x-ray laser experiments, (4) XCALIBR, an effective soft x-ray calibration facility, and (5) DELPHI- a new hydrodynamics code, (6) polymer technology, (7) glass shell technology, (8) shell production facility, (9) cryogenic technology, (10) characterization and quality assurance, and (11) coating technology

  9. Environmental licensing of nuclear facilities: compatibility of technical competencies

    International Nuclear Information System (INIS)

    Shu, J.; Paiva, R.L.C. de; Mezrahi, A.; Cardoso, E.M.; Aquino, W.P.; Deppe, A.L.; Menezes, R.M.; Prado, V.; Franco, N.M.F.L.; Nouailhetas, Y.; Xavier, A.M.

    1996-01-01

    The Brazilian Nuclear Energy Commission (CNEN) has the technical competency for diagnosing environmental radiological impacts, as well as evaluating the safety and requiring adequate control of the facilities which, due to their activities, represent a potential risk of radiological contamination for the environment. The institution is responsible for emission of radioprotection guidelines, controls and surveys in nuclear safety according to the country's regulations and international recommendations. The methodology to assure the limitation of radiation exposure is consequence from shared control over the nuclear activities, in special the nuclear facilities. According to the Federal Constitution of 1988, the nuclear activities must be under exclusive control of the Union in special related to the nuclear policies, economical, laboral and nuclear safety aspects, while the health and environmental controls of these activities are shared by the Federation, Union, States, Federal District and Counties. The controls related to specific aspects have to be harmonized in such a way to be optimized and effective. In this paper the results of compatibilization of nuclear legislation and environmental legislation are presented aiming to optimize the licensing of nuclear facilities. (author)

  10. Technical specifications: Health Physics Research Reactor

    International Nuclear Information System (INIS)

    1979-02-01

    The technical specifications define the key limitations that must be observed for safe operation of the Health Physics Research Reactor (HPRR) and an envelope of operation within which there is assurance that these limits will not be exceeded. The specifications were written to satisfy the requirements of the Department of Energy (DOE) Manual Chapter 0540, September 1, 1972

  11. Development of technical specifications for research reactors

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    This standard identifies and establishes the content of technical specifications for research reactors. Areas addressed are: definitions, safety limits, limiting safety system settings, limiting conditions for operation, surveillance requirements, design features and administrative controls. Sufficient detail is incorporated so that applicable specifications can be derived or extracted

  12. Meson facility. Powerful new research tool

    International Nuclear Information System (INIS)

    Lobashev, V.M.; Tavkhelidze, A.N.

    A meson facility is being built at the Institute of Nuclear Research, USSR Academy of Sciences, in Troitsk, where the Scientific Center, USSR Academy of Sciences is located. The facility will include a linear accelerator for protons and negative hydrogen ions with 600 MeV energy and 0.5-1 mA beam current. Some fundamental studies that can be studied at a meson facility are described in the areas of elementary particles, neutron physics, solid state physics, and applied research. The characteristics of the linear accelerator are given and the meson facility's experimental complex is described

  13. Technical Reports: Langley Aerospace Research Summer Scholars. Part 1

    Science.gov (United States)

    Schwan, Rafaela (Compiler)

    1995-01-01

    The Langley Aerospace Research Summer Scholars (LARSS) Program was established by Dr. Samuel E. Massenberg in 1986. The program has increased from 20 participants in 1986 to 114 participants in 1995. The program is LaRC-unique and is administered by Hampton University. The program was established for the benefit of undergraduate juniors and seniors and first-year graduate students who are pursuing degrees in aeronautical engineering, mechanical engineering, electrical engineering, material science, computer science, atmospheric science, astrophysics, physics, and chemistry. Two primary elements of the LARSS Program are: (1) a research project to be completed by each participant under the supervision of a researcher who will assume the role of a mentor for the summer, and (2) technical lectures by prominent engineers and scientists. Additional elements of this program include tours of LARC wind tunnels, computational facilities, and laboratories. Library and computer facilities will be available for use by the participants.

  14. Access to major overseas research facilities

    International Nuclear Information System (INIS)

    Bolderman, J. W.

    1997-01-01

    This paper will describe four schemes which have been established to permit Australian researchers access to some of the most advanced overseas research facilities. These include, access to Major Research Facilities Program, the Australian National Beamline Facility at the Photon Factory, the Australian Synchrotron Research Program and the ISIS Agreement. The details of each of these programs is discussed and the statistics on the scientific output provided. All programs are managed on behalf of the Department of Industry, Science and Tourism by the Australian Nuclear Science and Technology Organisation. One hundred and thirteen senior scientists plus forty, one postgraduate, students were supported through these schemes during the 1996-1997 financial year

  15. Structural Research Facilities | Wind | NREL

    Science.gov (United States)

    -hydraulic equipment and data acquisition systems tailored for researching composite blades and components 61400-23 standard. General types of rotor blade research performed at the NWTC includes: Property

  16. Interim Storage Facility for LLW of Decommissioning Nuclear Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Amato, S.; Ugolini, D.; Basile, F. [European Commission, Joint Research Centre, Nuclear Decommissioning and Facility Management Unit, TP 800, Via E. Fermi 2749, 21027 Ispra - VA (Italy)

    2009-06-15

    JRC-Ispra has initiated a Decommissioning and Waste Management (D and WM) Programme of all its nuclear facilities. In the frame of this programme, it has been decided to build an interim storage facility to host conditioned low level waste (LLW) that had been produced during the operation of JRC-Ispra nuclear research reactors and laboratories and that will be produced from their decommissioning. This paper presents the main characteristics of the facility. The storage ISFISF has a rectangular shape with uniform height and it is about 128 m long, 41 m wide and 9 m high. The entire surface affected by the facility, including screening area and access roads, is about 27.000 m{sup 2}. It is divided in three sectors, a central one, about 16 m long, for loading/unloading operations and operational services and two lateral sectors, each about 55 m long, for the conditioned LLW storage. Each storage sector is divided by a concrete wall in two transversal compartments. The ISFISF, whose operational lifetime is 50 years, is designed to host the conditioned LLW boxed in UNI CP-5.2 packages, 2,5 m long, 1.65 m wide, and 1,25 m high. The expected nominal inventory of waste is about 2100 packages, while the maximum storage is 2540 packages, thus a considerably large reserve capacity is available. The packages will be piled in stacks of maximum number of five. The LLW is going to be conditioned with a cement matrix. The maximum weight allowed for each package has been fixed at 16.000 kg. The total radioactivity inventory of waste to be hosted in the facility is about 30 TBq (mainly {beta}/{gamma} emitters). In order to satisfy the structural, seismic, and, most of all, radiological requirements, the external walls of the ISFISF are made of pre-fabricated panels, 32 cm thick, consisting of, from inside to outside, 20 cm of reinforced concrete, 7 cm of insulating material, and again 5 cm of reinforced concrete. For the same reason the roof is made with pre-fabricated panels in

  17. Review of Sodium and Plutonium related Technical Standards in Trans-Uranium Fuel Fabrication Facilities

    International Nuclear Information System (INIS)

    Jang, Misuk; Jeon, Jong Seon; Kang, Hyun Sik; Kim, Seoung Rae

    2016-01-01

    In this paper, we would introduce and review technical standards related to sodium fire and plutonium criticality safety. This paper may be helpful to identify considerations in the development of equipment, standards, and etc., to meet the safety requirements in the design, construction and operating of TFFF, KAPF and SFR. The feasibility and conceptual designs are being examined on related facilities, for example, TRU Fuel Fabrication Facilities (TFFF), Korea Advanced Pyro-process Facility (KAPF), and Sodium Cooled Fast Reactor (SFR), in Korea. However, the safety concerns of these facilities have been controversial in part because of the Sodium fire accident and Plutonium related radiation safety caused by transport and handling accident. Thus, many researches have been performed to ensure safety and various documents including safety requirements have been developed. In separating and reducing the long-lived radioactive transuranic(TRU) in the spent nuclear fuel, reusing as the potential energy of uranium fuel resources and reducing the high level wastes, TFFF would be receiving the attention of many people. Thus, people would wonder whether compliance with technical standards that ensures safety. For new facility design, one of the important tasks is to review of technical standards, especially for sodium and Plutonium because of water related highly reactive characteristics and criticality hazard respectively. We have introduced and reviewed two important technical standards for TFFF, which are sodium fire and plutonium criticality safety, in this paper. This paper would provide a brief guidance, about how to start and what is important, to people who are responsible for the initial design to operation of TFFF

  18. Review of Sodium and Plutonium related Technical Standards in Trans-Uranium Fuel Fabrication Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Jang, Misuk; Jeon, Jong Seon; Kang, Hyun Sik; Kim, Seoung Rae [NESS, Daejeon (Korea, Republic of)

    2016-10-15

    In this paper, we would introduce and review technical standards related to sodium fire and plutonium criticality safety. This paper may be helpful to identify considerations in the development of equipment, standards, and etc., to meet the safety requirements in the design, construction and operating of TFFF, KAPF and SFR. The feasibility and conceptual designs are being examined on related facilities, for example, TRU Fuel Fabrication Facilities (TFFF), Korea Advanced Pyro-process Facility (KAPF), and Sodium Cooled Fast Reactor (SFR), in Korea. However, the safety concerns of these facilities have been controversial in part because of the Sodium fire accident and Plutonium related radiation safety caused by transport and handling accident. Thus, many researches have been performed to ensure safety and various documents including safety requirements have been developed. In separating and reducing the long-lived radioactive transuranic(TRU) in the spent nuclear fuel, reusing as the potential energy of uranium fuel resources and reducing the high level wastes, TFFF would be receiving the attention of many people. Thus, people would wonder whether compliance with technical standards that ensures safety. For new facility design, one of the important tasks is to review of technical standards, especially for sodium and Plutonium because of water related highly reactive characteristics and criticality hazard respectively. We have introduced and reviewed two important technical standards for TFFF, which are sodium fire and plutonium criticality safety, in this paper. This paper would provide a brief guidance, about how to start and what is important, to people who are responsible for the initial design to operation of TFFF.

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

    International Nuclear Information System (INIS)

    2013-01-01

    The objectives of the meeting were: - To identify the main issues and technical features that affect capital and energy production costs of fast reactors and related fuel cycle facilities; - To present fast reactor concepts and designs with enhanced economic characteristics, as well as innovative technical solutions (components, subsystems, etc.) that have the potential to reduce the capital costs of fast reactors and related fuel cycle facilities; - To present energy models and advanced tools for the cost assessment of innovative fast reactors and associated nuclear fuel cycles; - To discuss the results of studies and on-going R&D activities that address cost reduction and the future economic competitiveness of fast reactors; and - To identify research and technology development needs in the field, also in view of new IAEA initiatives to help and support Member States in improving the economic competitiveness of fast reactors and associated nuclear fuel cycles

  20. Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics. Presentations

    International Nuclear Information System (INIS)

    2013-01-01

    The objectives of the meeting were: • To identify the main issues and technical features that affect capital and energy production costs of fast reactors and related fuel cycle facilities; • To present fast reactor concepts and designs with enhanced economic characteristics, as well as innovative technical solutions (components, subsystems, etc.) that have the potential to reduce the capital costs of fast reactors and related fuel cycle facilities; • To present energy models and advanced tools for the cost assessment of innovative fast reactors and associated nuclear fuel cycles; • To discuss the results of studies and ongoing R&D activities that address cost reduction and the future economic competitiveness of fast reactors; • To identify research and technology development needs in the field, also in view of new IAEA initiatives to help and support Member States in improving the economic competitiveness of fast reactors and associated nuclear fuel cycles

  1. Researches at hadron experiment facility

    International Nuclear Information System (INIS)

    Sawada, Shinya

    2006-01-01

    Some of the nuclear, hadron and elementary particle experiments proposed to hadron experiment facility to use the extracted slow proton beam at J-PARC are overviewed. Characteristic feature of the facility is the secondary beam obtained from the intense proton beam. Nuclear hadron physics experiments and kaon rare decay experiments are presented here as the typical ones. Hypernuclear spectroscopy with S=-2 state is expected to be started as soon as the beam becomes available. The kaon bound systems not only with three nucleons like K-pnn but also more numerous like Li and Be are to be studied systematically. Bound states of two kaons using (K - , K + ) reaction will be challenged. Pentaquark will be searched for and its properties will be studied if it really exists. Nuclear structure studies from the view point of large Bjorken x are planned to be studied by irradiating hydrogen, deuteron or heavier targets with primary proton beam and analyzing generated muon pairs. Properties of vector mesons in nuclear matter are to be studied with the primary beam. Neutral kaon rare decay will be investigated to study CP nonconservation. Large progress of elementary particle physics is anticipated by using the intense proton beam at J-PARC. (S. Funahashi)

  2. 76 FR 36102 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2011-06-21

    ... vacancies on the Biomass Research and Development Technical Advisory Committee (Technical Advisory Committee..., 2008, H.R. 6124]. FCEA section 9008(d) establishes the Biomass Research and Development Technical... committee are ineligible for nomination. Appointments to the Biomass Research and Development Technical...

  3. 77 FR 42298 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2012-07-18

    ... Biomass Research and Development Technical Advisory Committee (Technical Advisory Committee). DATES: The... 9008(d) established the Biomass Research and Development Technical Advisory Committee and lays forth... nomination. Appointments to the Biomass Research and Development Technical Advisory Committee will be made by...

  4. Independent technical review of Savannah River Site Defense Waste Processing Facility technical issues

    International Nuclear Information System (INIS)

    1992-07-01

    The Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) will vitrify high-level radioactive waste that is presently stored as liquid, salt-cake, and sludge in 51 waste-storage tanks. Construction of the DWPF began in 1984, and the Westinghouse Savannah Company (WSRC) considers the plant to be 100% turned over from construction and 91% complete. Cold-chemical runs are scheduled to begin in November 1992, and hot start up is projected for June 1994. It is estimated that the plant lifetime must exceed 15 years to complete the vitrification of the current, high-level tank waste. In a memo to the Assistant Secretary for Defense Programs (DP-1), the Assistant Secretary for Environmental Restoration and Waste management (EM-1) established the need for an Independent Technical Review (ITR), or the Red Team, to ''review process technology issues preventing start up of the DWPF.'' This report documents the findings of an Independent Technical Review (ITR) conducted by the Department of Energy (DOE), Office of Environmental Restoration and Waste Management (EM), at the request of the Assistant Secretary for Environmental Restoration and Waste Management, of specified aspects of Defense Waste Process Facility (DWPF) process technology. Information for the assessment was drawn from documents provided to the ITR Team by the Westinghouse Savannah River Company (WSRC), and presentations, discussions, interviews, and tours held at the Savannah River Site (SRS) during the weeks of February and March 9, 1992

  5. FAIR - Facility, Research Program and Status of the Project

    International Nuclear Information System (INIS)

    Majka, Z.

    2011-01-01

    The international Facility for Antiproton and Ion Research (FAIR) in Europe will provide a worldwide science community with a unique and technically innovative accelerator system to perform forefront research in the sciences concerned with the basic structure of matter, and in intersections with other fields. The facility will deliver an extensive range of primary and secondary particle beams from protons and their antimatter partners, antiprotons, to ion beams of all chemical elements up to the heaviest, uranium, with in many respects unique properties and intensities. The paper will include overview of the new facility design and research programs to be carried out there. The current status of the FAIR project will be also presented. (author)

  6. Facility management research in the Netherlands

    NARCIS (Netherlands)

    Thijssen, Thomas; van der Voordt, Theo; Mobach, Mark P.

    This article provides a brief overview of the history and development of facility management research in the Netherlands and indicates future directions. Facility management as a profession has developed from single service to multi-services and integral services over the past 15 years.

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

    DEFF Research Database (Denmark)

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

    2005-01-01

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

  8. Flood Fighting Products Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — A wave research basin at the ERDC Coastal and Hydraulics Laboratory has been modified specifically for testing of temporary, barrier-type, flood fighting products....

  9. Zero Gravity Research Facility (Zero-G)

    Data.gov (United States)

    Federal Laboratory Consortium — The Zero Gravity Research Facility (Zero-G) provides a near weightless or microgravity environment for a duration of 5.18 seconds. This is accomplished by allowing...

  10. Research Projects, Technical Reports and Publications

    Science.gov (United States)

    Oliger, Joseph

    1996-01-01

    The Research Institute for Advanced Computer Science (RIACS) was established by the Universities Space Research Association (USRA) at the NASA Ames Research Center (ARC) on June 6, 1983. RIACS is privately operated by USRA, a consortium of universities with research programs in the aerospace sciences, under contract with NASA. The primary mission of RIACS is to provide research and expertise in computer science and scientific computing to support the scientific missions of NASA ARC. The research carried out at RIACS must change its emphasis from year to year in response to NASA ARC's changing needs and technological opportunities. A flexible scientific staff is provided through a university faculty visitor program, a post doctoral program, and a student visitor program. Not only does this provide appropriate expertise but it also introduces scientists outside of NASA to NASA problems. A small group of core RIACS staff provides continuity and interacts with an ARC technical monitor and scientific advisory group to determine the RIACS mission. RIACS activities are reviewed and monitored by a USRA advisory council and ARC technical monitor. Research at RIACS is currently being done in the following areas: Advanced Methods for Scientific Computing High Performance Networks During this report pefiod Professor Antony Jameson of Princeton University, Professor Wei-Pai Tang of the University of Waterloo, Professor Marsha Berger of New York University, Professor Tony Chan of UCLA, Associate Professor David Zingg of University of Toronto, Canada and Assistant Professor Andrew Sohn of New Jersey Institute of Technology have been visiting RIACS. January 1, 1996 through September 30, 1996 RIACS had three staff scientists, four visiting scientists, one post-doctoral scientist, three consultants, two research associates and one research assistant. RIACS held a joint workshop with Code 1 29-30 July 1996. The workshop was held to discuss needs and opportunities in basic research in

  11. Exploration and thinking of dynamic scientific and technical intelligence research

    International Nuclear Information System (INIS)

    Zhang Xupu; Xia Yun

    2014-01-01

    This article discusses the concept and types of dynamic scientific and technical intelligence, describes the characteristics and role of dynamic scientific and technical intelligence, and analyzes methods and procedures of dynamic scientific and technical intelligence research. Combined with the status quo of dynamic scientific and technical intelligence research in library of China Institute of Atomic Energy, this article makes some suggestions for strengthening dynamic scientific and technical intelligence research. (authors)

  12. Research and research impact of a technical university

    DEFF Research Database (Denmark)

    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...

  13. Identification of Vital Areas at Nuclear Facilities. Technical Guidance

    International Nuclear Information System (INIS)

    2012-01-01

    The possibility that nuclear or other radioactive material could be used for malicious purposes cannot be ruled out in the current global situation. States have responded to this risk by engaging in a collective commitment to strengthen the protection and control of such material and to effectively respond to nuclear security events. States have agreed to strengthen existing and established new international legal instruments to enhance nuclear security around the world. Nuclear security is fundamental in the management of nuclear technologies and in applications where nuclear or other radioactive material is used or transported. Through its nuclear security programme, the IAEA supports States to establish, maintain and sustain an effective nuclear security regime. The IAEA has adopted a comprehensive approach to nuclear security. This recognizes that an effective national nuclear security regime builds on: the implementation of relevant international legal instruments; information protection; physical protection; material accounting and control; detection of and response to trafficking in such material; national response plans; and contingency measures. With its nuclear security series, the IAEA aims to assist States to implement and sustain such a regime in a coherent and integrated manner. The IAEA Nuclear Security Series comprises: Nuclear Security Fundamentals, which include objectives and essential elements of a State?s nuclear security regime; Recommendations; Implementing Guides; and Technical Guidance publications. Each State carries the full responsibility for nuclear security, i.e. to provide for the security of nuclear and other radioactive material and associated facilities and activities; to ensure the security of such material in use, storage or in transport; and to combat illicit trafficking and the inadvertent movement of such material. It should also be prepared to respond to a nuclear security event. The IAEA recommendations for the protection of

  14. Accelerator technical design report for high-intensity proton accelerator facility project, J-PARC

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-03-01

    This report presents the detail of the technical design of the accelerators for the High-Intensity Proton Accelerator Facility Project, J-PARC. The accelerator complex comprises a 400-MeV room-temperature linac (600-MeV superconducting linac), 3-GeV rapid-cycling synchrotron (RCS), and a 50-GeV synchrotron (MR). The 400-MeV beam is injected to the RCS, being accelerated to 3 GEV. The 1-MW beam thus produced is guided to the Materials Life Science Experimental Facility, with both the pulsed spallation neutron source and muon source. A part of the beam is transported to the MR, which provides the 0.75-MW beam to either the Nuclear and Fundamental Particle Experimental Facility or the Neutrino Production Target. On the other hand, the beam accelerated to 600 MeV by the superconducting linac is used for the Nuclear Waster Transmutation Experiment. In this way, this facility is unique, being multipurpose one, including many new inventions and Research and Development Results. This report is based upon the accomplishments made by the Accelerator Group and others of the Project Team, which is organized on the basis of the Agreement between JAERI and KEK on the Construction and Research and Development of the High-Intensity Proton Accelerator Facility. (author)

  15. 77 FR 20377 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2012-04-04

    ... Biomass Research and Development Technical Advisory Committee under Section 9008(d) of the Food... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy Biomass Research and Development Technical Advisory Committee AGENCY: Office of Energy Efficiency and Renewable Energy, Department...

  16. Qualification and actuation of the independent technical supervision organisms in nuclear power plants and others facilities

    International Nuclear Information System (INIS)

    1999-09-01

    This norm presents the following objectives: establishment of the Brazilian National Nuclear Energy Commission requirements for qualifying an institution as independent technical supervision organization, in a specific area of activity related to nuclear power plants and others nuclear or radioactive facilities as appropriated; regulation of the independent technical supervision and others complementary activities to be executed by an independent technical supervision organism

  17. Access to major overseas research facilities

    Energy Technology Data Exchange (ETDEWEB)

    Bolderman, J. W. [Australian Nuclear Science and Technology Organisation, Lucas Heights, NSW (Australia)

    1997-12-31

    This paper will describe four schemes which have been established to permit Australian researchers access to some of the most advanced overseas research facilities. These include, access to Major Research Facilities Program, the Australian National Beamline Facility at the Photon Factory, the Australian Synchrotron Research Program and the ISIS Agreement. The details of each of these programs is discussed and the statistics on the scientific output provided. All programs are managed on behalf of the Department of Industry, Science and Tourism by the Australian Nuclear Science and Technology Organisation. One hundred and thirteen senior scientists plus forty, one postgraduate, students were supported through these schemes during the 1996-1997 financial year. 1 fig.

  18. Unlocking investment in cities: ELENA-EIB technical assistance facility

    International Nuclear Information System (INIS)

    Cicmanova, Jana; Garabetian, Thomas

    2015-06-01

    Energy Cities prepared a review of projects undertaken in the cities of Paris, Malmoe (in association with Lund and Helsingborg), Barcelona, Bristol and Brussels-Capital that received support from the ELENA-EIB facility. The aim of this study is to identify the ways in which technical assistance programs such as ELENA-EIB can help unlock investment in cities. The projects we reviewed (developed by Energy Cities' members) cover a wide array of sectors, from public building refurbishment to public transport or renewable energy production. These five projects illustrate how cities can focus on developing capacity in a long-term perspective, looking at the expected benefits of an investment or a support mechanism beyond that of the project itself. Overall, we found that project development assistance mechanisms such as ELENA can be beneficial to trigger investment for climate action in cities. Cities maximise the benefits of such a program by looking at how their climate-protection actions can generate benefits for the citizens, or how to systematically integrate climate action in other investment projects. Project development assistance (PDA) affects cities by allowing them to develop a new vision of the way they prepare an investment program. The search of synergies and the override of silo mentalities were a core element in the projects we reviewed. Indeed, the support provided by the European Union through ELENA-EIB is used by the local authorities to develop a transversal approach to climate action. The grant provided for PDA and the requirements of the ELENA-EIB facility represent an opportunity for local authorities to set up a new strategy regarding energy efficiency and renewable energy actions. It can be the necessary push for cities and local authorities to change the way they plan their investments, and develop projects to achieve their climate objectives. Besides, the grant is used for building long-term capacity in the development of investment programs

  19. 75 FR 30804 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2010-06-02

    ... DEPARTMENT OF ENERGY Biomass Research and Development Technical Advisory Committee AGENCY.... SUMMARY: This notice announces an open meeting of the Biomass Research and Development Technical Advisory... public are welcome to observe the business of the Biomass Research and Development Technical Advisory...

  20. 75 FR 11526 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2010-03-11

    ... DEPARTMENT OF ENERGY Biomass Research and Development Technical Advisory Committee AGENCY.... SUMMARY: This notice announces an open meeting of the Biomass Research and Development Technical Advisory... public are welcome to observe the business of the Biomass Research and Development Technical Advisory...

  1. 78 FR 64932 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2013-10-30

    ... DEPARTMENT OF ENERGY Biomass Research and Development Technical Advisory Committee AGENCY: Energy... announces an open meeting of the Biomass Research and Development Technical Advisory Committee under Section... Biomass Research and Development Technical Advisory Committee. To attend the meeting and/or to make oral...

  2. 75 FR 56525 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2010-09-16

    ... DEPARTMENT OF ENERGY Biomass Research and Development Technical Advisory Committee AGENCY.... SUMMARY: This notice announces an open meeting of the Biomass Research and Development Technical Advisory... business of the Biomass Research and Development Technical Advisory Committee. To attend the meeting and/or...

  3. Technical report from Radioactive Waste Management Funding and Research Center

    International Nuclear Information System (INIS)

    2007-10-01

    As the only one Japanese organization specialized in radioactive waste, RWMC (Radioactive Waste Management Funding and Research Center) has been conducting the two major roles; R and D and the fund administration for radioactive waste management. The focus of its studies includes land disposal of LLW (Low-level radioactive wastes) and it has gradually extended to research on management and disposal techniques for high-level (HLW) and TRU wastes and studies on securing and managing the funds required for disposal of these wastes. The present document is the yearly progress report of 2006 and the main activities and research results are included on spent fuel disposal techniques including radon diffusion and emanation problem, performance studies on underground facilities for radioactive waste disposal and its management, technical assessment for geological environment, remote control techniques, artificial barrier systems proposed and its monitoring systems, and TRU disposals. (S. Ohno)

  4. The Sanford underground research facility at Homestake

    International Nuclear Information System (INIS)

    Heise, J.

    2014-01-01

    The former Homestake gold mine in Lead, South Dakota is being transformed into a dedicated laboratory to pursue underground research in rare-process physics, as well as offering research opportunities in other disciplines such as biology, geology and engineering. A key component of the Sanford Underground Research Facility (SURF) is the Davis Campus, which is in operation at the 4850-foot level (4300 m.w.e) and currently hosts three projects: the LUX dark matter experiment, the MAJORANA DEMONSTRATOR neutrinoless double-beta decay experiment and the CUBED low-background counter. Plans for possible future experiments at SURF are well underway and include long baseline neutrino oscillation experiments, future dark matter experiments as well as nuclear astrophysics accelerators. Facility upgrades to accommodate some of these future projects have already started. SURF is a dedicated facility with significant expansion capability

  5. Decommissioning of small medical, industrial and research facilities

    International Nuclear Information System (INIS)

    2003-01-01

    Most of the technical literature on decommissioning addresses the regulatory, organizational, technical and other aspects for large facilities such as nuclear power plants, reprocessing plants and relatively large prototype, research and test reactors. There are, however, a much larger number of licensed users of radioactive material in the fields of medicine, research and industry. Most of these nuclear facilities are smaller in size and complexity and may present a lower radiological risk during their decommissioning. Such facilities are located at research establishments, biological and medical laboratories, universities, medical centres, and industrial and manufacturing premises. They are often operated by users who have not been trained or are unfamiliar with the decommissioning, waste management and associated safety aspects of these types of facility at the end of their operating lives. Also, for many small users of radioactive material such as radiation sources, nuclear applications are a small part of the overall business or process and, although the operating safety requirements may be adhered to, concern or responsibility may not go much beyond this. There is concern that even the minimum requirements of decommissioning may be disregarded, resulting in avoidable delays, risks and safety implications (e.g. a loss of radioactive material and a loss of all records). Incidents have occurred in which persons have been injured or put at risk. It is recognized that the strategies and specific requirements for small facilities may be much less onerous than for large ones such as nuclear power plants or fuel processing facilities, but many of the same principles apply. There has been considerable attention given to nuclear facilities and many IAEA publications are complementary to this report. This report, however, attempts to give specific guidance for small facilities. 'Small' in this report does not necessarily mean small in size but generally modest in terms

  6. Multi-beam Mossbauer scattering facility. Final technical report

    International Nuclear Information System (INIS)

    1994-01-01

    The Mossbauer instrument construction which was financed by the DOE grant of $74,065 and MU matching funds of $52,000 is essentially completed and awaiting installation at the Missouri University Research Reactor (MURR) facility. All of the DOE funds have been spent and all of the matching funds plus about $4,000 to $5,000 of additional physics department funds have been committed to finishing the first phase of the new instrument, QUEGS--II (for QUAsiElastic Gamma-ray Scattering--generation II). This phase includes computer controls, detectors, and instrumentation for two of the four beam lines afforded by QUEGS-II. Included in this commitment of funds is $8,700 for equipment and machine shop services which have not yet been paid and $19,700 for a Ge detector for which bids are ready to be let

  7. Research on technical trading and market efficiency : a trader's perspective

    OpenAIRE

    Vico-Ivanina, Julianna V.

    2012-01-01

    Research on the predictive power of technical analysis is a matter of controversy. The objective of this thesis is to look at the empirical research done on technical trading and see how the results can be used from a trader’s perspective. Some results provide strong support for the technical trading and propose useful trading strategies. However, there are some limitations regarding transaction costs, risk adjustment, and statistical tests. Technical research has developed new methodology ap...

  8. Ministry of ordinance determining the technical standard concerning atomic energy facilities for power generation

    International Nuclear Information System (INIS)

    1985-01-01

    The ministerial ordinance provides for the technical standards for the power generation of nuclear facilities; i.e., electric power facilities generating electricity with nuclear energy for motive power, according to the Electricity Enterprises Act. The contents are as follows: protection against fires, aseismatic design, radiation protective barriers, structural protection for sitings, reactor installation, safety measures, materials and structures, safety valves, pressure resistance tests, reactor core, radiation shields, reactor cooling, emergency core cooling system, facility equipment, alarm system, reactor control system, reactor control room, fuel storage facility, fuel handling facility, ventilation equipment, radioactive contamination prevention, radioactive waste management facility, reactor containment facility, and so on. (Kubozono, M.)

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

    International Nuclear Information System (INIS)

    2013-01-01

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

  10. Research activities by INS cyclotron facility

    International Nuclear Information System (INIS)

    1992-06-01

    Research activities made by the cyclotron facility and the related apparatuses at Institute for Nuclear Study (INS), University of Tokyo, have been reviewed in terms of the associated scientific publications. This publication list, which is to be read as a continuation of INS-Rep.-608 (October, 1986), includes experimental works on low-energy nuclear physics, accelerator technology, instrumental developments, radiation physics and other applications in interdisciplinary fields. The publications are classified into the following four categories. (A) : Internal reports published in INS. (B) : Publications in international scientific journals on experimental research works done by the cyclotron facility and the related apparatuses at INS. Those made by outside users are also included. (C) : Publications in international scientific journals on experimental low-energy nuclear physics, which have been done by the staff of INS Nuclear Physics Division using facilities outside INS. (D) : Contributions to international conferences. (author)

  11. The Roles of Technical Communication Researchers in Design Scholarship

    Science.gov (United States)

    Sánchez, Fernando

    2017-01-01

    Design has come to be understood as an essential aspect of the work that technical communicators claim. As a result, research in the field of technical communication has approached studies of design in numerous ways. This article showcases how technical communication researchers assume the roles of observers, testers, critics, creators, and…

  12. Facilities Management research in the Nordic Countries

    DEFF Research Database (Denmark)

    Jensen, Per Anker

    2011-01-01

    to the establishment of the Centre for Facilities Management – Realdania Research (CFM), and updated information from keynote contributions to CFM’s Nordic FM Conference on 22-23 August 2011 by Suvi Nenonen (Finland), Jan Bröchner (Sweden), Geir K Hansen (Norway) and Per Anker Jensen (Denmark)....

  13. CLOUD: an atmospheric research facility at CERN

    OpenAIRE

    The Cloud Collaboration

    2001-01-01

    This report is the second of two addenda to the CLOUD proposal at CERN (physics/0104048), which aims to test experimentally the existence a link between cosmic rays and cloud formation, and to understand the microphysical mechanism. The document places CLOUD in the framework of a CERN facility for atmospheric research, and provides further details on the particle beam requirements.

  14. The Sanford Underground Research Facility at Homestake

    International Nuclear Information System (INIS)

    Heise, J.

    2015-01-01

    The former Homestake gold mine in Lead, South Dakota, has been transformed into a dedicated facility to pursue underground research in rare-process physics, as well as offering research opportunities in other disciplines such as biology, geology and engineering. A key component of the Sanford Underground Research Facility (SURF) is the Davis Campus, which is in operation at the 4850-foot level (4300 m.w.e.) and currently hosts two main physics projects: the LUX dark matter experiment and the MAJORANA DEMONSTRATOR neutrinoless double-beta decay experiment. In addition, two low-background counters currently operate at the Davis Campus in support of current and future experiments. Expansion of the underground laboratory space is underway at the 4850L Ross Campus in order to maintain and enhance low-background assay capabilities as well as to host a unique nuclear astrophysics accelerator facility. Plans to accommodate other future experiments at SURF are also underway and include the next generation of direct-search dark matter experiments and the Fermilab-led international long-baseline neutrino program. Planning to understand the infrastructure developments necessary to accommodate these future projects is well advanced and in some cases have already started. SURF is a dedicated research facility with significant expansion capability

  15. The Sanford Underground Research Facility at Homestake

    International Nuclear Information System (INIS)

    Heise, J

    2015-01-01

    The former Homestakegold mine in Lead, South Dakota has been transformed into a dedicated facility to pursue underground research in rare-process physics, as well as offering research opportunities in other disciplines such as biology, geology and engineering. A key component of the Sanford Underground Research Facility (SURF) is the Davis Campus, which is in operation at the 4850-foot level (4300 m.w.e.) and currently hosts two main physics projects: the LUX dark matter experiment and the MAJORANA DEMONSTRATOR neutrinolessdouble-beta decay experiment. In addition, two low-background counters currently operate at the Davis Campus in support of current and future experiments. Expansion of the underground laboratory space is underway at the 4850L Ross Campus in order to maintain and enhance low- background assay capabilities as well as to host a unique nuclear astrophysics accelerator facility. Plans to accommodate other future experiments at SURF are also underway and include the next generation of direct-search dark matter experiments and the Fermilab-led international long- baseline neutrino program. Planning to understand the infrastructure developments necessary to accommodate these future projects is well advanced and in some cases have already started. SURF is a dedicated research facility with significant expansion capability. (paper)

  16. Lead Coolant Test Facility Technical and Functional Requirements, Conceptual Design, Cost and Construction Schedule

    International Nuclear Information System (INIS)

    Soli T. Khericha

    2006-01-01

    This report presents preliminary technical and functional requirements (T and FR), thermal hydraulic design and cost estimate for a lead coolant test facility. The purpose of this small scale facility is to simulate lead coolant fast reactor (LFR) coolant flow in an open lattice geometry core using seven electrical rods and liquid lead or lead-bismuth eutectic. Based on review of current world lead or lead-bismuth test facilities and research need listed in the Generation IV Roadmap, five broad areas of requirements of basis are identified: Develop and Demonstrate Prototype Lead/Lead-Bismuth Liquid Metal Flow Loop Develop and Demonstrate Feasibility of Submerged Heat Exchanger Develop and Demonstrate Open-lattice Flow in Electrically Heated Core Develop and Demonstrate Chemistry Control Demonstrate Safe Operation and Provision for Future Testing. These five broad areas are divided into twenty-one (21) specific requirements ranging from coolant temperature to design lifetime. An overview of project engineering requirements, design requirements, QA and environmental requirements are also presented. The purpose of this T and FRs is to focus the lead fast reactor community domestically on the requirements for the next unique state of the art test facility. The facility thermal hydraulic design is based on the maximum simulated core power using seven electrical heater rods of 420 kW; average linear heat generation rate of 300 W/cm. The core inlet temperature for liquid lead or Pb/Bi eutectic is 420 C. The design includes approximately seventy-five data measurements such as pressure, temperature, and flow rates. The preliminary estimated cost of construction of the facility is $3.7M. It is also estimated that the facility will require two years to be constructed and ready for operation

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

    International Nuclear Information System (INIS)

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

    1997-03-01

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

  18. Unique life sciences research facilities at NASA Ames Research Center

    Science.gov (United States)

    Mulenburg, G. M.; Vasques, M.; Caldwell, W. F.; Tucker, J.

    1994-01-01

    The Life Science Division at NASA's Ames Research Center has a suite of specialized facilities that enable scientists to study the effects of gravity on living systems. This paper describes some of these facilities and their use in research. Seven centrifuges, each with its own unique abilities, allow testing of a variety of parameters on test subjects ranging from single cells through hardware to humans. The Vestibular Research Facility allows the study of both centrifugation and linear acceleration on animals and humans. The Biocomputation Center uses computers for 3D reconstruction of physiological systems, and interactive research tools for virtual reality modeling. Psycophysiological, cardiovascular, exercise physiology, and biomechanical studies are conducted in the 12 bed Human Research Facility and samples are analyzed in the certified Central Clinical Laboratory and other laboratories at Ames. Human bedrest, water immersion and lower body negative pressure equipment are also available to study physiological changes associated with weightlessness. These and other weightlessness models are used in specialized laboratories for the study of basic physiological mechanisms, metabolism and cell biology. Visual-motor performance, perception, and adaptation are studied using ground-based models as well as short term weightlessness experiments (parabolic flights). The unique combination of Life Science research facilities, laboratories, and equipment at Ames Research Center are described in detail in relation to their research contributions.

  19. Holifield Heavy Ion Research Facility: Users handbook

    International Nuclear Information System (INIS)

    Auble, R.L.

    1987-01-01

    The primary objective of this handbook is to provide information for those who plan to carry out research programs at the Holifield Heavy Ion Research Facility (HHIRF) at Oak Ridge National Laboratory. The accelerator systems and experimental apparatus available are described. The mechanism for obtaining accelerator time and the responsibilities of those users who are granted accelerator time are described. The names and phone numbers of ORNL personnel to call for information about specific areas are given

  20. Characterization of BIPV(T) applications in research facility ‘SOLARBEAT’

    NARCIS (Netherlands)

    Valckenborg, R.M.E.; Hensen, J.L.M.; Folkerts, W.; Vries, de A.

    2015-01-01

    The SolarBEAT facility is an outdoor Research & Development infrastructure for innovation on BIPV(T). The facility is a cooperation between SEAC and the Technical University Eindhoven and is located in the Netherlands. It has been founded early 2014 and has grown rapidly to its full capacity at the

  1. Technical, economic and institutional aspects of regional spent fuel storage facilities

    International Nuclear Information System (INIS)

    2005-11-01

    A particular challenge facing countries with small nuclear programmes is the preparation for extended interim storage and then disposal of their spent nuclear fuel. The costs and complications of providing for away-from-reactor storage facilities and/or geological repositories for relatively small amounts of spent fuel may be prohibitively high, motivating interest in regional solutions. This publication addresses the technical, economic and institutional aspects of regional spent fuel storage facilities (RSFSF) and is based on the results of a series of meetings on this topic with participants from IAEA Member States. Topics discussed include safety criteria and standards, safeguards and physical protection, fuel acceptance criteria, long term stability of systems and stored fuel, selection of site, infrastructure aspects, storage technology, licensing, operations, transport, decommissioning, as well as research and development. Furthermore the publication comprises economic, financial and institutional considerations including organizations and legal aspects followed by political and public acceptance and ethical considerations. Approaches and processes for implementation are discussed, as well as the overall benefits and risks of implementing a regional facility. It is illustrated that implementing a RSFSF facility would involve simultaneously addressing a wide range of diverse challenges. The appendix to this report tabulates the numerous issues that have been touched upon in the study. It appears, however, from the discussions that the challenges can in principle be met; the RSFSF concept is technically feasible and potentially economically viable. The technical committees producing this report did not identify any obvious institutional deficiencies that would prevent completion of such a project. Storing spent fuel in a few safe, reliable, secure facilities could enhance safeguards, physical protection and non-proliferation benefits. The committee also

  2. The training and research reactor of the Zittau Technical College

    International Nuclear Information System (INIS)

    Ackermann, G.; Hampel, R.; Konschak, K.

    1979-01-01

    The light-water moderated training and research reactor of the Zittau Technical College, which has been put into operation 1 July 1979, is described. Having a power of 10 MW, it is provided for education of students and advanced training of nuclear power plant staff members. High inherent nuclear safety and economy of operation are achieved by appropriate design of the reactor core and the use of fresh fuel elements provided for the 10-MW research reactor at the Rossendorf Central Institute for Nucleear Research for one year on a loan basis. Further characteristics of the reactor are easy accessibility of the core interior for in-core studies, sufficient external experimental channels, and a control and protection system meeting the requirements of teaching operation. The installed technological and dosimetric devices not only ensure reliable operation of the reactor, but also extend the potentialities of experimental work and education that is reported in detail. The principles on which the training programs are based are explained in the light of some examples. The training reactor is assumed to serve for providing basic knowledge about processes in nuclear power stations with pressurized water reactors. Where the behaviour of a nuclear power station cannot sufficiently be demonstrated by the training reactor, a reasonable completion of practical training at special simulation models and experimental facilities of the Technical College and at the nuclear power plant simulator of the Rheinsberg nuclear power plant school has been conceived. (author)

  3. Nanotechnology on a dime: building affordable research facilities

    Science.gov (United States)

    DiBattista, Jeff; Clare, Donna; Lynch, David

    2005-08-01

    Designing buildings to house nanotechnology research presents a multitude of well-recognized challenges to architectural and engineering design teams, from environmental control to spatial arrangements to operational functionality. These technical challenges can be solved with relative ease on projects with large budgets: designers have the option of selecting leading-edge systems without undue regard for their expense. This is reflected in the construction cost of many nanotechnology research facilities that run well into the hundreds of millions of dollars. Smaller universities and other institutions need not be shut out of the nanotechnology research field simply because their construction budgets are tens of millions of dollars or less. The key to success for these less expensive projects lies with making good strategic decisions: identifying priorities for the facility in terms of what it will is--and will not--provide to the researchers. Making these strategic decisions puts bounds on the tactical, technical problems that the design team at large must address, allowing them to focus their efforts on the key areas for success. The process and challenges of this strategic decision-making process are examined, with emphasis placed on the types of decisions that must be made and the factors that must be considered when making them. Case study examples of projects undertaken at the University of Alberta are used to illustrate how strategic-level decision-making sets the stage for cutting-edge success on a modest budget.

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

    International Nuclear Information System (INIS)

    2001-01-01

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

  5. methodological and technical aspects to be considered in the location of physical recreational sports facilities

    Directory of Open Access Journals (Sweden)

    Jesús I. Benítez Llanes

    2012-03-01

    Full Text Available Sometimes we wonder. Why practitioners of recreational physical activities do not make systematic use of a particular sports facility ?, Why some sports facility remains almost always empty? Why it is continued unnecessarily reversed large sums of material resources for maintenance? For the simple reason that sports facilities were from the beginning that were not well conceived and designed architecturally, where among other things, not sporting habits and population size of the place properly examined. Similarly, we have witnessed criteria issued regarding the performance of a specific sports field, far from contributing to the extension and improvement of the practice of recreational physical and sports activities in its various manifestations, its null or poor continuous maintenance contributing negatively to limit the sporting life and lacerate mental and physical welfare of the inhabitants of the environment. Justifications that led the author of this research to the development of methodological technical aspects regarding the location of recreational physical sports infrastructure, content which also form part of the subject and / or curricular unit "Spaces and Sports Facilities" currently teaches future professionals and managers of Physical Culture for the last two academic years at the University of the Sciences of Physical Culture and Sport Nancy Uranga Romagoza in Pinar del Río Cuba and the Iberoamerican University of Sport in Venezuela.

  6. The technological study on the decommissioning of nuclear facility, etc. in the Tokai Research Establishment

    International Nuclear Information System (INIS)

    Tomii, Hiroyuki; Matsuo, Kiyoshi; Shiraishi, Kunio; Kato, Rokuro; Watabe, Kozou; Higashiyama, Yutaka; Nagane, Satoru

    2005-03-01

    Since JPDR is dismantled and is removed, in Tokai Research Establishment, Japan Atomic Energy Research Institute, the dismantling of nuclear facility which finished the mission, etc. is advanced. At present, nuclear facility as a dismantling object count the approximately 20 facilities, and decommissioning plan of these facilities becomes an important problem, when the decommissioning countermeasure is considered. However, decommissioning techniques in proportion to various nuclear facility, etc. are clearly, and it has not been determined. In this report, the technical consideration on decommissioning techniques of nuclear facility promoted on the basis of this experience in future, while until now decommissioning experience and technical knowledge are arranged, etc. was added in order to appropriately and surely carry out decommissioning techniques and legal procedures, etc. (author)

  7. Lewis Research Center R and D Facilities

    Science.gov (United States)

    1991-01-01

    The NASA Lewis Research Center (LeRC) defines and develops advanced technology for high priority national needs. The work of the Center is directed toward new propulsion, power, and communications technologies for application to aeronautics and space, so that U.S. leadership in these areas is ensured. The end product is knowledge, usually in a report, that is made fully available to potential users--the aircraft engine industry, the energy industry, the automotive industry, the space industry, and other NASA centers. In addition to offices and laboratories for almost every kind of physical research in such fields as fluid mechanics, physics, materials, fuels, combustion, thermodynamics, lubrication, heat transfer, and electronics, LeRC has a variety of engineering test cells for experiments with components such as compressors, pumps, conductors, turbines, nozzles, and controls. A number of large facilities can simulate the operating environment for a complete system: altitude chambers for aircraft engines; large supersonic wind tunnels for advanced airframes and propulsion systems; space simulation chambers for electric rockets or spacecraft; and a 420-foot-deep zero-gravity facility for microgravity experiments. Some problems are amenable to detection and solution only in the complete system and at essentially full scale. By combining basic research in pertinent disciplines and generic technologies with applied research on components and complete systems, LeRC has become one of the most productive centers in its field in the world. This brochure describes a number of the facilities that provide LeRC with its exceptional capabilities.

  8. Research and education by SF cyclotron facility

    International Nuclear Information System (INIS)

    1992-04-01

    This report represents the current activities in research and education using the cyclotron facility and related apparatus which are supported by Nuclear Physics Division and this is a continuation of INS-T-466 (1986, December). In this version an iron-free β-ray spectrometer and a cooler-synchrotron (TARN II) are briefly described also in the first chapter. The second chapter explains experimental programs performed in the last 5 years. The third chapter gives the number of publications on researches performed in 1975-1991, and also gives twelve topics obtained from the cyclotron and the β-ray spectrometer in recent 5 years. The last chapter provides the whole list of the works for Doctor and Master theses performed at the facility in the last 10 years. (J.P.N.)

  9. Thermal fuel research and development facilities in BNFL

    International Nuclear Information System (INIS)

    Roberts, V.A.; Vickers, J.

    1996-01-01

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

  10. Scientific and technical information output of the Langley Research Center

    Science.gov (United States)

    1984-01-01

    Scientific and technical information that the Langley Research Center produced during the calendar year 1983 is compiled. Included are citations for Formal Reports, Quick-Release Technical Memorandums, Contractor Reports, Journal Articles and other Publications, Meeting Presentations, Technical Talks, Computer Programs, Tech Briefs, and Patents.

  11. A US Based Ultrafast Interdisciplinary Research Facility

    Science.gov (United States)

    Gueye, Paul; Hill, Wendell; Johnson, Anthony

    2006-10-01

    The US scientific competitiveness on the world arena has substantially decreased due to the lack of funding and training of qualified personnel. Most of the potential workforce found in higher education is composed of foreign students and post-docs. In the specific field of low- and high-field science, the European and Asian communities are rapidly catching-up with the US, even leading in some areas. To remain the leader in ultrafast science and technology, new visions and commitment must be embraced. For that reason, an international effort of more than 70 countries for a US-based interdisciplinary research facility using ultrafast laser technology is under development. It will provide research and educational training, as well as new venues for a strong collaboration between the fields of astrophysics, nuclear/high energy physics, plasma physics, optical sciences, biological and medical physics. This facility will consist of a uniquely designed high contrast multi-lines concept housing twenty experimental rooms shared between four beams:[0.1 TW, 1 kHz], [10 TW, 9 kHz], [100-200 TW, 10 Hz] and [500 TW, 10 Hz]. The detail schematic of this multi-laser system, foreseen research and educational programs, and organizational structure of this facility will be presented.

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

    International Nuclear Information System (INIS)

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

    1985-01-01

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

  13. Operating large controlled thermonuclear fusion research facilities

    International Nuclear Information System (INIS)

    Gaudreau, M.P.J.; Tarrh, J.M.; Post, R.S.; Thomas, P.

    1987-01-01

    The MIT Tara Tandem Mirror is a large, state of the art controlled thermonuclear fusion research facility. Over the six years of its design, implementation, and operation, every effort was made to minimize cost and maximize performance by using the best and latest hardware, software, and scientific and operational techniques. After reviewing all major DOE fusion facilities, an independent DOE review committee concluded that the Tara operation was the most automated and efficient of all DOE facilities. This paper includes a review of the key elements of the Tara design, construction, operation, management, physics milestones, and funding that led to this success. The authors emphasize a chronological description of how the system evolved from the proposal stage to a mature device with an emphasis on the basic philosophies behind the implementation process. This description can serve both as a qualitative and quantitative database for future large experiment planning. It includes actual final costs and manpower spent as well as actual run and maintenance schedules, number of data shots, major system failures, etc. The paper concludes with recommendations for the next generation of facilities

  14. Operating large controlled thermonuclear fusion research facilities

    International Nuclear Information System (INIS)

    Gaudreau, M.P.J.; Tarrh, J.M.; Post, R.S.; Thomas, P.

    1987-10-01

    The MIT Tara Tandem Mirror is a large, state of the art controlled thermonuclear fusion research facility. Over the six years of its design, implementation, and operation, every effort was made to minimize cost and maximize performance by using the best and latest hardware, software, and scientific and operational techniques. After reviewing all major DOE fusion facilities, an independent DOE review committee concluded that the Tara operation was the most automated and efficient of all DOE facilities. This paper includes a review of the key elements of the Tara design, construction, operation, management, physics milestones, and funding that led to this success. We emphasize a chronological description of how the system evolved from the proposal stage to a mature device with an emphasis on the basic philosophies behind the implementation process. This description can serve both as a qualitative and quantitative database for future large experiment planning. It includes actual final costs and manpower spent as well as actual run and maintenance schedules, number of data shots, major system failures, etc. The paper concludes with recommendations for the next generation of facilities. 13 refs., 15 figs., 3 tabs

  15. 78 FR 46331 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2013-07-31

    ... DEPARTMENT OF ENERGY Biomass Research and Development Technical Advisory Committee AGENCY: Energy.... Appointments to the Biomass Research and Development Technical Advisory Committee will be made by the Secretary... Energy is soliciting nominations for candidates to fill vacancies on the Biomass Research and Development...

  16. 77 FR 64970 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2012-10-24

    ... Biomass Research and Development Technical Advisory Committee. The Federal Advisory Committee Act (Pub. L... observe the business of the Biomass Research and Development Technical Advisory Committee. To attend the... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy Biomass Research and...

  17. 78 FR 29125 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2013-05-17

    ... Biomass Research and Development Technical Advisory Committee. The Federal Advisory Committee Act (Pub. L... public are welcome to observe the business of the Biomass Research and Development Technical Advisory... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy Biomass Research and...

  18. Performance of simulated flexible integrated gasification polygeneration facilities. Part A: A technical-energetic assessment

    NARCIS (Netherlands)

    Meerman, J.C.; Ramírez Ramírez, C.A.; Turkenburg, W.C.; Faaij, A.P.C.

    2011-01-01

    This article investigates technical possibilities and performances of flexible integrated gasification polygeneration (IG-PG) facilities equipped with CO2 capture for the near future. These facilities can produce electricity during peak hours, while switching to the production of chemicals during

  19. Experimental facilities for Generation IV reactors research

    International Nuclear Information System (INIS)

    Krecanova, E.; Di Gabriele, F.; Berka, J.; Zychova, M.; Macak, J.; Vojacek, A.

    2013-06-01

    Centrum Vyzkumu Rez (CVR) is research and development Company situated in Czech Republic and member of the UJV group. One of its major fields is material research for Generation IV reactor concepts, especially supercritical water-cooled reactor (SCWR), very high temperature/gas-cooled fast reactor (VHTR/GFR) and lead-cooled fast reactor (LFR). The CVR is equipped by and is building unique experimental facilities which simulate the environment in the active zones of these reactor concepts and enable to pre-qualify and to select proper constructional materials for the most stressed components of the facility (cladding, vessel, piping). New infrastructure is founded within the Sustainable Energy project focused on implementation the Generation IV and fusion experimental facilities. The research of SCWR concept is divided to research and development of the constructional materials ensured by SuperCritical Water Loop (SCWL) and fuel components research on Fuel Qualification Test loop (SCWL-FQT). SCWL provides environment of the primary circuits of European SCWR, pressure 25 MPa, temperature 600 deg. C and its major purpose is to simulate behavior of the primary medium and candidate constructional materials. On-line monitoring system is included to collect the operational data relevant to experiment and its evaluation (pH, conductivity, chemical species concentration). SCWL-FQT is facility focused on the behavior of cladding material and fuel at the conditions of so-called preheater, the first pass of the medium through the fuel (in case of European SCWR concept). The conditions are 450 deg. C and 25 MPa. SCWL-FQT is unique facility enabling research of the shortened fuel rods. VHTR/GFR research covers material testing and also cleaning methods of the medium in primary circuit. The High Temperature Helium Loop (HTHL) enables exposure of materials and simulates the VHTR/GFR core environment to analyze the behavior of medium, especially in presence of organic compounds and

  20. Compilation of interim technical research memoranda. Volume I

    International Nuclear Information System (INIS)

    Shanahan, W.R.

    1984-04-01

    Four interim technical research memoranda are presented that describe the results of numerical simulations designed to investigate the dynamics of energetic plasma beams propagating across magnetic fields

  1. Anti- and Hypermatter Research at the Facility for Antiproton and Ion Research FAIR

    International Nuclear Information System (INIS)

    Steinheimer, J; Xu, Z; Gudima, K; Botvina, A; Mishustin, I; Bleicher, M; Stöcker, H

    2012-01-01

    Within the next six years, the Facility for Antiproton and Ion Research (FAIR) is built adjacent to the existing accelerator complex of the GSI Helmholtz Center for Heavy Ion Research at Darmstadt, Germany. Thus, the current research goals and the technical possibilities are substantially expanded. With its worldwide unique accelerator and experimental facilities, FAIR will provide a wide range of unprecedented fore-front research in the fields of hadron, nuclear, atomic, plasma physics and applied sciences which are summarized in this article. As an example this article presents research efforts on strangeness at FAIR using heavy ion collisions, exotic nuclei from fragmentation and antiprotons to tackle various topics in this area. In particular, the creation of hypernuclei and antimatter is investigated.

  2. Underground characterisation and research facility ONKALO

    International Nuclear Information System (INIS)

    Ikonen, Antti; Ylae-Mella, Mia; Aeikaes, Timo

    2006-01-01

    Posiva's repository for geological disposal of the spent fuel from Finnish nuclear reactors will be constructed at Olkiluoto. The selection of Olkiluoto was made based on site selection research programme conducted between 1987-2001. The next step is to carry out complementary investigations of the site and apply for the construction license for the disposal facility. The license application will be submitted in 2012. To collect detailed information of the geological environment at planned disposal depth an underground characterisation and research facility will be built at the site. This facility, named as ONKALO, will comprise a spiral access tunnel and two vertical shafts. The excavation of ONKALO is in progress and planned depth (400 m) will be reached in 2009. During the course of the excavation Posiva will conduct site characterisation activities to assess the structure and other properties of the site geology. The aim is that construction will not compromise the favourable conditions of the planned disposal depth or introduce harmful effects in the surrounding bedrock which could jeopardize the long-term safety of the geological disposal. (author)

  3. Standards for psychological assessment of nuclear facility personnel. Technical report

    International Nuclear Information System (INIS)

    Frank, F.D.; Lindley, B.S.; Cohen, R.A.

    1981-07-01

    The subject of this study was the development of standards for the assessment of emotional instability in applicants for nuclear facility positions. The investigation covered all positions associated with a nuclear facility. Conclusions reached in this investigation focused on the ingredients of an integrated selection system including the use of personality tests, situational simulations, and the clinical interview; the need for professional standards to ensure quality control; the need for a uniform selection system as organizations vary considerably in terms of instruments presently used; and the need for an on-the-job behavioral observation program

  4. Holifield Heavy Ion Research Facility. Phase II

    International Nuclear Information System (INIS)

    Ball, J.B.; Hudson, E.D.; Lord, R.S.; Johnson, J.W.; Martin, J.A.; McNeilly, G.S.; Milner, W.T.; Mosko, S.W.; Sayer, R.O.; Robinson, R.L.

    1979-01-01

    The Holifield Heavy Ion Research Facility, with the completion of Phase I in late 1979, will include the Oak Ridge Isochronous Cyclotron (ORIC) and associated research areas, the new 25 MV tandem accelerator with new research areas for tandem beams, and modifications to utilize the ORIC as a booster accelerator. The combination of the tandem and ORIC will provide beam energies of 25 MeV/A for light heavy ions and 6 MeV/A up to A = 160. This paper discusses plans for a Phase II expansion of the facility to include an isochronous cyclotron with superconducting magnet and reconfiguration of the existing research areas and the ORIC vault to handle the higher energy beams from the new cyclotron. The new booster cyclotron is a low-flutter high-spiral design patterned after the MSU K = 800 design, with a central magnetic field of about 5 tesla and an extraction radius of 1 meter. The new beam transport system will incorporate an rf beam-splitter system that will be able to deliver successive beam pulses to two or three experiment areas

  5. Technical bases for establishing a salt test facility

    International Nuclear Information System (INIS)

    1985-05-01

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

  6. the effects of unavailability of technical storage facilities to the ...

    African Journals Online (AJOL)

    flavour and good appearance to our daily food, rather they are the major. 1. Development Studies Institute ... Morogoro. 3. Food Science and Technology, Sokoine University of Agriculture, P.O. Box 3006,. Morogoro. ..... To design good packing facilities for fruits and vegetables instead of. “Tengas”. • To have transport ...

  7. Cost calculations for decommissioning and dismantling of nuclear research facilities

    International Nuclear Information System (INIS)

    Andersson, I.; Backe, S.; Cato, A.; Lindskog, S.; Efraimsson, H.; Iversen, Klaus; Salmenhaara, S.; Sjoeblom, R.

    2008-07-01

    Today, it is recommended that planning of decommission should form an integral part of the activities over the life cycle of a nuclear facility (planning, building and operation), but it was only in the nineteen seventies that the waste issue really surface. Actually, the IAEA guidelines on decommissioning have been issued as recently as over the last ten years, and international advice on finance of decommissioning is even younger. No general international guideline on cost calculations exists at present. This implies that cost calculations cannot be performed with any accuracy or credibility without a relatively detailed consideration of the radiological prerequisites. Consequently, any cost estimates based mainly on the particulars of the building structures and installations are likely to be gross underestimations. The present study has come about on initiative by the Swedish Nuclear Power Inspectorate (SKI) and is based on a common need in Denmark, Finland, Norway and Sweden. The content of the report may be briefly summarised as follows. The background covers design and operation prerequisites as well as an overview of the various nuclear research facilities in the four participating countries: Denmark, Finland, Norway and Sweden. The purpose of the work has been to identify, compile and exchange information on facilities and on methodologies for cost calculation with the aim of achieving an 80 % level of confidence. The scope has been as follows: 1) to establish a Nordic network 2) to compile dedicated guidance documents on radiological surveying, technical planning and financial risk identification and assessment 3) to compile and describe techniques for precise cost calculations at early stages 4) to compile plant and other relevant data A separate section is devoted in the report to good practice for the specific purpose of early but precise cost calculations for research facilities, and a separate section is devoted to techniques for assessment of cost

  8. Cost calculations for decommissioning and dismantling of nuclear research facilities

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, I. (Studsvik Nuclear AB (Sweden)); Backe, S. (Institute for Energy Technology (Norway)); Cato, A.; Lindskog, S. (Swedish Nuclear Power Inspectorate (Sweden)); Efraimsson, H. (Swedish Radiation Protection Authority (Sweden)); Iversen, Klaus (Danish Decommissioning (Denmark)); Salmenhaara, S. (VTT Technical Research Centre of Finland (Finland)); Sjoeblom, R. (Tekedo AB, (Sweden))

    2008-07-15

    Today, it is recommended that planning of decommission should form an integral part of the activities over the life cycle of a nuclear facility (planning, building and operation), but it was only in the nineteen seventies that the waste issue really surface. Actually, the IAEA guidelines on decommissioning have been issued as recently as over the last ten years, and international advice on finance of decommissioning is even younger. No general international guideline on cost calculations exists at present. This implies that cost calculations cannot be performed with any accuracy or credibility without a relatively detailed consideration of the radiological prerequisites. Consequently, any cost estimates based mainly on the particulars of the building structures and installations are likely to be gross underestimations. The present study has come about on initiative by the Swedish Nuclear Power Inspectorate (SKI) and is based on a common need in Denmark, Finland, Norway and Sweden. The content of the report may be briefly summarised as follows. The background covers design and operation prerequisites as well as an overview of the various nuclear research facilities in the four participating countries: Denmark, Finland, Norway and Sweden. The purpose of the work has been to identify, compile and exchange information on facilities and on methodologies for cost calculation with the aim of achieving an 80 % level of confidence. The scope has been as follows: 1) to establish a Nordic network 2) to compile dedicated guidance documents on radiological surveying, technical planning and financial risk identification and assessment 3) to compile and describe techniques for precise cost calculations at early stages 4) to compile plant and other relevant data A separate section is devoted in the report to good practice for the specific purpose of early but precise cost calculations for research facilities, and a separate section is devoted to techniques for assessment of cost

  9. ARM Climate Research Facility Annual Report 2005

    Energy Technology Data Exchange (ETDEWEB)

    J. Voyles

    2005-12-31

    Through the ARM Program, the DOE funded the development of several highly instrumented ground stations for studying cloud formation processes and their influence on radiative transfer, and for measuring other parameters that determine the radiative properties of the atmosphere. This scientific infrastructure, and resultant data archive, is a valuable national and international asset for advancing scientific knowledge of Earth systems. In fiscal year (FY) 2003, the DOE designated ARM sites as a national scientific user facility: the ARM Climate Research (ACRF). The ACRF has enormous potential to contribute to a wide range interdisciplinary science in areas such as meteorology, atmospheric aerosols, hydrology, biogeochemical cycling, and satellite validation, to name only a few.

  10. Synchrotron radiation research facility conceptual design report

    International Nuclear Information System (INIS)

    1976-06-01

    A report is presented to define, in general outline, the extent and proportions, the type of construction, the schedule for accomplishment, and the estimated cost for a new Synchrotron Radiation Facility, as proposed to the Energy Research and Development Administration by the Brookhaven National Laboratory. The report is concerned only indirectly with the scientific and technological justification for undertaking this project; the latter is addressed explicitly in separate documents. The report does consider user requirements, however, in order to establish a basis for design development. Preliminary drawings, outline specifications, estimated cost data, and other descriptive material are included as supporting documentation on the current status of the project in this preconstruction phase

  11. 77 FR 6791 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2012-02-09

    ... DEPARTMENT OF ENERGY Biomass Research and Development Technical Advisory Committee AGENCY: Energy... announces an open meeting of the Biomass Research and Development Technical Advisory Committee. The Federal... leading to the production of biobased fuels and biobased products. Tentative Agenda Update on USDA Biomass...

  12. 77 FR 26276 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2012-05-03

    ... business of the Biomass Research and Development Technical Advisory Committee. To attend the meeting and/or... DEPARTMENT OF ENERGY Energy Efficiency and Renewable Energy Biomass Research and Development Technical Advisory Committee AGENCY: Energy Efficiency and Renewable Energy, Department of Energy. ACTION...

  13. 78 FR 44105 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2013-07-23

    ... Research and Development Technical Advisory Committee. To attend the meeting and/or to make oral statements... DEPARTMENT OF ENERGY Energy Efficiency and Renewable Energy Biomass Research and Development Technical Advisory Committee AGENCY: Energy Efficiency and Renewable Energy, Department of Energy. ACTION...

  14. 76 FR 63614 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2011-10-13

    ... Biomass Research and Development Technical Advisory Committee. To attend the meeting and/or to make oral... DEPARTMENT OF ENERGY Energy Efficiency and Renewable Energy Biomass Research and Development Technical Advisory Committee AGENCY: Energy Efficiency and Renewable Energy, Department of Energy. ACTION...

  15. Bibliography of Lewis Research Center Technical Publications announced in 1991

    Science.gov (United States)

    1992-01-01

    This compilation of abstracts describes and indexes the technical reporting that resulted from the scientific engineering work performed and managed by the Lewis Research Center in 1991. All the publications were announced in the 1991 issues of STAR (Scientific and Technical Aerospace Reports) and/or IAA (International Aerospace Abstracts). Included are research reports, journal articles, conference presentations, patents and patent applications, and theses.

  16. Exploratory shaft facility preliminary designs - Paradox Basin. Technical report

    International Nuclear Information System (INIS)

    1983-09-01

    The purpose of the Preliminary Design Report, Paradox Basin, is to provide a description of the preliminary design for an Exploratory Shaft Facility in the Paradox Basin, Utah. This issue of the report describes the preliminary design for constructing the exploratory shaft using the Large Hole Drilling Method of construction and outlines the preliminary design and estimates of probable construction cost. The Preliminary Design Report is prepared to complement and summarize other documents that comprise the design at the preliminary stage of completion, December 1982. Other design documents include drawings, cost estimates and schedules. The preliminary design drawing package, which includes the construction schedule drawing, depicts the descriptions in this report. For reference, a list of the drawing titles and corresponding numbers is included in the Appendix. The report is divided into three principal sections: Design Basis, Facility Description, and Construction Cost Estimate. 30 references

  17. Mineral deposits research in Uruguay. Technical economic part

    International Nuclear Information System (INIS)

    Raabe, W.

    1959-01-01

    Technical researches, mineralogical and chemical analysis were carried out in Zapucay and Iman deposit located in Uruguay south America, as a result of that, researchers was described the mineral adherences of the deposits.

  18. SINP MSU accelerator facility and applied research

    International Nuclear Information System (INIS)

    Chechenin, N.G.; Ishkhanov, B.S.; Kulikauskas, V.S.; Novikov, L.S.; Pokhil, G.P.; Romanovskii, E.A.; Shvedunov, V.I.; Spasskii, A.V.

    2004-01-01

    Full text: SINP accelerator facility includes 120 cm cyclotron, electrostatic generator with the upper voltage 3.0 MeV, electrostatic generator with the upper voltage 2.5 MeV, Cocroft -Walton generator with the upper voltage 500 keV, 150 keV accelerator for solid microparticles. A new generation of electron beam accelerators has been developed during the last decade. The SINP accelerator facility will be shortly described in the report. A wide range of basic research in nuclear and atomic physics, physics of ion-beam interactions with condensed matter is currently carried out. SINP activity in the applied research is concentrated in the following areas of materials science: - Materials diagnostics with the Rutherford backscattering techniques (RBS) and channeling of ions (RBS/C). A large number of surface ad-layers and multilayer systems for advanced micro- and nano-electronic technology have been investigated. A selected series of examples will be illustrated. - Concentration depth profiles of hydrogen by the elastic recoils detection techniques (ERD). Primarily, the hydrogen depth profiles in perspective materials for thermonuclear reactors have been investigated. - Lattice site locations of hydrogen by a combination of ERD and channeling techniques. This is a new technique which was successfully applied for investigation of hydrogen and hydrogen-defect complexes in silicon for the smart-cut technology. - Light element diagnostics by RBS and nuclear backscattering techniques (NBS). The technique is illustrated by applications for nitrogen concentration profiling in steels. Nitrogen take-up and release, nitrides precipitate formation will be illustrated. - New medium energy ion scattering (MEIS) facility and applications. Ultra-high vacuum and superior energy resolution electrostatic toroidal analyzer is designed to be applied for characterization of composition and structure of several upper atomic layers of materials

  19. An overview of technical requirements on durable concrete production for near surface disposal facilities for radioactive wastes

    International Nuclear Information System (INIS)

    Tolentino, Evandro; Tello, Cledola Cassia Oliveira de

    2013-01-01

    Radioactive waste can be generated by a wide range of activities varying from activities in hospitals to nuclear power plants, to mines and mineral processing facilities. General public have devoted nowadays considerable attention to the subject of radioactive waste management due to heightened awareness of environmental protection. The preferred strategy for the management of all radioactive waste is to contain it and to isolate it from the accessible biosphere. The Federal Government of Brazil has announced the construction for the year of 2014 and operation for the year of 2016 of a near surface disposal facility for low and intermediate level radioactive waste. The objective of this paper is to provide an overview of technical requirements related to production of durable concrete to be used in near surface disposal facilities for radioactive waste concrete structures. These requirements have been considered by researchers dealing with ongoing designing effort of the Brazilian near surface disposal facility. (author)

  20. Neutron beam facilities at the replacement research reactor

    International Nuclear Information System (INIS)

    Kennedy, S.

    1999-01-01

    Full text: On September 3rd 1997 the Australian Federal Government announced their decision to replace the HIFAR research reactor by 2005. The proposed reactor will be a multipurpose reactor with improved capabilities for neutron beam research and for the production of radioisotopes for pharmaceutical, scientific and industrial use. The neutron beam facilities are intended to cater for Australian scientific needs well into the 21st century. In the first stage of planning the neutron Beam Facilities at the replacement reactor, a Consultative Group was formed (BFCG) to determine the scientific capabilities of the new facility. Members of the group were drawn from academia, industry and government research laboratories. The BFCG submitted their report in April 1998, outlining the scientific priorities to be addressed. Cold and hot neutron sources are to be included, and cold and thermal neutron guides will be used to position most of the instruments in a neutron guide hall outside the reactor confinement building. In 2005 it is planned to have eight instruments installed with a further three to be developed by 2010, and seven spare instrument positions for development of new instruments over the life of the reactor. A beam facilities technical group (BFTG) was then formed to prepare the engineering specifications for the tendering process. The group consisted of some members of the BFCG, several scientists and engineers from ANSTO, and scientists from leading neutron scattering centres in Europe, USA and Japan. The BFTG looked in detail at the key components of the facility such as the thermal, cold and hot neutron sources, neutron collimators, neutron beam guides and overall requirements for the neutron guide hall. The report of the BFTG, completed in August 1998, was incorporated into the draft specifications for the reactor project, which were distributed to potential reactor vendors. An assessment of the first stage of reactor vendor submissions was completed in

  1. Status of CHESS facility and research programs: 2010

    Energy Technology Data Exchange (ETDEWEB)

    Fontes, Ernest, E-mail: ef11@cornell.edu [Cornell High Energy Synchrotron Source, Cornell University, Ithaca, NY 14853 (United States); Bilderback, Donald H.; Gruner, Sol M. [Cornell High Energy Synchrotron Source, Cornell University, Ithaca, NY 14853 (United States)

    2011-09-01

    CHESS is a hard X-ray synchrotron radiation national facility located at Cornell University and funded by the National Science Foundation. It is open to all scientists by peer-reviewed proposal and serves 500-1000 visitors each year. The CHESS scientific and technical staff develops forefront research tools and X-ray instrumentation and methods and supports 12 experimental stations delivering high intensity X-ray beams produced at 5.3 GeV and 250 mA. The facility consists of a mix of dedicated and flexible experimental stations that are easily configured for general X-ray diffraction (wide- and small-angle), spectroscopy, imaging applications, etc. Dedicated stations support high-pressure powder X-ray diffraction, pulsed-laser deposition for layer-by-layer growth of surfaces, and three dedicated stations for protein crystallography. Specialized resource groups at the laboratory include: an X-ray detector group; MacCHESS, an NIH-supported research resource for protein crystallography; the G-line division, which primarily organizes graduate students and Cornell faculty members around three X-ray stations; a high-pressure diamond-anvil cell support laboratory; and a monocapillary drawing facility for making microbeam X-ray optics. Research is also ongoing to upgrade CHESS to a first-ever 5 GeV, 100 mA Energy Recovery Linac (ERL) hard X-ray source. This source will provide ultra-high spectral-brightness and <100 fs short-pulse capability at levels well in advance of those possible with existing storage rings. It will produce diffraction-limited X-rays beams of up to 10 keV energy and be capable of providing 1 nm round beams. Prototyping for this facility is under way now to demonstrate critical DC photoelectron injector and superconducting linac technologies needed for the full-scale ERL.

  2. Status of CHESS facility and research programs: 2010

    International Nuclear Information System (INIS)

    Fontes, Ernest; Bilderback, Donald H.; Gruner, Sol M.

    2011-01-01

    CHESS is a hard X-ray synchrotron radiation national facility located at Cornell University and funded by the National Science Foundation. It is open to all scientists by peer-reviewed proposal and serves 500-1000 visitors each year. The CHESS scientific and technical staff develops forefront research tools and X-ray instrumentation and methods and supports 12 experimental stations delivering high intensity X-ray beams produced at 5.3 GeV and 250 mA. The facility consists of a mix of dedicated and flexible experimental stations that are easily configured for general X-ray diffraction (wide- and small-angle), spectroscopy, imaging applications, etc. Dedicated stations support high-pressure powder X-ray diffraction, pulsed-laser deposition for layer-by-layer growth of surfaces, and three dedicated stations for protein crystallography. Specialized resource groups at the laboratory include: an X-ray detector group; MacCHESS, an NIH-supported research resource for protein crystallography; the G-line division, which primarily organizes graduate students and Cornell faculty members around three X-ray stations; a high-pressure diamond-anvil cell support laboratory; and a monocapillary drawing facility for making microbeam X-ray optics. Research is also ongoing to upgrade CHESS to a first-ever 5 GeV, 100 mA Energy Recovery Linac (ERL) hard X-ray source. This source will provide ultra-high spectral-brightness and <100 fs short-pulse capability at levels well in advance of those possible with existing storage rings. It will produce diffraction-limited X-rays beams of up to 10 keV energy and be capable of providing 1 nm round beams. Prototyping for this facility is under way now to demonstrate critical DC photoelectron injector and superconducting linac technologies needed for the full-scale ERL.

  3. High temperature aircraft research furnace facilities

    Science.gov (United States)

    Smith, James E., Jr.; Cashon, John L.

    1992-01-01

    Focus is on the design, fabrication, and development of the High Temperature Aircraft Research Furnace Facilities (HTARFF). The HTARFF was developed to process electrically conductive materials with high melting points in a low gravity environment. The basic principle of operation is to accurately translate a high temperature arc-plasma gas front as it orbits around a cylindrical sample, thereby making it possible to precisely traverse the entire surface of a sample. The furnace utilizes the gas-tungsten-arc-welding (GTAW) process, also commonly referred to as Tungsten-Inert-Gas (TIG). The HTARFF was developed to further research efforts in the areas of directional solidification, float-zone processing, welding in a low-gravity environment, and segregation effects in metals. The furnace is intended for use aboard the NASA-JSC Reduced Gravity Program KC-135A Aircraft.

  4. How Large-Scale Research Facilities Connect to Global Research

    DEFF Research Database (Denmark)

    Lauto, Giancarlo; Valentin, Finn

    2013-01-01

    Policies for large-scale research facilities (LSRFs) often highlight their spillovers to industrial innovation and their contribution to the external connectivity of the regional innovation system hosting them. Arguably, the particular institutional features of LSRFs are conducive for collaborative...... research. However, based on data on publications produced in 2006–2009 at the Neutron Science Directorate of Oak Ridge National Laboratory in Tennessee (United States), we find that internationalization of its collaborative research is restrained by coordination costs similar to those characterizing other...

  5. Technical and economic feasibility study for the reactivation of the integral test facility of IPEN/CNEN Nuclear Engineering Center

    Energy Technology Data Exchange (ETDEWEB)

    Biaty, Flávia P.; Rocha, Marcelo da S.; Oliveira, Otávio L. de, E-mail: flavia.biaty@usp.br, E-mail: msrocha@ipen.br, E-mail: otavioluis@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

    2017-07-01

    The Integral Test Facility of Nuclear Engineering Center (CEN/IPEN/CNEN-SP), known as 'Loop 70', is a semi-industrial thermal-hydraulic test facility and can operate as a BWR (Boiling Water Reactor) or a PWR (Pressurizing Water Reactor) mode. Designed and built in the 1980's, it is currently disabled. The experimental circuits ('test loop') are facilities that reproduce the thermohydraulic and fluid dynamic conditions that occur inside a reactor and are used to simulate the practical reality which it is not possible to be obtained through mathematical models. In this context, this research project aims the development of a Business Plan to analyze the technical and economic feasibility related to the reactivation of the facility. This methodology (adapted to the government sector) is a decision-making tool that will offer a wide perspective of the project, set the guidelines and actions that will define the future of the facility and provide a general rule to make investments on it. This paper presents the historic aspects to better understand the Loop 70's current situation. It also presents information about similar facilities around the world, services that can be offered (thermal-hydraulics parameters measurements, equipment qualification and transient analysis due accident situations), results of the strategic analysis (SWOT) performed, specific goals for each critical success or failure factor of the facility, financial aspects related to the reactivation and an overview of the facility's perspectives. (author)

  6. Technical and economic feasibility study for the reactivation of the integral test facility of IPEN/CNEN Nuclear Engineering Center

    International Nuclear Information System (INIS)

    Biaty, Flávia P.; Rocha, Marcelo da S.; Oliveira, Otávio L. de

    2017-01-01

    The Integral Test Facility of Nuclear Engineering Center (CEN/IPEN/CNEN-SP), known as 'Loop 70', is a semi-industrial thermal-hydraulic test facility and can operate as a BWR (Boiling Water Reactor) or a PWR (Pressurizing Water Reactor) mode. Designed and built in the 1980's, it is currently disabled. The experimental circuits ('test loop') are facilities that reproduce the thermohydraulic and fluid dynamic conditions that occur inside a reactor and are used to simulate the practical reality which it is not possible to be obtained through mathematical models. In this context, this research project aims the development of a Business Plan to analyze the technical and economic feasibility related to the reactivation of the facility. This methodology (adapted to the government sector) is a decision-making tool that will offer a wide perspective of the project, set the guidelines and actions that will define the future of the facility and provide a general rule to make investments on it. This paper presents the historic aspects to better understand the Loop 70's current situation. It also presents information about similar facilities around the world, services that can be offered (thermal-hydraulics parameters measurements, equipment qualification and transient analysis due accident situations), results of the strategic analysis (SWOT) performed, specific goals for each critical success or failure factor of the facility, financial aspects related to the reactivation and an overview of the facility's perspectives. (author)

  7. Solar Energy Research Center Instrumentation Facility

    Energy Technology Data Exchange (ETDEWEB)

    Meyer, Thomas, J.; Papanikolas, John, P.

    2011-11-11

    SOLAR ENERGY RESEARCH CENTER INSTRUMENTATION FACILITY The mission of the Solar Energy Research Center (UNC SERC) at the University of North Carolina at Chapel Hill (UNC-CH) is to establish a world leading effort in solar fuels research and to develop the materials and methods needed to fabricate the next generation of solar energy devices. We are addressing the fundamental issues that will drive new strategies for solar energy conversion and the engineering challenges that must be met in order to convert discoveries made in the laboratory into commercially available devices. The development of a photoelectrosynthesis cell (PEC) for solar fuels production faces daunting requirements: (1) Absorb a large fraction of sunlight; (2) Carry out artificial photosynthesis which involves multiple complex reaction steps; (3) Avoid competitive and deleterious side and reverse reactions; (4) Perform 13 million catalytic cycles per year with minimal degradation; (5) Use non-toxic materials; (6) Cost-effectiveness. PEC efficiency is directly determined by the kinetics of each reaction step. The UNC SERC is addressing this challenge by taking a broad interdisciplinary approach in a highly collaborative setting, drawing on expertise across a broad range of disciplines in chemistry, physics and materials science. By taking a systematic approach toward a fundamental understanding of the mechanism of each step, we will be able to gain unique insight and optimize PEC design. Access to cutting-edge spectroscopic tools is critical to this research effort. We have built professionally-staffed facilities equipped with the state-of the-art instrumentation funded by this award. The combination of staff, facilities, and instrumentation specifically tailored for solar fuels research establishes the UNC Solar Energy Research Center Instrumentation Facility as a unique, world-class capability. This congressionally directed project funded the development of two user facilities: TASK 1: SOLAR

  8. Designing and constructing/installing technical security countermeasures (TSCM) into supersensitive facilities

    International Nuclear Information System (INIS)

    Davis, D.L.

    1988-01-01

    The design and construction of supersensitive facilities and the installation of systems secure from technical surveillance and sabotage penetration involve ''TSCM'' in the broad sense of technical ''security'' countermeasures. When the technical threat was at a lower level of intensity and sophistication, it was common practice to defer TSCM to the future facility occupant. However, the New Moscow Embassy experience has proven this course of action subject to peril. Although primary concern with the embassy was audio surveillance, elsewhere there are other threats of equal or greater concern, e.g., technical implants may be used to monitor readiness status or interfere with the operation of C3I and weapons systems. Present and future technical penetration threats stretch the imagination. The Soviets have committed substantial hard scientific resources to a broad range of technical intelligence, even including applications or parapsychology. Countering these threats involves continuous TSCM precautions from initial planning to completion. Designs and construction/installation techniques must facilitate technical inspections and preclude the broadest range of known and suspected technical penetration efforts

  9. Designing and constructing/installing technical security countermeasures (TSCM) into supersensitive facilities

    Energy Technology Data Exchange (ETDEWEB)

    Davis, D.L.

    1988-01-01

    The design and construction of supersensitive facilities and the installation of systems secure from technical surveillance and sabotage penetration involve ''TSCM'' in the broad sense of technical ''security'' countermeasures. When the technical threat was at a lower level of intensity and sophistication, it was common practice to defer TSCM to the future facility occupant. However, the New Moscow Embassy experience has proven this course of action subject to peril. Although primary concern with the embassy was audio surveillance, elsewhere there are other threats of equal or greater concern, e.g., technical implants may be used to monitor readiness status or interfere with the operation of C3I and weapons systems. Present and future technical penetration threats stretch the imagination. The Soviets have committed substantial hard scientific resources to a broad range of technical intelligence, even including applications or parapsychology. Countering these threats involves continuous TSCM precautions from initial planning to completion. Designs and construction/installation techniques must facilitate technical inspections and preclude the broadest range of known and suspected technical penetration efforts.

  10. Development of an Extreme Environment Materials Research Facility at Princeton

    International Nuclear Information System (INIS)

    Cohen, A.B.; Gentile, C.A.; Tully, C.G.; Austin, R.; Calaprice, F.; McDonald, K.; Ascione, G.; Baker, G.; Davidson, R.; Dudek, L.; Grisham, L.; Kugel, H.; Pagdon, K.; Stevenson, T.; Woolley, R.; Zwicker, A.

    2010-01-01

    The need for a fundamental understanding of material response to a neutron and/or high heat flux environment can yield development of improved materials and operations with existing materials. Such understanding has numerous applications in fields such as nuclear power (for the current fleet and future fission and fusion reactors), aerospace, and other research fields (e.g., high-intensity proton accelerator facilities for high energy physics research). A proposal has been advanced to develop a facility for testing various materials under extreme heat and neutron exposure conditions at Princeton. The Extreme Environment Materials Research Facility comprises an environmentally controlled chamber (48 m 3 ) capable of high vacuum conditions, with extreme flux beams and probe beams accessing a central, large volume target. The facility will have the capability to expose large surface areas (1 m 2 ) to 14 MeV neutrons at a fluence in excess of 10 13 n/s. Depending on the operating mode. Additionally beam line power on the order of 15-75 MW/m 2 for durations of 1-15 seconds are planned. The multi-second duration of exposure can be repeated every 2-10 minutes for periods of 10-12 hours. The facility will be housed in the test cell that held the Tokamak Fusion Test Reactor (TFTR), which has the desired radiation and safety controls as well as the necessary loading and assembly infrastructure. The facility will allow testing of various materials to their physical limit of thermal endurance and allow for exploring the interplay between radiation-induced embrittlement, swelling and deformation of materials, and the fatigue and fracturing that occur in response to thermal shocks. The combination of high neutron energies and intense fluences will enable accelerated time scale studies. The results will make contributions for refining predictive failure modes (modeling) in extreme environments, as well as providing a technical platform for the development of new alloys, new

  11. In Vivo Radiobioassay and Research Facility

    International Nuclear Information System (INIS)

    Lynch, Timothy P.

    2011-01-01

    Bioassay monitoring for intakes of radioactive material is an essential part of the internal dosimetry program for radiation workers at the Department of Energy's (DOE) Hanford Site. This monitoring program includes direct measurements of radionuclides in the body by detecting photons that exit the body and analyses of radionuclides in excreta samples. The specialized equipment and instrumentation required to make the direct measurements of these materials in the body are located at the In Vivo Radiobioassay and Research Facility (IVRRF). The IVRRF was originally built in 1960 and was designed expressly for the in vivo measurement of radioactive material in Hanford workers. Most routine in vivo measurements are performed annually and special measurements are performed as needed. The primary source terms at the Hanford Site include fission and activation products (primarily 137Cs and 90Sr), uranium, uranium progeny, and transuranic radionuclides. The facility currently houses five shielded counting systems, men's and women's change rooms and an instrument maintenance and repair shop. Four systems include high purity germanium detectors and one system utilizes large sodium iodide detectors. These systems are used to perform an average of 7,000 measurements annually. This includes approximately 5000 whole body measurements analyzed for fission and activation products and 2000 lung measurements analyzed for americium, uranium, and plutonium. Various other types of measurements are performed periodically to estimate activity in wounds, the thyroid, the liver, and the skeleton. The staff maintains the capability to detect and quantify activity in essentially any tissue or organ. The in vivo monitoring program that utilizes the facility is accredited by the Department of Energy Laboratory Accreditation Program for direct radiobioassay.

  12. A Framework for Managing Core Facilities within the Research Enterprise

    OpenAIRE

    Haley, Rand

    2009-01-01

    Core facilities represent increasingly important operational and strategic components of institutions' research enterprises, especially in biomolecular science and engineering disciplines. With this realization, many research institutions are placing more attention on effectively managing core facilities within the research enterprise. A framework is presented for organizing the questions, challenges, and opportunities facing core facilities and the academic units and institutions in which th...

  13. The technical development on recycled aggregate concrete for nuclear facility

    International Nuclear Information System (INIS)

    Sukekiyo, M.; Saishu, S.; Ishikura, T.; Ishigure, K.

    2000-01-01

    The large amount of non-radioactive concrete waste generated by decommissioning has a very big impact on the final disposal site. Therefore, NUPEC has been developing technology which recovers at a high ratio the aggregate from the dismantling concrete with a quality which can be used to construct a new nuclear power plant. The developed high-quality recycled aggregate meets the quality standards of the natural aggregate stipulated by the Japanese architectural standard specifications for nuclear power plant facilities. As a result of these experiments, it was confirmed that the recycled concrete which used this high-quality recycled aggregate had a performance equal or better than ordinary concrete which used natural aggregate. (authors)

  14. Large power supply facilities for fusion research

    International Nuclear Information System (INIS)

    Miyahara, Akira; Yamamoto, Mitsuyoshi.

    1976-01-01

    The authors had opportunities to manufacture and to operate two power supply facilities, that is, 125MVA computer controlled AC generator with a fly wheel for JIPP-T-2 stellerator in Institute of Plasma Physics, Nagoya University and 3MW trial superconductive homopolar DC generator to the Japan Society for Promotion of Machine Industry. The 125MVA fly-wheel generator can feed both 60MW (6kV x 10kA) DC power for toroidal coils and 20MW (0.5kV x 40kA) DC power for helical coils. The characteristic features are possibility of Bung-Bung control based on Pontrjagin's maximum principle, constant current control or constant voltage control for load coils, and cpu control for routine operation. The 3MW (150V-20000A) homopolar generator is the largest in the world as superconductive one, however, this capacity is not enough for nuclear fusion research. The problems of power supply facilities for large Tokamak devices are discussed

  15. MYRRHA. An innovative and unique research facility

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez, Rafaeol; Neerdael, Bernard; Schyns, Marc; Dyck, Steven Van; Michiels, Sidney; Ait Abderrahim, Hamid, E-mail: myrrha@sckcen.be [Belgian Nuclear Research Centre (SCK-CEN), Mol (Belgium)

    2012-03-15

    The MYRRHA project started in 1998 by SCK{center_dot}CEN in collaboration with Ion Beam Applications (IBA, Louvain-la-Neuve), as an upgrade of the ADONIS project. MYRRHA is designed as a multi-purpose irradiation facility in order to support research programmes on fission and fusion reactor structural materials and nuclear fuel development. Applications of these are found in Accelerator Driven Systems (ADS) systems and in present generation as well as in next generation critical reactors. The first objective of MYRRHA however, will be to demonstrate on one hand the ADS concept at a reasonable power level and on the other hand the technological feasibility of transmutation of Minor Actinides (MA) and Long-Lived Fission Products (LLFP) arising from the reprocessing of radioactive waste. MYRRHA will also help the development of the Pb-alloys technology needed for the LFR (Lead Fast Reactor) Gen.IV concept. Transmutation of MA can be completed in an efficient way in fast neutron spectrum facilities. Both critical reactors and sub-critical ADS are potential candidates as dedicated transmutation systems. However, critical reactors, heavily loaded with fuel containing large amounts of MA, pose safety problems caused by unfavourable reactivity coefficients due to the little delayed neutron fraction. A sub-critical ADS operates in a flexible and safe manner even with a core loading containing a high amount of MA leading to achieve a high efficient transmutation. Thus, the sub-criticality is not a virtue but rather a necessity for an efficient and economical burning of the MA. Besides the reduction of the HLW burden, the MYRRHA project will serve the purpose of developing the lead alloys technology as a reactor coolant that can be used in one of the Generation IV reactor concepts namely the Lead Fast Reactor (LFR). Although carrying out the MYRRHA project will lead to the demonstration of the efficient and safe transmutation of MA in ADS systems as the ultimate goal the

  16. Technical considerations in the design of near surface disposal facilities for radioactive waste

    International Nuclear Information System (INIS)

    2001-11-01

    Good design is an important step towards ensuring operational as well as long term safety of low and intermediate level waste (LILW) disposal. The IAEA has produced this report with the objective of outlining the most important technical considerations in the design of near surface disposal facilities and to provide some examples of the design process in different countries. This guidance has been developed in light of experience gained from the design of existing near surface disposal facilities in a range of Member States. In particular the report provide information on design objective, design requirements, and design phases. The report focuses on: near surface disposal facilities accepting solidified LILW; disposal facilities on or just below the ground surface, where the final protective covering is of the order of a few metres thick; and disposal facilities several tens of metres below the ground surface (including rock cavern type facilities)

  17. Study of In-Pile test facility for fast reactor safety research: performance requirements and design features

    Energy Technology Data Exchange (ETDEWEB)

    Nonaka, N.; Kawatta, N.; Niwa, H.; Kondo, S.; Maeda, K

    1996-12-31

    This paper describes a program and the main design features of a new in-pile safety facility SERAPH planned for future fast reactor safety research. The current status of R and D on technical developments in relation to the research objectives and performance requirements to the facility design is given.

  18. THE OFFICE OF AEROSPACE RESEARCH SCIENTIFIC AND TECHNICAL INFORMATION PROGRAM

    Science.gov (United States)

    The document outlines the mission and organization of the Office of Aerospace Research (OAR), then describes how its principal product, scientific...effective technical information program, are documented by examples. The role of the Office of Scientific and Technical Information within OAR as performed

  19. Safety of and regulations for nuclear fuel cycle facilities. Report of a technical committee meeting

    International Nuclear Information System (INIS)

    2001-05-01

    In order to compile information on the nature of the safety concerns and current status of the regulations concerning nuclear fuel cycle facilities in Member States, an IAEA Technical Committee meeting on this topic was convened from 8 to 12 May 2000 in Vienna. The present publication contains the results of this meeting. The contributions of the participants in Annex 3 exemplify the work done in some Member States to develop an adequate regulatory framework to oversee the safe operation of these facilities

  20. Vehicle Thermal Management Facilities | Transportation Research | NREL

    Science.gov (United States)

    Integration Facility The Vehicle Testing and Integration Facility features a pad to conduct vehicle thermal station next to the pad provides a continuous data stream on temperature, humidity, wind speed, and solar

  1. Facilities available for actinide research in Prague

    International Nuclear Information System (INIS)

    Sechovský, V.

    2014-01-01

    Since June 2012 the Prague group at the Charles University operates a Czech research infrastructure Magnetism and Low Temperature Laboratories (MLTL - http://mltl.eu orhttp://lmnt.cz)which is financially supported by the Government of Czech Republic. The main mission of MLTL is to provide broad scientific community unique possibilities for comprehensive experimental studies of physical phenomena and properties of materials in multiextreme conditions.MLTL offer open access to a wide range of experimental facilities for sample preparation (SSE refinement of staring metals, synthesis of bulk polycrystals, growth of single crystals), characterization (XRD, SEM + EDX) and measurements of various physical properties in high magnetic fields up to 20 T, temperatures from 30 mK to 1000Kand external pressures up to 25 GPa). Anybody can apply for experimental time with his proposal on the user portal of http://mltl.eu. The main strategic objective is the excellence of the infrastructure on the international scale. Therefore the MLTL Panel evaluation the proposals and allocation of experimental time is based primarily on the quality of intended research. The proposals of students for experiments needed for their theses are promoted within the evaluation process. The research opportunities offered by MLTL will be demonstrated during the lecture with emphasis on methodology

  2. Psychometric model for safety culture assessment in nuclear research facilities

    International Nuclear Information System (INIS)

    Nascimento, C.S. do; Andrade, D.A.; Mesquita, R.N. de

    2017-01-01

    Highlights: • A psychometric model to evaluate ‘safety climate’ at nuclear research facilities. • The model presented evidences of good psychometric qualities. • The model was applied to nuclear research facilities in Brazil. • Some ‘safety culture’ weaknesses were detected in the assessed organization. • A potential tool to develop safety management programs in nuclear facilities. - Abstract: A safe and reliable operation of nuclear power plants depends not only on technical performance, but also on the people and on the organization. Organizational factors have been recognized as the main causal mechanisms of accidents by research organizations through USA, Europe and Japan. Deficiencies related with these factors reveal weaknesses in the organization’s safety culture. A significant number of instruments to assess the safety culture based on psychometric models that evaluate safety climate through questionnaires, and which are based on reliability and validity evidences, have been published in health and ‘safety at work’ areas. However, there are few safety culture assessment instruments with these characteristics (reliability and validity) available on nuclear literature. Therefore, this work proposes an instrument to evaluate, with valid and reliable measures, the safety climate of nuclear research facilities. The instrument was developed based on methodological principles applied to research modeling and its psychometric properties were evaluated by a reliability analysis and validation of content, face and construct. The instrument was applied to an important nuclear research organization in Brazil. This organization comprises 4 research reactors and many nuclear laboratories. The survey results made possible a demographic characterization and the identification of some possible safety culture weaknesses and pointing out potential areas to be improved in the assessed organization. Good evidence of reliability with Cronbach's alpha

  3. Psychometric model for safety culture assessment in nuclear research facilities

    Energy Technology Data Exchange (ETDEWEB)

    Nascimento, C.S. do, E-mail: claudio.souza@ctmsp.mar.mil.br [Centro Tecnológico da Marinha em São Paulo (CTMSP), Av. Professor Lineu Prestes 2468, 05508-000 São Paulo, SP (Brazil); Andrade, D.A., E-mail: delvonei@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN – SP), Av. Professor Lineu Prestes 2242, 05508-000 São Paulo, SP (Brazil); Mesquita, R.N. de, E-mail: rnavarro@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN – SP), Av. Professor Lineu Prestes 2242, 05508-000 São Paulo, SP (Brazil)

    2017-04-01

    Highlights: • A psychometric model to evaluate ‘safety climate’ at nuclear research facilities. • The model presented evidences of good psychometric qualities. • The model was applied to nuclear research facilities in Brazil. • Some ‘safety culture’ weaknesses were detected in the assessed organization. • A potential tool to develop safety management programs in nuclear facilities. - Abstract: A safe and reliable operation of nuclear power plants depends not only on technical performance, but also on the people and on the organization. Organizational factors have been recognized as the main causal mechanisms of accidents by research organizations through USA, Europe and Japan. Deficiencies related with these factors reveal weaknesses in the organization’s safety culture. A significant number of instruments to assess the safety culture based on psychometric models that evaluate safety climate through questionnaires, and which are based on reliability and validity evidences, have been published in health and ‘safety at work’ areas. However, there are few safety culture assessment instruments with these characteristics (reliability and validity) available on nuclear literature. Therefore, this work proposes an instrument to evaluate, with valid and reliable measures, the safety climate of nuclear research facilities. The instrument was developed based on methodological principles applied to research modeling and its psychometric properties were evaluated by a reliability analysis and validation of content, face and construct. The instrument was applied to an important nuclear research organization in Brazil. This organization comprises 4 research reactors and many nuclear laboratories. The survey results made possible a demographic characterization and the identification of some possible safety culture weaknesses and pointing out potential areas to be improved in the assessed organization. Good evidence of reliability with Cronbach's alpha

  4. Creation of a new-generation research nuclear facility

    International Nuclear Information System (INIS)

    Girchenko, A.A.; Matyushin, A.P.; Kudryavtsev, E.M.; Skopin, V.P.; Shchepelev, R.M.

    2013-01-01

    The SO-2M research nuclear facility operated on the industrial area of the institute. The facility is now removed from service. In view of this circumstance, it is proposed to restore the facility at the new qualitative level, i.e., to create a new-generation research nuclear facility with a very high safety level consisting of a subcritical bench and a proton accelerator (electronuclear facility). Competitive advantages and design features have been discussed and the productive capacity of the research nuclear facility under development has been evaluated [ru

  5. KEEP Language Research Strategy. Technical Report #14.

    Science.gov (United States)

    Tharp, Roland G.; Gallimore, Ronald

    This paper outlines the strategies of Kamehameha Early Education Program (KEEP) language research, and briefly reviews the findings through Spring 1974. A major research emphasis has been placed on the assessment of Standard English comptence of Hawaii school children. (CM)

  6. Research studies performed using the Cairo Fourier Diffractometer Facility

    International Nuclear Information System (INIS)

    Maayouf, R.M.A.; Ridikas, D.

    2009-12-01

    This report represents the results of the research studies performed using the Cairo Fourier Diffractometer Facility (CFDF), within 10 years after it was installed and put into operation at the beginning of 1996. The main components of the CFDF were supplied by the IAEA according to the technical assistance project EGY/1/022 'Upgrading of Research Reactor Utilization'. The present report is the second published INDC report, while the first one, published at the beginning of 1997, was about the performance of the CFDF and its main characteristic parameters. Plenty of measurements were performed since then, yielding several publications both in local and international scientific periodicals and resulting in 8 M.Sc. and Ph.D. degrees from Egyptian Universities. In addition, a new approach for the analysis of the neutron spectra was implemented using the CFDF. Specially designed interface card with proper software program was applied instead of the reverse time of flight (RTOF) and Finnish made analyzer originally attached to the facility. It has been verified that the new approach can successfully replace the RTOF analyzer, significantly decreasing the time of measurement and saving the reactor's operation time. Besides, a special fault diagnostic system program was developed and tested for caring and handling the possible failures of the CFDF. Moreover, measurements were carried out for the diffraction spectra emitted at different points of one of the samples. The latter was scanned across the neutron beam of the CFDF, for studying the stress after welding; used in industrial applications. (author)

  7. Europlanet Research Infrastructure: Planetary Simulation Facilities

    Science.gov (United States)

    Davies, G. R.; Mason, N. J.; Green, S.; Gómez, F.; Prieto, O.; Helbert, J.; Colangeli, L.; Srama, R.; Grande, M.; Merrison, J.

    2008-09-01

    EuroPlanet The Europlanet Research Infrastructure consortium funded under FP7 aims to provide the EU Planetary Science community greater access for to research infrastructure. A series of networking and outreach initiatives will be complimented by joint research activities and the formation of three Trans National Access distributed service laboratories (TNA's) to provide a unique and comprehensive set of analogue field sites, laboratory simulation facilities, and extraterrestrial sample analysis tools. Here we report on the infrastructure that comprises the second TNA; Planetary Simulation Facilities. 11 laboratory based facilities are able to recreate the conditions found in the atmospheres and on the surfaces of planetary systems with specific emphasis on Martian, Titan and Europa analogues. The strategy has been to offer some overlap in capabilities to ensure access to the highest number of users and to allow for progressive and efficient development strategies. For example initial testing of mobility capability prior to the step wise development within planetary atmospheres that can be made progressively more hostile through the introduction of extreme temperatures, radiation, wind and dust. Europlanet Research Infrastructure Facilties: Mars atmosphere simulation chambers at VUA and OU These relatively large chambers (up to 1 x 0.5 x 0.5 m) simulate Martian atmospheric conditions and the dual cooling options at VUA allows stabilised instrument temperatures while the remainder of the sample chamber can be varied between 220K and 350K. Researchers can therefore assess analytical protocols for instruments operating on Mars; e.g. effect of pCO2, temperature and material (e.g., ± ice) on spectroscopic and laser ablation techniques while monitoring the performance of detection technologies such as CCD at low T & variable p H2O & pCO2. Titan atmosphere and surface simulation chamber at OU The chamber simulates Titan's atmospheric composition under a range of

  8. Research and Development Issues for Interactive Electronic Technical Manuals

    National Research Council Canada - National Science Library

    Ricci, Katrina

    2002-01-01

    .... While there is a wide range of research issues associated with technical manuals, the focus of the Intelligent Performance Support and Training effort is the development and evaluation of various...

  9. Research and Development Issues for Interactive Electronic Technical Manuals

    National Research Council Canada - National Science Library

    Ricci, Katrina

    2002-01-01

    ... technologies to support Interactive Electronic Technical Manuals (IETMs). A workshop was conducted at the NAVAIR Orlando, Training Systems Division to discuss the domain and to present current research in this area...

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

    Science.gov (United States)

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

  11. Technical Meeting on Existing and Proposed Experimental Facilities for Fast Neutron Systems. Working Material

    International Nuclear Information System (INIS)

    2013-01-01

    The discussion which followed the different presentations highlighted the following points: • All the Member States representatives participating in the technical meeting welcomed this IAEA initiative and expressed their potential interest in contributing to the catalogue; • Not all the countries with a fast reactor programme were represented at the meeting. In particular, it was noted that there was no participation from China, the Russian Federation and the USA. Even contribution from Sweden and Spain would be beneficial. It will be a task of the IAEA Secretariat to try involving also these countries in the preparation of the catalogue; • The catalogue will focus only on experimental facilities supporting development of liquid metal cooled fast reactors (Sodium, Lead and Lead-Bismuth). For the time being, facilities in support of GFR and MSR research will not be included; • As for countries involved in HLM technology research, only European countries were participating at the meeting, i.e. Belgium, France, Italy and Germany. In order to avoid duplication of the work performed within the European project ADRIANA, representatives from these countries underlined that a condition for their contribution to the IAEA catalogue is the involvement of non-European countries with HLM research programmes; • The advice from the Member States is fundamental to clearly define scope, objectives and content of the catalogue. The plan for its drafting has also to be further discussed with Member States representatives; • The catalogue is also intended to identify gaps and future needs that require further R&D initiatives; • The catalogue will be a useful tool to set up international collaboration

  12. Technical on the TAB of air handling system in IMEF facility

    International Nuclear Information System (INIS)

    Oh, Yon Woo; Baik, S. Y.; Kim, S. D.; Lee, B. J.

    2002-08-01

    A T.A.B(Testing, Adjusting and Balancing) technique, the basic technique of air handling facility, is one of the essential technical items which workers in charge of operation of facilities have to acquire. Especially, through scientific and reasonable inspective procedures, the reduction of energy and guarantee of designed skill have become influential important problems in our time rather than in the past days. Entrepreneurs have required more thorough verify of performances and procedure of test in order to raise the investment efficiency and reduce expenditure. For that reason, I hope that cooperator acquire objective and substantial knowledges about air handling facility so that they are helped from them

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

    Science.gov (United States)

    1990-06-22

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

  14. Lewis Research Center space station electric power system test facilities

    Science.gov (United States)

    Birchenough, Arthur G.; Martin, Donald F.

    1988-01-01

    NASA Lewis Research Center facilities were developed to support testing of the Space Station Electric Power System. The capabilities and plans for these facilities are described. The three facilities which are required in the Phase C/D testing, the Power Systems Facility, the Space Power Facility, and the EPS Simulation Lab, are described in detail. The responsibilities of NASA Lewis and outside groups in conducting tests are also discussed.

  15. Technical Support DLA Apparel Research Network

    National Research Council Canada - National Science Library

    Guthrie, Jeffrey

    2002-01-01

    The Defense Logistics Agency's Research and Development Enterprise Division established a network of universities, equipment suppliers, apparel manufacturers, industry consultants and software developers...

  16. Bibliography of Lewis Research Center technical publications announced in 1990

    Science.gov (United States)

    1991-01-01

    This compilation of abstracts describes and indexes the technical reporting that resulted from the scientific and engineering work performed and managed by the Lewis Research Center in 1990. All the publications were announced in the 1990 issues of STAR (Scientific and Technical Aerospace Reports) and/or IAA (International Aerospace Abstracts). Included are research reports, journal articles, conference presentations, patents and patent applications, and theses.

  17. Bibliography of Lewis Research Center technical publications announced in 1992

    Science.gov (United States)

    1993-01-01

    This compilation of abstracts describes and indexes the technical reporting that resulted from the scientific and engineering work performed and managed by the Lewis Research Center in 1992. All the publications were announced in the 1992 issues of STAR (Scientific and Technical Aerospace Reports) and/or IAA (International Aerospace Abstracts). Included are research reports, journal articles, conference presentations, patents and patent applications, and theses.

  18. Bibliography of Lewis Research Center technical publications announced in 1993

    Science.gov (United States)

    1994-01-01

    This compilation of abstracts describes and indexes the technical reporting that resulted from the scientific and engineering work performed and managed by the Lewis Research Center in 1993. All the publications were announced in the 1993 issues of STAR (Scientific and Technical Aerospace Reports) and/or IAA (International Aerospace Abstracts). Included are research reports, journal articles, conference presentations, patents and patent applications, and theses.

  19. Bibliography of Lewis Research Center technical publications announced in 1989

    Science.gov (United States)

    1990-01-01

    This compilation of abstracts describes and indexes the technical reporting that resulted from the scientific and engineering work performed and managed by the Lewis Research Center in 1989. All the publications were announced in the 1989 issues of STAR (Scientific and Technical Aerospace Reports) and/or IAA (International Aerospace Abstracts). Included are research reports, journal articles, conference presentations, patents and patent applications, and theses.

  20. Scientific and technical photography at NASA Langley Research Center

    Science.gov (United States)

    Davidhazy, Andrew

    1994-12-01

    As part of my assignment connected with the Scientific and Technical Photography & Lab (STPL) at the NASA Langley Research Center I conducted a series of interviews and observed the day to day operations of the STPL with the ultimate objective of becoming exposed first hand to a scientific and technical photo/imaging department for which my school prepares its graduates. I was also asked to share my observations with the staff in order that these comments and observations might assist the STPL to better serve its customers. Meetings with several individuals responsible for various wind tunnels and with a group that provides photo-optical instrumentation services at the Center gave me an overview of the services provided by the Lab and possible areas for development. In summary form these are some of the observations that resulted from the interviews and daily contact with the STPL facility. (1) The STPL is perceived as a valuable and almost indispensable service group within the organization. This comment was invariably made by everyone. Everyone also seemed to support the idea that the STPL continue to provide its current level of service and quality. (2) The STPL generally is not perceived to be a highly technically oriented group but rather as a provider of high quality photographic illustration and documentation services. In spite of the importance and high marks assigned to the STPL there are several observations that merit consideration and evaluation for possible inclusion into the STPL's scope of expertise and future operating practices. (1) While the care and concern for artistic rendition of subjects is seen as laudable and sometimes valuable, the time that this often requires is seen as interfering with keeping the tunnels operating at maximum productivity. Tunnel managers would like to shorten down-time due to photography, have services available during evening hours and on short notice. It may be of interest to the STPL that tunnel managers are

  1. MYRRHA. An experimental ADS Facility for Research and Development

    International Nuclear Information System (INIS)

    Ait Abderrahim, H.

    2006-01-01

    Full text of publication follows: Since 1998, SCK-CEN in partnership with IBA s.a. and many European research laboratories, is designing a multipurpose ADS for R and D applications MYRRHA - and is conducting an associated R and D support programme. MYRRHA is an Accelerator Driven System (ADS) under development at Mol in Belgium and aiming to serve as a basis for the European experimental ADS to provide protons and neutrons for various R and D applications. It consists of a proton accelerator delivering a 350 MeV * 5 mA proton beam to a liquid Pb-Bi spallation target that in turn couples to a Pb-Bi cooled, subcritical fast core. In a first stage, the project focuses mainly on demonstration of the ADS concept, safety research on sub-critical systems and nuclear waste transmutation studies. In a later stage, the device will also be dedicated to research on structural materials, nuclear fuel, liquid metal technology and associated aspects and on sub-critical reactor physics. Subsequently, it will be used as fast spectrum irradiation facility and as radioisotope production facility. Along the above design features, the MYRRHA project team is developing the MYRRHA project as a multipurpose irradiation facility for R and D applications on the basis of an Accelerator Driven System (ADS). The project is intended to fit into the European strategy towards an ADS Demo facility for nuclear waste transmutation as described in the PDS-XADS FP5 Project. As such it should serve the following task catalogue: ADS concept demonstration, Safety studies for ADS, MA transmutation studies, LLFP transmutation studies, Medical radioisotopes, Material research, Fuel research. A first preliminary conceptual design file of MYRRHA was completed by the end of 2001 and has been reviewed by an International Technical Guidance Committee that concluded that there are no show stoppers in the project even thought some topics such as the safety studies and the fuel qualification need to be addressed

  2. High Energy Solid State Laser Research Facility

    Data.gov (United States)

    Federal Laboratory Consortium — A suite of laboratories with advanced spectroscopic and laser equipment, this facility develops materials and techniques for advanced solid state high energy lasers....

  3. Decommissioning of Medical, Industrial and Research Facilities. Safety Guide

    International Nuclear Information System (INIS)

    2010-01-01

    Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of medical, industrial and research facilities where radioactive materials and sources are produced, received, used and stored. It is intended to provide guidance to national authorities and operating organizations, particularly to those in developing countries (as such facilities are predominant in these countries), for the planning and safe management of the decommissioning of such facilities. The Safety Guide has been prepared through a series of Consultants meetings and a Technical Committee meeting

  4. Decommissioning of medical, industrial and research facilities. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

    Radioactive waste is produced in the generation of nuclear power and the use of radioactive materials in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized, and considerable experience has been gained in this field. The IAEA's Radioactive Waste Safety Standards Programme aimed at establishing a coherent and comprehensive set of principles and requirements for the safe management of waste and formulating the guidelines necessary for their application. This is accomplished within the IAEA Safety Standards Series in an internally consistent set of publications that reflect an international consensus. The publications will provide Member States with a comprehensive series of internationally agreed publications to assist in the derivation of, and to complement, national criteria, standards and practices. The Safety Standards Series consists of three categories of publications: Safety Fundamentals, Safety Requirements and Safety Guides. With respect to the Radioactive Waste Safety Standards Programme, the set of publications is currently undergoing review to ensure a harmonized approach throughout the Safety Standards Series. This Safety Guide addresses the subject of decommissioning of medical, industrial and research facilities where radioactive materials and sources are produced, received, used and stored. It is intended to provide guidance to national authorities and operating organizations, particularly to those in developing countries (as such facilities are predominant in these countries), for the planning and safe management of the decommissioning of such facilities. The Safety Guide has been prepared through a series of Consultants meetings and a Technical Committee meeting

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

    International Nuclear Information System (INIS)

    Persiani, P.J.

    1975-02-01

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

  6. Technical - Economic Research for Passive Buildings

    Science.gov (United States)

    Miniotaite, Ruta

    2017-10-01

    A newly constructed passive house must save 80 % of heat resources; otherwise it is not a passive house. The heating energy demand of a passive building is less than 15 kWh/m2 per year. However, a passive house is something more than just an energy-saving house. This concept involves sustainable, high-quality, valuable, healthy and durable construction. Features of a passive house: high insulation of envelope components, high-quality windows, good tightness of the building, regenerative ventilation system and elimination of thermal bridges. The Energy Performance of Buildings Directive (EPBD) 61 requires all new public buildings to become near-zero energy buildings by 2019 and will be extended to all new buildings by 2021. This concept involves sustainable, high-quality, valuable, healthy and durable construction. Foundation, walls and roofs are the most essential elements of a house. The type of foundation for a private house is selected considering many factors. The article examines technological and structural solutions for passive buildings foundation, walls and roofs. The technical-economic comparison of the main structures of a passive house revealed that it is cheaper to install an adequately designed concrete slab foundation than to build strip or pile foundation and the floor separately. Timber stud walls are the cheapest wall option for a passive house and 45-51% cheaper compared to other options. The comparison of roofs and ceilings showed that insulation of the ceiling is 25% more efficient than insulation of the roof. The comparison of the main envelope elements efficiency by multiple-criteria evaluation methods showed that it is economically feasible to install concrete slab on ground foundation, stud walls with sheet cladding and a pitched roof with insulated ceiling.

  7. Research in artificial intelligence for nuclear facilities

    International Nuclear Information System (INIS)

    Uhrig, R.E.

    1990-01-01

    The application of artificial intelligence, in the form of expert systems and neural networks, to the control room activities in a nuclear power plant has the potential to reduce operator error and increase plant safety, reliability, and efficiency. Furthermore, artificial intelligence can increase efficiency and effectiveness in a large number of nonoperating activities (testing, routine maintenance, outage planning, equipment diagnostics, and fuel management) and in research facility experiments. Recent work at the University of Tennessee has demonstrated the feasibility of using neural networks to identify six different transients introduced into the simulation of a steam generator of a nuclear power plant. This work is now being extended to utilize data from a nuclear power plant training simulator. In one configuration, the inputs to the neural network are a subset of the quantities that are typical of those available from the safety parameter display system. The outputs of the network represent the various states of the plant (e.g., normal operation, coolant leakage, inadequate core flow, excessive peak fuel temperature, etc.). Training of the neural network is performed by introducing various faults or conditions to be diagnosed into the simulator. The goal of this work is to demonstrate a neural network diagnostic system that could provide advice to the operators in accordance with the emergency operating procedures

  8. Radwaste requirements at a biomedical research facility

    International Nuclear Information System (INIS)

    Brannegan, D.P.; Wolter, W.; Merenda, J.M.; Figdor, S.K.

    1993-01-01

    The low-level radioactive waste (LLRW) federal legislation that was passed during the 1980s was intended to provide an orderly system of LLRW disposal as the country's three waste sites proceeded toward excluding out-of-state generators. The system was based on a regional interstate compact system. As originally envisioned, several contiguous states were to form an association (compact) with one state receiving radwaste from the compact. Everyone is aware of the difficulties that followed as attempts were made to implement these laws and to meet the prescribed milestones to avoid financial penalties. Although the states (compacts) have labored for over 12 yr along this rocky road, no compact has developed and licensed a new disposal site prior to the January 1, 1993 deadline. A recent report by the Center for the Study of American Business at Washington University in St. Louis states that open-quotes The current regional interstate compact system for disposal of low-level radioactive waste is fatally flawed on both technical and practical political grounds.close quotes Thus, the system has broken down and the three original LLRW sites closed their gates (with the possible exception of Barnwell) as planned on January 1, 1993. It would appear that the fate of LLRW will be the same as that of high-level waste (HLW); it will be stored at the site of the generator until a solution to the problem is found. For the nonutility generator, storage is an entirely new problem. It must be appreciated that almost all nonutility generators are in the business of research or medical treatment and not in the business of storing LLRW. Thus, storage represents a new turn of events and a new aspect of doing business. It also means the diversion of limited resources to a problem that should not exist. Lastly, on-site LLRW storage for the nonutility generator will also require additional regulatory approval for the handling, storage, and ongoing monitoring of this waste

  9. Sanford Underground Research Facility - The United State's Deep Underground Research Facility

    Science.gov (United States)

    Vardiman, D.

    2012-12-01

    The 2.5 km deep Sanford Underground Research Facility (SURF) is managed by the South Dakota Science and Technology Authority (SDSTA) at the former Homestake Mine site in Lead, South Dakota. The US Department of Energy currently supports the development of the facility using a phased approach for underground deployment of experiments as they obtain an advanced design stage. The geology of the Sanford Laboratory site has been studied during the 125 years of operations at the Homestake Mine and more recently as part of the preliminary geotechnical site investigations for the NSF's Deep Underground Science and Engineering Laboratory project. The overall geology at DUSEL is a well-defined stratigraphic sequence of schist and phyllites. The three major Proterozoic units encountered in the underground consist of interbedded schist, metasediments, and amphibolite schist which are crosscut by Tertiary rhyolite dikes. Preliminary geotechnical site investigations included drift mapping, borehole drilling, borehole televiewing, in-situ stress analysis, laboratory analysis of core, mapping and laser scanning of new excavations, modeling and analysis of all geotechnical information. The investigation was focused upon the determination if the proposed site rock mass could support the world's largest (66 meter diameter) deep underground excavation. While the DUSEL project has subsequently been significantly modified, these data are still available to provide a baseline of the ground conditions which may be judiciously extrapolated throughout the entire Proterozoic rock assemblage for future excavations. Recommendations for facility instrumentation and monitoring were included in the preliminary design of the DUSEL project design and include; single and multiple point extensometers, tape extensometers and convergence measurements (pins), load cells and pressure cells, smart cables, inclinometers/Tiltmeters, Piezometers, thermistors, seismographs and accelerometers, scanners (laser

  10. Combustion Research Facility | A Department of Energy Office of Science

    Science.gov (United States)

    Collaborative Research Facility Back to Sandia National Laboratory Homepage Combustion Research Search the CRF Combustion Chemistry Flame Chemistry Research.Combustion_Chemistry.Flame_Chemistry Theory and Modeling Theory and Modeling Combustion Kinetics High Pressure Chemistry Chemistry of Autoignition

  11. Research Facilities for the Future of Nuclear Energy

    International Nuclear Information System (INIS)

    Ait Abderrahim, H.

    1996-01-01

    The proceedings of the ENS Class 1 Topical Meeting on Research facilities for the Future of Nuclear Energy include contributions on large research facilities, designed for tests in the field of nuclear energy production. In particular, issues related to facilities supporting research and development programmes in connection to the operation of nuclear power plants as well as the development of new concepts in material testing, nuclear data measurement, code validation, fuel cycle, reprocessing, and waste disposal are discussed. The proceedings contain 63 papers

  12. 50 Years of the Radiological Research Accelerator Facility (RARAF)

    OpenAIRE

    Marino, Stephen A.

    2017-01-01

    The Radiological Research Accelerator Facility (RARAF) is in its 50th year of operation. It was commissioned on April 1, 1967 as a collaboration between the Radiological Research Laboratory (RRL) of Columbia University, and members of the Medical Research Center of Brookhaven National Laboratory (BNL). It was initially funded as a user facility for radiobiology and radiological physics, concentrating on monoenergetic neutrons. Facilities for irradiation with MeV light charged particles were d...

  13. Research on accelerator-driven transmutation and studies of experimental facilities

    Energy Technology Data Exchange (ETDEWEB)

    Takizuka, Takakazu [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-11-01

    JAERI is carrying out R and Ds on accelerator-driven transmutation systems under the national OMEGA Program that aims at development of the technology to improve efficiency and safety in the final disposal of radioactive waste. Research facilities for accelerator-driven transmutation experiments are proposed to construct within the framework of the planned JAERI Neutron Science Project. This paper describes the features of the proposed accelerator-driven transmutation systems and their technical issues to be solved. A research facility plan under examination is presented. The plan is divided in two phases. In the second phase, technical feasibility of accelerator-driven systems will be demonstrated with a 30-60 MW experimental integrated system and with a 7 MW high-power target facility. (author)

  14. Shock Thermodynamic Applied Research Facility (STAR)

    Data.gov (United States)

    Federal Laboratory Consortium — The STAR facility, within Sandia's Solid Dynamic Physics Department, is one of a few institutions in the world with a major shock-physics program. This is the only...

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

    Science.gov (United States)

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

    1985-01-01

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

  16. Trends in animal use at US research facilities.

    Science.gov (United States)

    Goodman, Justin; Chandna, Alka; Roe, Katherine

    2015-07-01

    Minimising the use of animals in experiments is universally recognised by scientists, governments and advocates as an ethical cornerstone of research. Yet, despite growing public opposition to animal experimentation, mounting evidence that animal studies often do not translate to humans, and the development of new research technologies, a number of countries have reported increased animal use in recent years. In the USA--one of the world's largest users of animals in experiments--a lack of published data on the species most commonly used in laboratories (eg, mice, rats and fish) has prevented such assessments. The current study aimed to fill this gap by analysing the use of all vertebrate animals by the top institutional recipients of National Institutes of Health research funds over a 15-year period. These data show a statistically significant 72.7% increase in the use of animals at these US facilities during this time period-driven primarily by increases in the use of mice. Our results highlight a need for greater efforts to reduce animal use. We discuss technical, institutional, sociological and psychological explanations for this trend. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://group.bmj.com/group/rights-licensing/permissions.

  17. Relationships between economic and technical research in nuclear power complex

    International Nuclear Information System (INIS)

    Drahny, M.; Martinek, J.

    1984-01-01

    The period from projecting and construction to operation and decommissioning of a nuclear power plant spans approximately 5a years. During this period it is necessary to resolve a range of technical, economic and social research problems. Even more complicated is the nuclear power complex as a whole. The respective technical and economic aspects are interactive and cannot be solved separately. It is therefore suggested that the respective national research and development program be linked with the national program of economic research, this both at the preparatory stage, in the course of work and during the evaluation of achieved results. (Ha)

  18. Research highlights from the Holifield Heavy Ion Research Facility

    International Nuclear Information System (INIS)

    Plasil, F.

    1982-01-01

    The purpose of this paper is to present the scope of research carried out at the new Holifield Heavy Ion Research Facility (HHIRF) at Oak Ridge. This will be accomplished with reference to several research projects currently underway. The areas of research represented are microscopic and macroscopic aspects of nuclear reactions and nuclear structure. In view of the scope of this conference, emphasis will be placed on nuclear reactions. A brief description of HHIRF is given, together with its current status. Microscopic aspects of reactions between nuclei are discussed with reference to the prospects for the study of giant resonances by means of heavy ions, and to studies of elastic and inelastic scattering of 60 Ni nuclei. Macroscopic aspects of nuclear reactions are illustrated by means of the study of collisions between 58 Ni nuclei at 15.1 MeV/u and by means of Spin Spectrometer (crystal ball) studies of the 19 F + 159 Tb reaction. Results are presented for lifetime measurements of high-spin states in ytterbium nuclei

  19. Trends of researches for fusion engineering research facility (FERF)

    International Nuclear Information System (INIS)

    Ozawa, Yasutomo; Enoto, Takeaki

    1975-01-01

    The role of a fusion neutron radiation test facility in the development of a scientific feasibility experimental reactor or demonstration fusion power reactor plant would be analogous to the role of the materials testing and experimental reactors in the development of fission power reactor. While the material testing fission reactor has been developed after successful operation of fission reactors, in the case of fusion reactor development it is desirable to realize the fusion engineering research facility (FERF) in-phase to the development of SFX and/or demonstration fusion power reactor plants. Here so called FERF in near future is the Controlled Thermonuclear Reactor which provides the high-intensity and high-energy neutron and plasma source whether the net power output is produced or not. From the point of direct attainment to SFX, we would like to emphasize that FEFE is the royal road leading to the goal of successful achievement of CTR program and could be useful for the experiment on impurity effects caused by neutron and plasma irradiations onto the wall material for SFX. Further, we rather suppose that hybrid FERF-fission assembly could be fairly and easily realizable in near future. (auth.)

  20. Hydrogen Infrastructure Testing and Research Facility Video (Text Version)

    Science.gov (United States)

    grid integration, continuous code improvement, fuel cell vehicle operation, and renewable hydrogen Systems Integration Facility or ESIF. Research projects including H2FIRST, component testing, hydrogen

  1. 78 FR 8500 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2013-02-06

    ... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy Biomass Research and... Biomass Research and Development Technical Advisory Committee. The Federal Advisory Committee Act (Pub. L... fuels and biobased products. Tentative Agenda: Agenda will include the following: Update on USDA Biomass...

  2. 76 FR 9339 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2011-02-17

    ... DEPARTMENT OF ENERGY Office of Energy Efficiency and Renewable Energy Biomass Research and... Biomass Research and Development Technical Advisory Committee under Section 9008(d) of the Food.... Tentative Agenda: Agenda will include the following: Update on USDA Biomass R&D Activities. Update on DOE...

  3. Future Directions for Research on Online Technical Education

    Science.gov (United States)

    Horvitz, Brian S.

    2017-01-01

    Most research on online learning in higher education has been focused on general education at four-year institutions. There is a need for more research that focuses on online and hybrid education at community colleges in technical education fields. This issue includes articles from eight National Science Foundation funded projects doing innovative…

  4. 76 FR 22091 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2011-04-20

    ... DEPARTMENT OF ENERGY Energy Efficiency and Renewable Energy Biomass Research and Development Technical Advisory Committee AGENCY: Energy Efficiency and Renewable Energy, Department of Energy. ACTION: Notice of Open Meeting. SUMMARY: This notice announces an open meeting of the Biomass Research and...

  5. An outline of research facilities of high intensity proton accelerator

    International Nuclear Information System (INIS)

    Tanaka, Shun-ichi

    1995-01-01

    A plan called PROTON ENGINEERING CENTER has been proposed in JAERI. The center is a complex composed of research facilities and a beam shape and storage ring based on a proton linac with an energy of 1.5 GeV and an average current of 10 mA. The research facilities planned are OMEGA·Nuclear Energy Development Facility, Neutron Facility for Material Irradiation, Nuclear Data Experiment Facility, Neutron Factory, Meson Factory, spallation Radioisotope Beam Facility, and Medium Energy Experiment Facility, where high intensity proton beam and secondary particle beams such as neutrons, π-mesons, muons, and unstable isotopes originated from the protons are available for promoting the innovative research of nuclear energy and basic science and technology. (author)

  6. Bat habitat research. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    Keller, B.L.; Bosworth, W.R.; Doering, R.W.

    1993-12-31

    This progress report describes activities over the current reporting period to characterize the habitats of bats on the INEL. Research tasks are entitled Monitoring bat habitation of caves on the INEL to determine species present, numbers, and seasons of use; Monitor bat use of man-made ponds at the INEL to determine species present and rates of use of these waters; If the Big Lost River is flowing on the INEL and/or if the Big Lost River sinks contain water, determine species present, numbers and seasons of use; Determine the habitat requirement of Townsend`s big-eared bats, including the microclimate of caves containing Townsend`s big-eared bats as compared to other caves that do not contain bats; Determine and describe an economical and efficient bat census technique to be used periodically by INEL scientists to determine the status of bats on the INEL; and Provide a suggestive management and protective plan for bat species on the INEL that might, in the future, be added to the endangered and sensitive list;

  7. Basic and technical research on lung cancer

    International Nuclear Information System (INIS)

    Miyamoto, Tadaaki

    2004-01-01

    In association with clinical study of carbon beam therapy for lung cancer, the basic research for lung cancer and the patients with this disease has been carried out for the past 10 years. With regard to lung damage by the carbon beams, firstly pulmonary function was measured and analyzed for the patients with stage I non-small cell lung cancer. Force expiratory volume in 1 second (FVE 1.0) and TLC (total lung capacity) was found to be reduced significantly at 6 and 12 months after therapy but the reduction rate was a little, which can support the safety of this treatment modality. Secondly, the regional lung damage by the beams was investigated by using correct fusion of CT images with carbon beam dose distribution, diagnostic follow-up CT images and blood flow and ventilation spect images. It demonstrated the graded decrease blood flow by dose and the compensatory increase of blood flow in the adjacent lobe of lung unexposed to irradiation. On the other hand, the biological study of carbon beam effects on lung cancer cells and tumors line was conducted. Firstly, by using 7 or 4 human lung cancer cell line, the radiosensitivity of carbon beams was compared with that of photons by different histological patterns. It was found that there was no essential difference in the sensitivity pattern for lung cancer histology between the carbon beams and photons though the former doubled the later in power. Secondly, by using IA cell lines among them, the dynamic of clonogenic cells (clonogen) in a nude tumor and the changes in its morphology following irradiation was investigated, clarifying that the clonogen proliferating under anoxic or hypoxic conditions played a pivotal role for tumor regrowth and stemmed from the different clone which had been genetically selected and developed under these conditions. The finding of clonogen becomes one of the evidence supporting the superiority of a single-dose radiotherapy to fractionated radiotherapy. (author)

  8. Native American Technical Assistance and Training for Renewable Energy Resource Development and Electrical Generation Facilities Management

    Energy Technology Data Exchange (ETDEWEB)

    A. David Lester

    2008-10-17

    The Council of Energy Resource Tribes (CERT) will facilitate technical expertise and training of Native Americans in renewable energy resource development for electrical generation facilities, and distributed generation options contributing to feasibility studies, strategic planning and visioning. CERT will also provide information to Tribes on energy efficiency and energy management techniques.This project will provide facilitation and coordination of expertise from government agencies and private industries to interact with Native Americans in ways that will result in renewable energy resource development, energy efficiency program development, and electrical generation facilities management by Tribal entities. The intent of this cooperative agreement is to help build capacity within the Tribes to manage these important resources.

  9. Staff technical position on regulatory considerations in the design and construction of the exploratory shaft facility

    International Nuclear Information System (INIS)

    Gupta, D.; Peshel, J.; Bunting, J.

    1991-07-01

    The staff of the US Nuclear Regulatory Commission has prepared this staff technical position for the purpose of compiling and further clarifying previous staff positions on regulatory considerations in the design and construction of the exploratory shaft facility (ESF). (The US Department of Energy (DOE) now refers to the ESF as the ''exploratory studies facility.'' DOE's change in terminology does not affect the positions taken in this guidance.) This document lists the key regulations in 10 CFR Part 60 that should be considered in the design and construction of the ESF and presents the staff position statements and corresponding discussions. 13 refs., 1 fig

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

    International Nuclear Information System (INIS)

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

    1985-04-01

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

  11. 48 CFR 801.602-80 - Legal and technical review-Office of Construction and Facilities Management and National Cemetery...

    Science.gov (United States)

    2010-10-01

    ...-Office of Construction and Facilities Management and National Cemetery Administration. 801.602-80 Section... Responsibilities 801.602-80 Legal and technical review-Office of Construction and Facilities Management and National Cemetery Administration. An Office of Construction and Facilities Management or National Cemetery...

  12. The Soreq Applied Research Accelerator Facility (SARAF): Overview, research programs and future plans

    Science.gov (United States)

    Mardor, Israel; Aviv, Ofer; Avrigeanu, Marilena; Berkovits, Dan; Dahan, Adi; Dickel, Timo; Eliyahu, Ilan; Gai, Moshe; Gavish-Segev, Inbal; Halfon, Shlomi; Hass, Michael; Hirsh, Tsviki; Kaiser, Boaz; Kijel, Daniel; Kreisel, Arik; Mishnayot, Yonatan; Mukul, Ish; Ohayon, Ben; Paul, Michael; Perry, Amichay; Rahangdale, Hitesh; Rodnizki, Jacob; Ron, Guy; Sasson-Zukran, Revital; Shor, Asher; Silverman, Ido; Tessler, Moshe; Vaintraub, Sergey; Weissman, Leo

    2018-05-01

    The Soreq Applied Research Accelerator Facility (SARAF) is under construction in the Soreq Nuclear Research Center at Yavne, Israel. When completed at the beginning of the next decade, SARAF will be a user facility for basic and applied nuclear physics, based on a 40 MeV, 5 mA CW proton/deuteron superconducting linear accelerator. Phase I of SARAF (SARAF-I, 4 MeV, 2 mA CW protons, 5 MeV 1 mA CW deuterons) is already in operation, generating scientific results in several fields of interest. The main ongoing program at SARAF-I is the production of 30 keV neutrons and measurement of Maxwellian Averaged Cross Sections (MACS), important for the astrophysical s-process. The world leading Maxwellian epithermal neutron yield at SARAF-I (5 × 10^{10} epithermal neutrons/s), generated by a novel Liquid-Lithium Target (LiLiT), enables improved precision of known MACSs, and new measurements of low-abundance and radioactive isotopes. Research plans for SARAF-II span several disciplines: precision studies of beyond-Standard-Model effects by trapping light exotic radioisotopes, such as 6He, 8Li and 18, 19, 23Ne, in unprecedented amounts (including meaningful studies already at SARAF-I); extended nuclear astrophysics research with higher energy neutrons, including generation and studies of exotic neutron-rich isotopes relevant to the rapid (r-) process; nuclear structure of exotic isotopes; high energy neutron cross sections for basic nuclear physics and material science research, including neutron induced radiation damage; neutron based imaging and therapy; and novel radiopharmaceuticals development and production. In this paper we present a technical overview of SARAF-I and II, including a description of the accelerator and its irradiation targets; a survey of existing research programs at SARAF-I; and the research potential at the completed facility (SARAF-II).

  13. Corium melt researches at VESTA test facility

    Directory of Open Access Journals (Sweden)

    Hwan Yeol Kim

    2017-10-01

    Full Text Available VESTA (Verification of Ex-vessel corium STAbilization and VESTA-S (-small test facilities were constructed at the Korea Atomic Energy Research Institute in 2010 to perform various corium melt experiments. Since then, several tests have been performed for the verification of an ex-vessel core catcher design for the EU-APR1400. Ablation tests of an impinging ZrO2 melt jet on a sacrificial material were performed to investigate the ablation characteristics. ZrO2 melt in an amount of 65–70 kg was discharged onto a sacrificial material through a well-designed nozzle, after which the ablation depths were measured. Interaction tests between the metallic melt and sacrificial material were performed to investigate the interaction kinetics of the sacrificial material. Two types of melt were used: one is a metallic corium melt with Fe 46%, U 31%, Zr 16%, and Cr 7% (maximum possible content of U and Zr for C-40, and the other is a stainless steel (SUS304 melt. Metallic melt in an amount of 1.5–2.0 kg was delivered onto the sacrificial material, and the ablation depths were measured. Penetration tube failure tests were performed for an APR1400 equipped with 61 in-core instrumentation penetration nozzles and extended tubes at the reactor lower vessel. ZrO2 melt was generated in a melting crucible and delivered down into an interaction crucible where the test specimen is installed. To evaluate the tube ejection mechanism, temperature distributions of the reactor bottom head and in-core instrumentation penetration were measured by a series of thermocouples embedded along the specimen. In addition, lower vessel failure tests for the Fukushima Daiichi nuclear power plant are being performed. As a first step, the configuration of the molten core in the plant was investigated by a melting and solidification experiment. Approximately 5 kg of a mixture, whose composition in terms of weight is UO2 60%, Zr 10%, ZrO2 15%, SUS304 14%, and B4C 1%, was melted in a

  14. Metering management at the plutonium research and development facilities

    International Nuclear Information System (INIS)

    Hirata, Masaru; Miyamoto, Fujio; Kurosawa, Makoto; Abe, Jiro; Sakai, Haruyuki; Suzuki, Tsuneo.

    1996-01-01

    Nuclear fuel research laboratory of the Oarai Research Laboratory of the Japan Atomic Energy Research Institute is an R and D facility to treat with plutonium and processes various and versatile type samples in chemical and physical form for use of various experimental researches even though on much small amount. Furthermore, wasted and plutonium samples are often transported to other KMP and MBA such as radioactive waste management facility, nuclear reactor facility and so forth. As this facility is a place to treat plutonium important on the safeguards, it is a facility necessary for detection and allowance actions and for detail managements on the metering management data to report to government and IAEA in each small amount sample and different configuration. In this paper, metering management of internationally regulated matters and metering management system using a work station newly produced in such small scale facility were introduced. (G.K.)

  15. DOE research and development and field facilities

    Energy Technology Data Exchange (ETDEWEB)

    1979-06-01

    This report describes the roles of DOE's headquarters, field offices, major multiprogram laboratories, Energy Technology and Mining Operations Centers, and other government-owned, contractor-operated facilities which are located in all regions of the United States. It gives brief descriptions of resources, activities, and capabilities of each field facility (sections III through V). These represent a cumulative capital investment of $12 billion and involve a work force of approximately 12,000 government (field) employees and approximately 100,000 contractor employees.

  16. Radiological, technical and financial planning for decommissioning of small nuclear facilities in Sweden - 16177

    International Nuclear Information System (INIS)

    Lindskog, Staffan; Sjoeblom, Rolf

    2009-01-01

    On November 1 2008, a new ordinance came into force in Sweden. It extends the implementation of nuclear liability to all nuclear facilities and companies, regardless of size. The Government has authorized the Swedish Radiation Safety Authority (SSM) to issue further regulation as warranted and appropriate, and commissioned the same Authority to oversee the implementation. Consequently, SSM is presently conducting research in order to establish a basis for the implementation of the ordinance to smaller facilities and enterprises. The goal is to enable finance to be assured in an efficient manner so that any burden on the companies is as small as possible. Thus, 'functional requirements' are identified, and used as a basis for various investigations. The aspects include technical and cost calculation prerequisites, as well as various domains of law: the environmental code, radiation and nuclear safety, financial reporting, and criminal law. It is found that the basis for the differentiation among the facility operators and owners should be the cost and the associated uncertainty. Thus, a cost calculation will have to be carried out by all. It should be based on available standards and guidance documents. It is found that this is a requirement that already exists elsewhere in the legislation, and thus no additional burden is imposed on the companies. It is found that segregated funds is the preferred option for long-term liabilities. Securities are suitable for short-term liabilities provided that the economy of the company in question is sound. Securities might also be used for long-term liabilities to cover uncertainty. It is proposed that a de minimis limit of at least kSEK 25 (about keuros 2,4 and k$ 3,4) is used. An important reason for this is that lower limits might be incompatible with the rules for financial reporting. It is also proposed that securities might be used also for long-term commitments if the total environmental liability does not exceed 1

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

    International Nuclear Information System (INIS)

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

    2010-01-01

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

  18. Tritium research and technology facilities at the JRC-Ispra

    International Nuclear Information System (INIS)

    Dworschak, H.; Mannone, F.; Perujo, A.; Pierini, G.; Reiter, F.; Vassallo, G.; Viola, A.; Camposilvan, J.; Douglas, K.; Grassi, G.; Lolli Ceroni, P.; Simonetta, A.; Spelta, B.

    1990-01-01

    A set of experiments which are of prominent interest for the development of nuclear fusion technology in Europe are planned by the JRC-Ispra for the near future, in the frame of experimental activities to be performed in ETHEL, the European Tritium Handling Experimental Laboratory under construction at the Ispra site. These experiments already included for the most part as JRC-Task Action Sheets in the 1989-1991 European Technology Programme Actions will initiate in ETHEL on a fully active laboratory scale starting mid-1991. They will concern the following research areas: Recycling of tritium from first wall materials; Tritium recovery from water cooled Pb-17Li blankets; Detritiation of ventilation atmospheres; Plasma exhaust processing; Tritiazed waste management. In view of fully active tritium experiments in ETHEL and to obtain information of the basic processes involved, since 1985 preparatory experimental studies are being performed at the JRC-Ispra laboratories using hydrogen and deuterium. Furthermore, always with regard to ETHEL experiments, particular attention is given to possible technical and managerial problems which potentially may arise in this context. To identify at an early stage such problems a questionnaire has been developed and distributed to researchers in conjunction with an ETHEL information packet. The questionnaire demands information regarding the scope, design and operation of the intended experiment as well as planning and required support to be supplied by ETHEL. A brief description of experimental preparatory studies and future tritium handling experiments in ETHEL as well of the ETHEL facility is here presented. (orig.)

  19. Research using small tokamaks. Proceedings of a technical committee meeting

    International Nuclear Information System (INIS)

    1997-09-01

    The technical reports in these proceedings were presented at the IAEA Technical Committee Meeting on research Using Small Tokamaks, held in Ahmedabad, India, 6-7 December 1995. The purpose of this annual meeting is to provide a forum for the exchange of information on various small and medium sized plasma experiments, not only for tokamaks. The potential benefits of these research programmes are to: test theories, such as effects of the plasma rotation; check empirical scalings, such as density limits; develop fusion technology hardware; develop plasma diagnostics; such as tomography; and to train scientists, engineers, technicians, and students, particularly in developing IAEA Member States

  20. Scientific and technical photography at NASA Langley Research Center

    Science.gov (United States)

    Davidhazy, Andrew

    1994-01-01

    As part of my assignment connected with the Scientific and Technical Photography & Lab (STPL) at the NASA Langley Research Center I conducted a series of interviews and observed the day to day operations of the STPL with the ultimate objective of becoming exposed first hand to a scientific and technical photo/imaging department for which my school prepares its graduates. I was also asked to share my observations with the staff in order that these comments and observations might assist the STPL to better serve its customers. Meetings with several individuals responsible for various wind tunnels and with a group that provides photo-optical instrumentation services at the Center gave me an overview of the services provided by the Lab and possible areas for development. In summary form these are some of the observations that resulted from the interviews and daily contact with the STPL facility. (1) The STPL is perceived as a valuable and almost indispensable service group within the organization. This comment was invariably made by everyone. Everyone also seemed to support the idea that the STPL continue to provide its current level of service and quality. (2) The STPL generally is not perceived to be a highly technically oriented group but rather as a provider of high quality photographic illustration and documentation services. In spite of the importance and high marks assigned to the STPL there are several observations that merit consideration and evaluation for possible inclusion into the STPL's scope of expertise and future operating practices. (1) While the care and concern for artistic rendition of subjects is seen as laudable and sometimes valuable, the time that this often requires is seen as interfering with keeping the tunnels operating at maximum productivity. Tunnel managers would like to shorten down-time due to photography, have services available during evening hours and on short notice. It may be of interest to the STPL that tunnel managers are

  1. Process Technical Basis Documentation Diagram for a solid-waste processing facility

    International Nuclear Information System (INIS)

    Benar, C.J.; Petersen, C.A.

    1994-02-01

    The Process Technical Basis Documentation Diagram is for a solid-waste processing facility that could be designed to treat, package, and certify contact-handled mixed low-level waste for permanent disposal. The treatment processes include stabilization using cementitious materials and immobilization using a polymer material. The Diagram identifies several engineering/demonstration activities that would confirm the process selection and process design. An independent peer review was conducted at the request of Westinghouse Hanford Company to determine the technical adequacy of the technical approach for waste form development. The peer review panel provided comments and identified documents that it felt were needed in the Diagram as precedence for Title I design. The Diagram is a visual tool to identify traceable documentation of key activities, including those documents suggested by the peer review, and to show how they relate to each other. The Diagram is divided into three sections: (1) the Facility section, which contains documents pertaining to the facility design, (2) the Process Demonstration section, which contains documents pertaining to the process engineering/demonstration work, and 3) the Regulatory section, which contains documents describing the compliance strategy for each acceptance requirement for each feed type, and how this strategy will be implemented

  2. Advancing nuclear technology and research. The advanced test reactor national scientific user facility

    Energy Technology Data Exchange (ETDEWEB)

    Benson, Jeff B; Marshall, Frances M [Idaho National Laboratory, Idaho Falls, ID (United States); Allen, Todd R [Univ. of Wisconsin, Madison, WI (United States)

    2012-03-15

    The Advanced Test Reactor (ATR), at the Idaho National Laboratory (INL), is one of the world's premier test reactors for providing the capability for studying the effects of intense neutron and gamma radiation on reactor materials and fuels. The INL also has several hot cells and other laboratories in which irradiated material can be examined to study material radiation effects. In 2007 the US Department of Energy (DOE) designated the ATR as a National Scientific User Facility (NSUF) to facilitate greater access to the ATR and the associated INL laboratories for material testing research. The mission of the ATR NSUF is to provide access to world-class facilities, thereby facilitating the advancement of nuclear science and technology. Cost free access to the ATR, INL post irradiation examination facilities, and partner facilities is granted based on technical merit to U.S. university-led experiment teams conducting non-proprietary research. Proposals are selected via independent technical peer review and relevance to United States Department of Energy. To increase overall research capability, ATR NSUF seeks to form strategic partnerships with university facilities that add significant nuclear research capability to the ATR NSUF and are accessible to all ATR NSUF users. (author)

  3. Technical Support Section Instrument Support Program for nuclear and nonnuclear facilities with safety requirements

    International Nuclear Information System (INIS)

    Adkisson, B.P.; Allison, K.L.

    1995-01-01

    This document describes requirements, procedures, and supervisory responsibilities of the Oak Ridge National Laboratory (ORNL) Instrumentation and Controls (I ampersand C) Division's Technical Support Section (TSS) for instrument surveillance and maintenance in nonreactor nuclear facilities having identified Operational Safety Requirements (OSRs) or Limiting Conditions Document (LCDs). Implementation of requirements comply with the requirements of U.S. Department of Energy (DOE) Orders 5480.5, 5480.22, and 5481.1B; Martin Marietta Energy Systems, Inc. (Energy Systems), Policy Procedure ESS-FS-201; and ORNL SPP X-ESH-15. OSRs and LCDs constitute an agreement or contract between DOE and the facility operating management regarding the safe operation of the facility. One basic difference between OSRs and LCDs is that violation of an OSR is considered a Category II occurrence, whereas violation of an LCD requirement is considered a Category III occurrence (see Energy Systems Standard ESS-OP-301 and ORNL SPP X-GP-13). OSRs are required for high- and moderate-hazard nuclear facilities, whereas the less-rigorous LCDs are required for low-hazard nuclear facilities and selected open-quotes generally acceptedclose quotes operations. Hazard classifications are determined through a hazard screening process, which each division conducts for its facilities

  4. Staff Technical Position on geological repository operations area underground facility design: Thermal loads

    International Nuclear Information System (INIS)

    Nataraja, M.S.

    1992-12-01

    The purpose of this Staff Technical Position (STP) is to provide the US Department of Energy (DOE) with a methodology acceptable to the Nuclear Regulatory Commission staff for demonstrating compliance with 10 CFR 60.133(i). The NRC staff's position is that DOE should develop and use a defensible methodology to demonstrate the acceptability of a geologic repository operations area (GROA) underground facility design. The staff anticipates that this methodology will include evaluation and development of appropriately coupled models, to account for the thermal, mechanical, hydrological, and chemical processes that are induced by repository-generated thermal loads. With respect to 10 CFR 60.133(i), the GROA underground facility design: (1) should satisfy design goals/criteria initially selected, by considering the performance objectives; and (2) must satisfy the performance objectives 10 CFR 60.111, 60.112, and 60.113. The methodology in this STP suggests an iterative approach suitable for the underground facility design

  5. Naval Research Laboratory Major Facilities 2008

    Science.gov (United States)

    2008-10-01

    consists of two equipment shelters, a chiller for cooling the transmitter, and a 175 kVA diesel generator for use at remote sites. A 40-ft-long... bioremediation , and biodeterioration. INSTRUMENTATION: • ESEM equipped with an energy-dispersive X-ray detector and an image acquisition and...a 125 kW uninterruptible power system with diesel backup. Magnetic sensitivity testing of precision Precision Clock Evaluation Facility CONTACT

  6. Decontamination Technology Development for Nuclear Research Facilities

    International Nuclear Information System (INIS)

    Oh, Won Zin; Jung, Chong Hun; Choi, Wang Kyu; Won, Hui Jun; Kim, Gye Nam

    2004-02-01

    Technology development of surface decontamination in the uranium conversion facility before decommissioning, technology development of component decontamination in the uranium conversion facility after decommissioning, uranium sludge treatment technology development, radioactive waste soil decontamination technology development at the aim of the temporary storage soil of KAERI, Optimum fixation methodology derivation on the soil and uranium waste, and safety assessment methodology development of self disposal of the soil and uranium waste after decontamination have been performed in this study. The unique decontamination technology applicable to the component of the nuclear facility at room temperature was developed. Low concentration chemical decontamination technology which is very powerful so as to decrease the radioactivity of specimen surface under the self disposal level was developed. The component decontamination technology applicable to the nuclear facility after decommissioning by neutral salt electro-polishing was also developed. The volume of the sludge waste could be decreased over 80% by the sludge waste separation method by water. The electrosorption method on selective removal of U(VI) to 1 ppm of unrestricted release level using the uranium-containing lagoon sludge waste was tested and identified. Soil decontamination process and equipment which can reduce the soil volume over 90% were developed. A pilot size of soil decontamination equipment which will be used to development of real scale soil decontamination equipment was designed, fabricated and demonstrated. Optimized fixation methodology on soil and uranium sludge was derived from tests and evaluation of the results. Safety scenario and safety evaluation model were development on soil and uranium sludge aiming at self disposal after decontamination

  7. Web server for the administrative and technical documentation of the radiodiagnostic facilities

    Energy Technology Data Exchange (ETDEWEB)

    Soto, M; Campayo, J. M; Guardia, V. [Logistica y Acondicionamientos Industriales SAU, Sorolla Center, Local 10, Av. de las Cortes Valencianas No. 58, 46015 Valencia (Spain); Mayo, P., E-mail: m.soto@lainsa.co [TITANIA Servicios Tecnologicos SL, Sorolla Center, Local 10, Av. de las Cortes Valencianas No. 58, 46015 Valencia (Spain)

    2010-10-15

    Nowadays Radiological Protection Technical Unit of LAINSA as part of Grupo Dominguis, has assigned radiological security tasks in a high number of medical X-ray facilities. It is recognised by the Nuclear Security Council as a specialist in the assessment of protection against the radiological risks associated with medical, industrial and nuclear activities. It is also authorised as an external personal dosimetry centre. Concretely medical X-ray facilities generate big amount of information because of national regulatory authority to assure the good functioning of it. This information is formed by administrative procedures for the regulatory authority in industrial and public health area, periodic quality controls of the radiographic equipment s, radiological verification in different locations to measure the radioactivity levels, certificates of employees training to work with radioactivity, dosimetric registrations of professional exposure employees and medical aptitude documents for their job, etc. In this paper it is presented a net server application to manage this information in an effective way by web. In this server each facility has an online net space with private key access and where there are all the administrative documents and nuclear security reports of the facility. Moreover, the client who is responsible of the radiological security of the centre, can have at any moment all this information, minimizing delay times and optimizing the information store support in electronic format. The objective is that this information can be updated for consulting, modifying or checking at anytime quickly and safety. All this information has to be accessible for the interested medical facility, for the Radiological Protection Technical Unit which has been contracted by the facility to do the assessment in radiological protection and for the regulatory authority in nuclear security to guarantee well-practice in medical and nuclear activities. (Author)

  8. Massachusetts Institute of Technology, Plasma Fusion Center, Technical Research Programs

    International Nuclear Information System (INIS)

    1980-08-01

    A review is given of the technical programs carried out by the Plasma Fusion Center. The major divisions of work areas are applied plasma research, confinement experiments, fusion technology and engineering, and fusion systems. Some objectives and results of each program are described

  9. Massachusetts Institute of Technology, Plasma Fusion Center, Technical Research Programs

    Energy Technology Data Exchange (ETDEWEB)

    Davidson, Ronald C.

    1980-08-01

    A review is given of the technical programs carried out by the Plasma Fusion Center. The major divisions of work areas are applied plasma research, confinement experiments, fusion technology and engineering, and fusion systems. Some objectives and results of each program are described. (MOW)

  10. Content Analysis as a Best Practice in Technical Communication Research

    Science.gov (United States)

    Thayer, Alexander; Evans, Mary; McBride, Alicia; Queen, Matt; Spyridakis, Jan

    2007-01-01

    Content analysis is a powerful empirical method for analyzing text, a method that technical communicators can use on the job and in their research. Content analysis can expose hidden connections among concepts, reveal relationships among ideas that initially seem unconnected, and inform the decision-making processes associated with many technical…

  11. Ohio Marketing Management and Research. Technical Competency Profile (TCP).

    Science.gov (United States)

    Ray, Gayl M.; Wilson, Nick; Mangini, Rick

    This document provides a framework for a broad-based secondary and postsecondary curriculum to prepare students for employment in marketing management and research (MMR). The first part of the technical competency profile (TCP) contains the following items: an explanation of the purpose and scope of Ohio's TCPs; college tech prep program…

  12. Educational Choice Regarding Technical Education: Research with Case Study

    Science.gov (United States)

    Kacerauskas, Tomas; Šaparauskas, Jonas

    2017-01-01

    In first part, the models, theories, mechanisms and presumptions, as well as the ideas of educational choice discourse have been scrutinized. In the second part, the survey on educational choice at Vilnius Gediminas Technical University, Lithuania has been presented. The methodology used in this research is a survey of respondents and survey…

  13. [The Engineering and Technical Services Directorate at the Glenn Research Center

    Science.gov (United States)

    Moon, James

    2004-01-01

    My name is James Moon and I am a senior at Tennessee State University where my major is Aeronautical and Industrial Technology with a concentration in industrial electronics. I am currently serving my internship in the Engineering and Technical Services Directorate at the Glenn Research Center (GRC). The Engineering and Technical Service Directorate provides the services and infrastructure for the Glenn Research Center to take research concepts to reality. They provide a full range of integrated services including engineering, advanced prototyping and testing, facility management, and information technology for NASA, industry, and academia. Engineering and Technical Services contains the core knowledge in Information Technology (IT). This includes data systems and analysis, inter and intranet based systems design and data security. Including the design and development of embedded real-time s o h a r e applications for flight and supporting ground systems, Engineering and Technical Services provide a wide range of IT services and products specific to the Glenn Research Center research and engineering community. In the 7000 Directorate I work directly in the 7611 organization. This organization is known as the Aviation Environments Technical Branch. My mentor is Vincent Satterwhite who is also the Branch Chief of the Aviation Environments Technical Branch. In this branch, I serve as the Assistant program manager of the Engineering Technology Program. The Engineering Technology Program (ETP) is one of three components of the High School L.E.R.C.I.P. This is an Agency-sponsored, eight-week research-based apprenticeship program designed to attract traditionally underrepresented high school students that demonstrate an aptitude for and interest in mathematics, science, engineering, and technology.

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

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-31

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

  15. Planning and implementation of Istanbul Technical University TRIGA research reactor program

    International Nuclear Information System (INIS)

    Aybers, N.; Yavuz, H.; Bayulken, A.

    1982-01-01

    The Istanbul Technical University TRIGA Research Reactor at the Institute for Nuclear Energy, which went critical on March 11, 1979 is basically a pulsing type TRIGA Mark - II reactor. Completion of the ITU-TRR contributed to broaden the role of the Institute for Nuclear Energy of the Technical University in Istanbul in the nuclear field by providing for the first time adequate on-campus experimental facilities for nuclear engineering studies to ITU students. The research program which is currently under planning at ITU-NEE encompasses: a) Neutron activation analysis studies by techniques and applications to chemistry, mining, materials research, archaeological and biomedical studies; b) applications of Radioisotopes; c) Radiography with reactor neutron beams; d) Radiation Pulsing

  16. National facility for neutron beam research

    Indian Academy of Sciences (India)

    In this talk, the growth of neutron beam research (NBR) in India over the past five decades is traced beginning with research at Apsara. A range of problems in condensed matter physics could be studied at CIRUS, followed by sophisticated indegenous instrumentation and research at Dhruva. The talk ends with an overview ...

  17. A low-temperature research facility for space

    International Nuclear Information System (INIS)

    Donnelly, R.J.

    1991-01-01

    The Jet Propulsion Laboratory is proposing to NASA a new initiative to construct a Low Temperature Research Facility for use in space. The facility is described, together with some details of timing and support. An advisory group has been formed which seeks to advise JPL and NASA of the capabilities required in this facility and to invite investigators to propose experiments which require the combination of low temperature and reduced gravity to be successful. (orig.)

  18. Technical and safe development features of modern research reactor

    International Nuclear Information System (INIS)

    Wang Jiaying; Dong Duo

    1998-01-01

    The development trend of research reactor in the world, and development situation in China are introduced. Up to now, some research reactors have serviced for long time and equipment have aged, not to be satisfied for requirement of science and technology development. New research reactors must been developed. The technical features and safe features of new type research reactor in China, for example: multi-pile utilization, compact core of high flux, high automation level of control, reactor two independent shutdown systems, great coefficient of negative temperature, passive safety systems, reliable residual heat removal system are studied

  19. Preliminary technical data summary for the Defense Waste Processing Facility, Stage 1

    International Nuclear Information System (INIS)

    1980-09-01

    This Preliminary Technical Data Summary presents the technical basis for design of Stage 1 of the Staged Defense Waste Processing Facility (DWPF), a process to efficiently immobilize the radionuclides in Savannah River Plant (SRP) high-level liquid waste. The radionuclides in SRP waste are present in sludge that has settled to the bottom of waste storage tanks and in crystallized salt and salt solution (supernate). Stage 1 of the DWPF receives washed, aluminum dissolved sludge from the waste tank farms and immobilizes it in a borosilicate glass matrix. The supernate is retained in the waste tank farms until completion of Stage 2 of the DWPF at which time it filtered and decontaminated by ion exchange in the Stage 2 facility. The decontaminated supernate is concentrated by evaporation and mixed with cement for burial. The radioactivity removed from the supernate is fixed in borosilicate glass along with the sludge. This document gives flowsheets, material, and curie balances, material and curie balance bases, and other technical data for design of the Stage 1 DWPF

  20. Functional design criteria for an exploratory shaft facility in salt: Technical report

    International Nuclear Information System (INIS)

    1986-11-01

    The purpose of the Functional Criteria for Design is to provide technical direction for the development of detailed design criteria for the exploratory shaft facility. This will assure that the exploratory shaft facility will be designed in accordance with the current Mission Plan as well as the Nuclear Waste Policy Act and 10 CFR Part 60, which will facilitate the licensing process. The functional criteria for design are not intended to limit or constrain the designer's flexibility. The following philosophies will be incorporated in the designs: (1) The exploratory shaft will be designed to fulfill its intended purpose which is to characterize the salt site by subsurface testing; (2) the design will minimize any adverse impact which the facility may cause to the environment and any damage to the site if it should be found suitable for a repository; (3) the health and safety of the public and of the workers will be an essential factor in the design; (4) sound engineering principles and practices will be consistently employed in the design process; (5) the exploratory shaft and related surface and subsurface facilities will be designed to be economical and reliable in construction, operation, and maintenance; and (6) the exploratory shaft facility will be designed in accordance with applicable federal, state, and local regulations, as well as all applicable national consensus codes and standards

  1. Hypervelocity Expansion Facility for Fundamental High-Enthalpy Research

    Science.gov (United States)

    2017-02-27

    ii Final Technical Report of Contract ONR N00014-15-1-2260 Entitled: HYPERVELOCITY EXPANSION FACILITY FOR FUNDAMENTAL HIGH-ENTHALPY...previous DoD investments in high-energy pulsed laser diagnostics for instantaneous planar velocimetry and thermometry to perform scientific studies of...capability for fundamental and applied studies of hypervelocity high enthalpy flows. In this document, we report on the progress over the 18-month

  2. Digital media in the home: technical and research challenges

    Science.gov (United States)

    Ribas-Corbera, Jordi

    2005-03-01

    This article attempts to identify some of the technology and research challenges facing the digital media industry in the future. We first discuss several trends in the industry, such as the rapid growth of broadband Internet networks and the emergence of networking and media-capable devices in the home. Next, we present technical challenges that result from these trends, such as effective media interoperability in devices, and provide a brief overview of Windows Media, which is one of the technologies in the market attempting to address these challenges. Finally, given these trends and the state of the art, we argue that further research on data compression, encoder optimization, and multi-format transcoding can potentially make a significant technical and business impact in digital media. We also explore the reasons that research on related techniques such as wavelets or scalable video coding is having a relatively minor impact in today"s practical digital media systems.

  3. Conceptual design of technical security systems for Russian nuclear facilities physical protection

    International Nuclear Information System (INIS)

    Izmailov, A.V.

    1995-01-01

    Conceptual design of technical security systems (TSS) used in the early stages of physical protection systems (PPS) design for Russia nuclear facilities is discussed. The importance of work carried out in the early stages was noted since the main design solutions are being made within this period (i.e. selection of a structure of TSS and its components). The methods of analysis and synthesis of TSS developed by ''Eleron'' (MINATOM of Russia) which take into account the specific conditions of Russian nuclear facilities and a scope of equipment available are described in the review. TSS effectiveness assessment is based on a probability theory and a simulation. The design procedure provides for a purposeful choice of TSS competitive options including a ''cost-benefit'' criterion and taking into account a prechosen list of design basis threats to be used for a particular facility. The attention is paid to a practical aspect of the methods application as well as to the bilateral Russian-American scientific and technical co-operation in the PPS design field

  4. Integrating research, legal technical assistance, and advocacy to inform shared use legislation in Mississippi.

    Science.gov (United States)

    Spengler, John O; Frost, Natasha R; Bryant, Katherine K

    2014-01-01

    The purpose of this article was to describe the process by which research findings informed the successful passage of legislation designed to increase opportunities for physical activity in Mississippi, and discuss implications and lessons learned from this process. The article is descriptive and conceptual, and addresses the collaborative process by which research, legal technical assistance, and advocacy informed and shaped shared use legislation in Mississippi. Collaborators informing this article were an Active Living Research grantee, a staff attorney with the Public Health Law Center, the American Heart Association Mississippi Government Relations Director, and community partners. The American Heart Association and Public Health Law Center developed policy guidance in the form of sample language for legislation as a starting point for states in determining policy needed to eliminate or reduce barriers to the shared use of school recreational facilities. The policy guidance was informed by evidence from Active Living Research-funded research studies. The American Heart Association, supporting a bill shaped by the policy guidance, led the effort to advocate for successful shared use legislation in Mississippi. Research should be policy relevant and properly translated and disseminated. Legal technical assistance should involve collaboration with both researchers and advocates so that policymakers have the information to make evidence-based decisions. Government relations directors should collaborate with legal technical staff to obtain and understand policy guidance relevant to their advocacy efforts. Effective collaborations, with an evidence-based approach, can lead to informed, successful policy change.

  5. Accelerator based research facility as an inter university centre

    International Nuclear Information System (INIS)

    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)

  6. Radiation applications research and facilities in AECL Research Company

    International Nuclear Information System (INIS)

    Iverson, S.L.

    1988-01-01

    In the 60's and 70's Atomic Energy of Canada had a very active R and D program to discover and develop applications of ionizing radiation. Widespread interest in the use of radiation for food processing and the possibility of developing reliable and competitive machine sources of radiation hold out the promise of a major increase in industrial use of radiation. In March 1985 a new branch, Radiation Applications Research, began operations with the objective of working closely with industry to develop and assist the introduction of new uses of ionizing radiation. The Branch is equipped with appropriate analytical equipment including HPLC (high performance liquid chromatograph) and GC/MS (gas chromatograph/mass spectrometer) as well as a Gammacell 220 and an I-10/1, one kilowatt 10 MeV electron accelerator. The accelerator is located in a specially designed facility equipped for experimental irradiation of the test quantities of packaged products as well as solids, liquids and gases in various configurations. A conveyor system moves the packaged products from the receiving area, through a maze, past the electron beam at a controlled rate and finally to the shipping area. Other necessary capabilities, such as gamma and electron dosimetry and a microbiology laboratory, have also been developed. Initial projects in areas ranging from food through environmental and industrial applications have been assessed and the most promising have been selected for further work. As an example, the use of charcoal absorbent beds to concentrate the components of gas or liquid waste streams requiring treatment is showing promise as a method of significantly reducing the cost of radiation treatment for some effluents. A number of other projects are described. (author)

  7. Profiles of facilities used for HTR research and testing

    International Nuclear Information System (INIS)

    1980-05-01

    This report contains a current description of facilities supporting HTR research and development submitted by countries participating in the IWGFR. It has the purpose of providing an overview of the facilities available for use and of the types of experiments that can be conducted therein

  8. Technical editing of research reports in biomedical journals.

    Science.gov (United States)

    Wager, Elizabeth; Middleton, Philippa

    2008-10-08

    Most journals try to improve their articles by technical editing processes such as proof-reading, editing to conform to 'house styles', grammatical conventions and checking accuracy of cited references. Despite the considerable resources devoted to technical editing, we do not know whether it improves the accessibility of biomedical research findings or the utility of articles. This is an update of a Cochrane methodology review first published in 2003. To assess the effects of technical editing on research reports in peer-reviewed biomedical journals, and to assess the level of accuracy of references to these reports. We searched The Cochrane Library Issue 2, 2007; MEDLINE (last searched July 2006); EMBASE (last searched June 2007) and checked relevant articles for further references. We also searched the Internet and contacted researchers and experts in the field. Prospective or retrospective comparative studies of technical editing processes applied to original research articles in biomedical journals, as well as studies of reference accuracy. Two review authors independently assessed each study against the selection criteria and assessed the methodological quality of each study. One review author extracted the data, and the second review author repeated this. We located 32 studies addressing technical editing and 66 surveys of reference accuracy. Only three of the studies were randomised controlled trials. A 'package' of largely unspecified editorial processes applied between acceptance and publication was associated with improved readability in two studies and improved reporting quality in another two studies, while another study showed mixed results after stricter editorial policies were introduced. More intensive editorial processes were associated with fewer errors in abstracts and references. Providing instructions to authors was associated with improved reporting of ethics requirements in one study and fewer errors in references in two studies, but no

  9. Radiation applications research and facilities in AECL research company

    Science.gov (United States)

    Iverson, S. L.

    In the 60's and 70's Atomic Energy of Canada had a very active R&D program to discover and develop applications of ionizing radiation. Out of this grew the technology underlying the company's current product line of industrial irradiators. With the commercial success of that product line the company turned its R&D attention to other activities. Presently, widespread interest in the use of radiation for food processing and the possibility of developing reliable and competitive machine sources of radiation hold out the promise of a major increase in industrial use of radiation. While many of the applications being considered are straightforward applications of existing knowledge, others depend on more subtle effects including combined effects of two or more agents. Further research is required in these areas. In March 1985 a new branch, Radiation Applications Research, began operations with the objective of working closely with industry to develop and assist the introduction of new uses of ionizing radiation. The Branch is equipped with appropriate analytical equipment including HPLC (high performance liquid chromatograph) and GC/MS (gas chromatograph/mass spectrometer) as well as a Gammacell 220 and an I-10/1, one kilowatt 10 MeV electron accelerator. The accelerator is located in a specially designed facility equipped for experimental irradiation of test quantities of packaged products as well as solids, liquids and gases in various configurations. A conveyor system moves the packaged products from the receiving area, through a maze, past the electron beam at a controlled rate and finally to the shipping area. Other necessary capabilities, such as gamma and electron dosimetry and a microbiology laboratory, have also been developed. Initial projects in areas ranging from food through environmental and industrial applications have been assessed and the most promising have been selected for further work. As an example, the use of charcoal adsorbent beds to concentrate

  10. Feasibility study to develop BNCT facility at the Indonesian research reactor

    International Nuclear Information System (INIS)

    Hastowo, H.

    2001-01-01

    A survey on the Indonesian research reactors and its supporting facilities has been done in order to check the possibility to install BNCT facility. Oncologists from several hospitals have been informing about the BNCT treatment for tumours and they give a positive response to support utilisation of the BNCT facility. Several aspects required to support the BNCT treatment have also been identified and related activities on that matter soon will be initiated. The interim result in our survey indicated that utilisation of the 30 MW Multipurpose reactor would not be possible from the technical point of view. Further study will be concentrated on the TRIGA reactor and an epithermal neutron beam facility at the thermal column of this reactor will be designed for further work. (author)

  11. Automated Generation of Technical Documentation and Provenance for Reproducible Research

    Science.gov (United States)

    Jolly, B.; Medyckyj-Scott, D.; Spiekermann, R.; Ausseil, A. G.

    2017-12-01

    Data provenance and detailed technical documentation are essential components of high-quality reproducible research, however are often only partially addressed during a research project. Recording and maintaining this information during the course of a project can be a difficult task to get right as it is a time consuming and often boring process for the researchers involved. As a result, provenance records and technical documentation provided alongside research results can be incomplete or may not be completely consistent with the actual processes followed. While providing access to the data and code used by the original researchers goes some way toward enabling reproducibility, this does not count as, or replace, data provenance. Additionally, this can be a poor substitute for good technical documentation and is often more difficult for a third-party to understand - particularly if they do not understand the programming language(s) used. We present and discuss a tool built from the ground up for the production of well-documented and reproducible spatial datasets that are created by applying a series of classification rules to a number of input layers. The internal model of the classification rules required by the tool to process the input data is exploited to also produce technical documentation and provenance records with minimal additional user input. Available provenance records that accompany input datasets are incorporated into those that describe the current process. As a result, each time a new iteration of the analysis is performed the documentation and provenance records are re-generated to provide an accurate description of the exact process followed. The generic nature of this tool, and the lessons learned during its creation, have wider application to other fields where the production of derivative datasets must be done in an open, defensible, and reproducible way.

  12. Technical design report of spallation neutron source facility in J-PARC

    International Nuclear Information System (INIS)

    Sakamoto, Shinichi

    2012-02-01

    One of the experimental facilities in Japan Proton Accelerator Research Complex (J-PARC) is the Materials and Life Science Experimental Facility (MLF), where high-intensity neutron beams are used as powerful probes for basic research on materials and life science, as well as research and development in industrial engineering. Neutrons are generated with nuclear spallation reaction by bombarding a mercury target with high-intensity proton beams. The neutrons are slowed down with supercritical hydrogen moderators and then extracted as beams to each experimental apparatus. The principal design of the spallation neutron source is compiled in this comprehensive report. (author)

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

    International Nuclear Information System (INIS)

    1988-07-01

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

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

    International Nuclear Information System (INIS)

    1986-05-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    1986-05-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    1988-07-01

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

  17. Technical report on natural evaporation system for radioactive liquid waste treatment arising from TRIGA research reactors' decontamination and decommissioning activities

    International Nuclear Information System (INIS)

    Moon, J. S.; Jung, K. J.; Baek, S. T.; Jung, U. S.; Park, S. K.; Jung, K. H.

    1999-01-01

    This technical report described that radioactive liquid waste treatment for dismantling/decontamination of TRIGA Mark research reactor in Seoul. That is, we try safety treatment of operation radioactive liquid waste during of operating TRIGA Mark research reactor and dismantling radioactive liquid waste during R and D of research reactor hereafter, and by utilizing of new natural evaporation facility with describing design criteria of new natural evaporation facility. Therefore, this technical report described the quantity of present radioactive liquid waste and dismantling radioactive liquid waste hereafter, analysis the status of radial-rays/radioactivity, and also treatment method of this radioactive liquid waste. Also, we derived the method that the safeguard of outskirts environment and the cost down of radioactive liquid waste treatment by minimize of the radioactive liquid waste quantities, through-out design/operation of new natural evaporation facility for treatment of operation radioactive liquid waste and dismantling radioactive liquid waste. (author). 6 refs., 12 tabs., 5 figs

  18. Introduction of neutron research facilities in Indonesia Nuclear Agency

    International Nuclear Information System (INIS)

    Nishida, Masayuki; Muslih, M. Refai; Minakawa, Nobuaki

    2004-01-01

    In this report, some facilities for neutron diffraction installed in Indonesia nuclear Agency (BATAN) are introduced. Rough sketch of BATAN, and facility arrangement in the reactor hall and the guide hall are schematically shown. The four facilities (powder diffractometer, four-circle goniometer, three-axis goniometer and neutron radiography system) are installed in the reactor hall and the three (small angle neutron scattering (SANS), high resolution SANS and high resolution powder diffractometer) in the guide hall. Neutron wavelengths determined from four hk1 planes of standard Si powder by the BATAN's neutron diffraction facility are compared with those measured by the similar facility in Japan Atomic Energy Research Institute (JAERI). The neutron diffraction profile of W-fiber reinforced Cu composite is measured by the BATAN's facility. The experimental results show the strong 110 preferred orientation to the fiber direction. (author)

  19. Environment for Auditory Research Facility (EAR)

    Data.gov (United States)

    Federal Laboratory Consortium — EAR is an auditory perception and communication research center enabling state-of-the-art simulation of various indoor and outdoor acoustic environments. The heart...

  20. Small Multi-Purpose Research Facility (SMiRF)

    Data.gov (United States)

    Federal Laboratory Consortium — The Small Multi-Purpose Research Facility (SMiRF) evaluates the performance of the thermal protection systems required to provide long-term storage (up to 10 years)...

  1. Direct Connect Supersonic Combustion Facility (Research Cell 22)

    Data.gov (United States)

    Federal Laboratory Consortium — Description: RC22 is a continuous-flow, direct-connect supersonic-combustion research facility that is capable of simulating flight conditions from Mach 3.0 to Mach...

  2. IsoDAR@KamLAND: A Conceptual Design Report for the Technical Facility

    CERN Document Server

    Abs, M; Alonso, J R; Axani, S; Barletta, W A; Barlow, R; Bartoszek, L; Bungau, A; Calabretta, L; Calanna, A; Campo, D; Castro, G; Celona, L; Collin, G H; Conrad, J M; Gammino, S; Johnson, R; Karagiorgi, G; Kayser, S; Kleeven, W; Kolano, A; Labrecque, F; Loinaz, W A; Minervini, J; Moulai, M H; Okuno, H; Owen, H; Papavassiliou, V; Shaevitz, M H; Shimizu, I; Shokair, T M; Sorensen, K F; Spitz, J; Toups, M; Vagins, M; Van Bibber, K; Wascko, M O; Winklehner, D; Winslow, L A; Yang, J J

    2015-01-01

    This conceptual design report describes the technical facility for the IsoDAR electron-antineutrino source at KamLAND. The IsoDAR source will allow an impressive program of neutrino oscillation and electroweak physics to be performed at KamLAND. This report provides information on the physics case, the conceptual design for the subsystems, alternative designs considered, specifics of installation at KamLAND, and identified needs for future development. We discuss the risks we have identified and our approach to mitigating those risks with this design. A substantial portion of the conceptual design is based on three years of experimental efforts and on industry experience. This report also includes information on the conventional facilities.

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

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

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

  4. Development of technical design for waste processing and storage facilities for Novi Han repository

    International Nuclear Information System (INIS)

    Canizares, J.; Benitez, J.C.; Asuar, O.; Yordanova, O.; Demireva, E.; Stefanova, I.

    2005-01-01

    Empresarion Agrupados Internacional S.A. (Spain) and ENPRO Consult Ltd. (Bulgaria) were awarded a contract by the Central Finance and Contracts Unit to develop the technical design of the waste processing and storage facilities at the Novi Han repository. At present conceptual design phase is finished. This conceptual design covers the definition of the basic design requirements to be applied to the installations defined above, following both European and Bulgarian legislation. In this paper the following items are considered: 1) Basic criteria for the layout and sizing of buildings; 2) Processing of radioactive waste, including: treatment and conditioning of disused sealed sources; treatment of liquid radioactive wastes; treatment of solid radioactive waste; conditioning of liquid and solid radioactive waste; 3) Control of waste packages and 4) Storage of radioactive waste, including storage facility and waste packages. An analysis of inventories of stored and estimated future wastes and its subsequent processes is also presented and the waste streams are illustrated

  5. A facility for using cluster research to study environmental problems

    Energy Technology Data Exchange (ETDEWEB)

    1991-11-01

    This report begins by describing the general application of cluster based research to environmental chemistry and the development of a Cluster Structure and Dynamics Research Facility (CSDRF). Next, four important areas of cluster research are described in more detail, including how they can impact environmental problems. These are: surface-supported clusters, water and contaminant interactions, time-resolved dynamic studies in clusters, and cluster structures and reactions. These facilities and equipment required for each area of research are then presented. The appendices contain workshop agenda and a listing of the researchers who participated in the workshop discussions that led to this report.

  6. A facility for using cluster research to study environmental problems

    International Nuclear Information System (INIS)

    1991-11-01

    This report begins by describing the general application of cluster based research to environmental chemistry and the development of a Cluster Structure and Dynamics Research Facility (CSDRF). Next, four important areas of cluster research are described in more detail, including how they can impact environmental problems. These are: surface-supported clusters, water and contaminant interactions, time-resolved dynamic studies in clusters, and cluster structures and reactions. These facilities and equipment required for each area of research are then presented. The appendices contain workshop agenda and a listing of the researchers who participated in the workshop discussions that led to this report

  7. 76 FR 46781 - Biomass Research and Development Technical Advisory Committee

    Science.gov (United States)

    2011-08-03

    ..., 2011: 7:30 a.m.-2 p.m.; August 24, 2011: 7:30 a.m.-12:30 p.m. ADDRESSES: I Hotel, 1900 S. First Street... welcome to observe the business of the Biomass Research and Development Technical Advisory Committee. To... ext. 220; E- mail: hq.com ">[email protected] hq.com at least 7 business days prior to the meeting. Members...

  8. Toxic Hazards Research Unit Annual Technical Report: 1984

    Science.gov (United States)

    1984-09-01

    exposed to TOCP exhibited the classic lesions of delayed neuropathy (Smith and Lillie, 1931; Barnes and Denz, 1953; (avanagh, 1954; and Fenton , 1955...Safety of *.i Chemicals in Food, Drugs, and Cosmetics , The staff of the Divi- sion of Pharmacology of the Federal Food and Drug Administration, Austin...Annual Technical Report: 1967, AMRL-TR-67-137 (AD 834723), Aerospace Medical Research Laboratory, Wright-Patterson Air Force Base, Ohio. Fenton , J. C

  9. High energy physics research. Final technical report, 1957--1994

    International Nuclear Information System (INIS)

    Williams, H.H.

    1995-01-01

    This is the final technical report to the Department of Energy on High Energy Physics at the University of Pennsylvania. It discusses research conducted in the following areas: neutrino astrophysics and cosmology; string theory; electroweak and collider physics; supergravity; cp violation and baryogenesis; particle cosmology; collider detector at Fermilab; the sudbury neutrino observatory; B-physics; particle physics in nuclei; and advanced electronics and detector development

  10. High energy physics research. Final technical report, 1957--1994

    Energy Technology Data Exchange (ETDEWEB)

    Williams, H.H.

    1995-10-01

    This is the final technical report to the Department of Energy on High Energy Physics at the University of Pennsylvania. It discusses research conducted in the following areas: neutrino astrophysics and cosmology; string theory; electroweak and collider physics; supergravity; cp violation and baryogenesis; particle cosmology; collider detector at Fermilab; the sudbury neutrino observatory; B-physics; particle physics in nuclei; and advanced electronics and detector development.

  11. Technical review and evaluation for the installation of cold neutron source facility at HANARO

    International Nuclear Information System (INIS)

    Choi, Chang Woong; Kim, Dong Hoon; Lee, Mu Woong; Cho, Man Soon; Oh, Yun Woo; Park, Sun Hee; Park, Kuk Nam; Lee, Chang Hee

    1996-01-01

    The principle subjects of this study are to analyze the technical characteristics of cold neutron source(CNS) and take measures to cope with the matters regarding the installation of CNS facility at HANARO. This report, thus, reviews the current status of the CNS facilities that are now in operation worldwide and classifies the system and equipment to select the appropriate type for HANARO and provides advice and guidance for the future basic and detail design. As we have none of CNS facility here and very few experienced persons yet, this report provides some information for domestic users through the investigation of the utilization fields and experimental facilities of CNS, and presents the estimated total cost for the project based on JRR-3M. In addition, the work scope of the conceptual design, which will be performed in advance of the basic and detail design, and cooperative program with the countries having the advanced technology of CNS is presented in this report. 43 tabs., 57 figs., 22 refs. (Author)

  12. Confinement Physics Research Facility/ZTH: A progress report

    International Nuclear Information System (INIS)

    Hammer, C.F.; Thullen, P.

    1989-01-01

    In October 1985 the Los Alamos National Laboratory's Controlled Thermonuclear Research (CTR) Division began the design and construction of the Confinement Physics Research Facility (CPRF) and the ZTH toroidal, reversed-field-pinch (RFP), plasma physics experiment. The CPRF is a facility which will provide the buildings, utilities, pulsed power system, control system and diagnostics needed to operate a magnetically confined fusion experiment, and ZTH will be the first experiment operated in the facility. The construction of CPRF/ZTH is scheduled for completion in the first quarter of 1993. 5 figs

  13. Public Facilities Management and Action Research for Sustainability

    DEFF Research Database (Denmark)

    Galamba, Kirsten Ramskov

    Current work is the main product of a PhD study with the initial working title ‘Sustainable Facilities Management’ at Centre for Facilities Management – Realdania Research, DTU Management 1. December 2008 – 30. November 2011. Here the notion of Public Sustainable Facilities Management (FM......) is analysed in the light of a change process in a Danish Municipal Department of Public Property. Three years of Action Research has given a unique insight in the reality in a Municipal Department of Public Property, and as to how a facilitated change process can lead to a more holistic and sustainable...

  14. Research and test facilities required in nuclear science and technology

    International Nuclear Information System (INIS)

    2009-01-01

    Experimental facilities are essential research tools both for the development of nuclear science and technology and for testing systems and materials which are currently being used or will be used in the future. As a result of economic pressures and the closure of older facilities, there are concerns that the ability to undertake the research necessary to maintain and to develop nuclear science and technology may be in jeopardy. An NEA expert group with representation from ten member countries, the International Atomic Energy Agency and the European Commission has reviewed the status of those research and test facilities of interest to the NEA Nuclear Science Committee. They include facilities relating to nuclear data measurement, reactor development, neutron scattering, neutron radiography, accelerator-driven systems, transmutation, nuclear fuel, materials, safety, radiochemistry, partitioning and nuclear process heat for hydrogen production. This report contains the expert group's detailed assessment of the current status of these nuclear research facilities and makes recommendations on how future developments in the field can be secured through the provision of high-quality, modern facilities. It also describes the online database which has been established by the expert group which includes more than 700 facilities. (authors)

  15. Decontamination Technology Development for Nuclear Research Facilities

    International Nuclear Information System (INIS)

    Choi, W. K.; Jung, C. H.; Oh, W. Z.

    2007-06-01

    The originative CO 2 pellet blasting equipment was developed by improving additional components such as feed screw, idle roller and air-lock feeder to clear up the problems of freezing and discontinuity of blasting and by adopting pneumatically operated vacuum suction head and vacuum cup to prevent recontamination by collecting contaminant particulates simultaneously with the decontamination. The optimum decontamination process was established according to the kind of materials such as metal, concrete and plastic and the type of contaminants such as particulate, fixed chemical compound and oil. An excellent decontamination performances were verified by means of the lab-scale hot test with radioactive specimen and the technology demonstration in IMEF hot cell. The PFC dry decontamination equipment applicable to the surface contaminated with high radioactive particulate was developed. This equipment consists of the unit processes such as spray, collection, filtration and dry distillation designed originatively applicable to inside of dry hot cell. Through the demonstration of PFC spray decontamination process in IMEF hot cell, we secured on-site applicability and the decontamination efficiency more than 90 %. We investigated the characteristics of dismantled metal waste melting and the radionuclide(Co, Cs, U) distribution into ingot and slag by melting decontamination experiments using electric arc melter. We obtained the decontamination factors greater than 100 for Cs and of 10∼100 for uranium. The pilot scale(200 kg/batch) demonstration for melting decontamination was carried out successfully using high temperature melting facility at KAERI. The volume reduction factor of 1/7 and the economical feasibility of the melting decontamination were verified.

  16. IAEA Technical committee meeting on methods used in design of spent fuel storage facilities

    International Nuclear Information System (INIS)

    Vitikainen, E.; Silfverberg, P.

    1985-01-01

    The meeting was held in Espoo, Finland and hosted by the Technical Research Centre of Finland (VTT), and was arranged to report and discuss design methods, licensing practise, operational experience as well as economic aspects connectied with spent fuel storage. This report contains session summaries by the session chairmen and the papers presented at the meeting

  17. ARM Climate Research Facility Annual Report 2004

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, J.

    2004-12-31

    Like a rock that slowly wears away beneath the pressure of a waterfall, planet earth?s climate is almost imperceptibly changing. Glaciers are getting smaller, droughts are lasting longer, and extreme weather events like fires, floods, and tornadoes are occurring with greater frequency. Why? Part of the answer is clouds and the amount of solar radiation they reflect or absorb. These two factors clouds and radiative transfer represent the greatest source of error and uncertainty in the current generation of general circulation models used for climate research and simulation. The U.S. Global Change Research Act of 1990 established an interagency program within the Executive Office of the President to coordinate U.S. agency-sponsored scientific research designed to monitor, understand, and predict changes in the global environment. To address the need for new research on clouds and radiation, the U.S. Department of Energy (DOE) established the Atmospheric Radiation Measurement (ARM) Program. As part of the DOE?s overall Climate Change Science Program, a primary objective of the ARM Program is improved scientific understanding of the fundamental physics related to interactions between clouds and radiative feedback processes in the atmosphere.

  18. Leak testing requirements at a research facility

    International Nuclear Information System (INIS)

    Conner, J.B.

    1979-01-01

    Since September, 1952, Lawrence Livermore Laboratory has conducted pioneering research in applied science. A vital part of this activity has been the development of a variety of high vacuum and ultrahigh vacuum systems. Leaks occur in everything, including vacuum systems. The mass spectrometer leak detection equipment is described

  19. Progress report concerning safety research for nuclear reactor facilities

    International Nuclear Information System (INIS)

    1978-01-01

    Examination and evaluation of safety research results for nuclear reactor facilities have been performed, as more than a year has elapsed since the plan had been initiated in April, 1976, by the special sub-committee for the safety of nuclear reactor facilities. The research is carried out by being divided roughly into 7 items, and seems to be steadily proceeding, though it does not yet reach the target. The above 7 items include researches for (1) criticality accident, (2) loss of coolant accident, (3) safety for light water reactor fuel, (4) construction safety for reactor facilities, (5) reduction of release of radioactive material, (6) safety evaluation based on the probability theory for reactor facilities, and (7) aseismatic measures for reactor facilities. With discussions on the progress and the results of the research this time, research on the behaviour on fuel in abnormal transients including in-core and out-core experiments has been added to the third item, deleting the power-cooling mismatch experiment in Nuclear Safety Research Reactor of JAERI. Also it has been decided to add two research to the seventh item, namely measured data collection, classification and analysis, and probability assessment of failures due to an earthquake. For these 7 items, the report describes the concrete contents of research to be performed in fiscal years of 1977 and 1978, by discussing on most rational and suitable contents conceivable at present. (Wakatsuki, Y.)

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

    International Nuclear Information System (INIS)

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

    1998-03-01

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

  1. Dispersion fuel for nuclear research facilities

    International Nuclear Information System (INIS)

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

    2017-01-01

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

  2. Nuclear Safety Research and Facilities Department. Annual report 1999

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E. [eds.

    2000-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  3. Nuclear Safety Research and Facilities Department annual report 1999

    DEFF Research Database (Denmark)

    Majborn, B.; Damkjær, A.; Jensen, Per Hedemann

    2000-01-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department´s research and development activities were organized in two research programmes: "Radiation Protection and Reactor Safety" and"Radioecology and Tracer Studies". The nuclear...... facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are includedtogether with a summary of the staff´s participation in national and international committees....

  4. Nuclear Safety Research and Facilities Department annual report 1997

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Aarkrog, A.; Brodersen, K. [and others

    1998-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1997. The department`s research and development activities were organized in four research programmes: Reactor Safety, Radiation protection, Radioecology, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the educational reactor DR1. Lists of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au) 11 tabs., 39 ills.; 74 refs.

  5. Nuclear Safety Research and Facilities Department annual report 1998

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E

    1999-04-01

    The report present a summary of the work of the Nuclear Safety Research and Facilities Department in 1998. The department`s research and development activities were organized in two research programmes: `Radiation Protection and Reactor Safety` and `Radioecology and Tracer Studies`. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment plant, and the educational reactor DR1. Lsits of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au)

  6. Nuclear Safety Research and Facilities Department. Annual report 1999

    International Nuclear Information System (INIS)

    Majborn, B.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E.

    2000-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  7. Nuclear Safety Research and Facilities department annual report 1996

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Floto, H.; Heydorn, K.; Oelgaard, P.L.

    1997-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1996. The Department's research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au) 2 tabs., 28 ills

  8. Nuclear Safety Research and Facilities Department annual report 1997

    International Nuclear Information System (INIS)

    Majborn, B.; Aarkrog, A.; Brodersen, K.

    1998-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1997. The department's research and development activities were organized in four research programmes: Reactor Safety, Radiation protection, Radioecology, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the educational reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  9. Nuclear Safety Research and Facilities Department annual report 1998

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E.

    1999-04-01

    The report present a summary of the work of the Nuclear Safety Research and Facilities Department in 1998. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment plant, and the educational reactor DR1. Lsits of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  10. Conceptual designs of near surface disposal facility for radioactive waste arising from the facilities using radioisotopes and research facilities for nuclear energy development and utilization

    International Nuclear Information System (INIS)

    Sakai, Akihiro; Yoshimori, Michiro; Okoshi, Minoru; Yamamoto, Tadatoshi; Abe, Masayoshi

    2001-03-01

    Various kinds of radioactive waste is generating from the utilization of radioisotopes in the field of science, technology, etc. and the utilization and development of nuclear energy. In order to promote the utilization of radionuclides and the research activities, it is necessary to treat and dispose of radioactive waste safely and economically. Japan Nuclear Cycle Development Institute (JNC), Japan Radioisotope Association (JRIA) and Japan Atomic Energy Research Institute (JAERI), which are the major waste generators in Japan in these fields, are promoting the technical investigations for treatment and disposal of the radioactive waste co-operately. Conceptual design of disposal facility is necessary to demonstrate the feasibility of waste disposal business and to determine the some conditions such as the area size of the disposal facility. Three institutes share the works to design disposal facility. Based on our research activities and experiences of waste disposal, JAERI implemented the designing of near surface disposal facilities, namely, simple earthen trench and concrete vaults. The designing was performed based on the following three assumed site conditions to cover the future site conditions: (1) Case 1 - Inland area with low groundwater level, (2) Case 2 - Inland area with high groundwater level, (3) Case 3 - Coastal area. The estimation of construction costs and the safety analysis were also performed based on the designing of facilities. The safety assessment results show that the safety for concrete vault type repository is ensured by adding low permeability soil layer, i.e. mixture of soil and bentonite, surrounding the vaults not depending on the site conditions. The safety assessment results for simple earthen trench also show that their safety is ensured not depending on the site conditions, if they are constructed above groundwater levels. The construction costs largely depend on the depth for excavation to build the repositories. (author)

  11. The Safety and Tritium Applied Research (STAR) Facility: Status-2004

    International Nuclear Information System (INIS)

    Anderl, R.A.; Longhurst, G.R.; Pawelko, R.J.; Sharpe, J.P.; Schuetz, S.T.; Petti, D.A.

    2005-01-01

    The Safety and Tritium Applied Research (STAR) Facility, a US DOE National User Facility at the Idaho National Engineering and Environmental Laboratory (INEEL), comprises capabilities and infrastructure to support both tritium and non-tritium research activities important to the development of safe and environmentally friendly fusion energy. Research thrusts include (1) interactions of tritium and deuterium with plasma-facing-component (PFC) materials, (2) fusion safety issues [PFC material chemical reactivity and dust/debris generation, activation product mobilization, tritium behavior in fusion systems], and (3) molten salts and fusion liquids for tritium breeder and coolant applications. This paper updates the status of STAR and the capabilities for ongoing research activities, with an emphasis on the development, testing and integration of the infrastructure to support tritium research activities. Key elements of this infrastructure include a tritium storage and assay system, a tritium cleanup system to process glovebox and experiment tritiated effluent gases, and facility tritium monitoring systems

  12. Progress towards a new Canadian irradiation-research facility

    International Nuclear Information System (INIS)

    Lee, A.G.; Lidstone, R.F.

    1993-01-01

    As reported at the second meeting of the International Group on Research Reactors, Atomic Energy of Canada Limited (AECL) is evaluating its options for future irradiation facilities. During the past year significant progress has been made towards achieving consensus on the irradiation requirements for AECL's major research programs and interpreting those requirements in terms of desirable characteristics for experimental facilities in a research reactor. The next stage of the study involves identifying near-term and long-term options for irradiation-research facilities to meet the requirements. The near-term options include assessing the availability of the NRU reactor and the capabilities of existing research reactors. The long-term options include developing a new irradiation-research facility by adapting the technology base for the MAPLE-X10 reactor design. Because materials testing in support of CANDU power reactors dominates AECL's irradiation requirements, the new reactor concept is called the MAPLE Materials Testing Reactor (MAPLE-MTR). Parametric physics and engineering studies are in progress on alternative MAPLE-MTR configurations to assess the capabilities for the following types of test facilities: - fast-neutron sites, that accommodate materials-irradiation assemblies, - small-diameter vertical fuel test loops that accommodate multielement assemblies, - large-diameter vertical fuel test loops, each able to hold one or more CANDU fuel bundles, - horizontal test loops, each able to hold full-size CANDU fuel bundles or small-diameter multi-element assemblies, and - horizontal beam tubes

  13. Radiation monitoring in high energy research facility

    International Nuclear Information System (INIS)

    Miyajima, Mitsuhiro

    1975-01-01

    In High Energy Physics Research Laboratory, construction of high energy proton accelerator is in progress. The accelerator is a cascaded machine comprising Cockcroft type (50 keV), linac (20 MeV), booster synchrotron (500 MeV), and synchrotron (8-12 GeV). Its proton beam intensity is 1x10 13 photons/pulse, and acceleration is carried out at the rate of every 2 minutes. The essential problems of radiation control in high energy accelerators are those of various radiations generated secondarily by proton beam and a number of induced radiations simultaneously originated with such secondary particles. In the Laboratory, controlled areas are divided into color-coded four regions, red, orange, yellow and green, based on each dose-rate. BF 3 counters covered with thick paraffin are used as neutron detectors, and side-window GM tubes, NaI (Tl) scintillators and ionization chambers as γ-detectors. In red region, however, ionization chambers are applied to induced radiation detection, and neutrons are not monitored. NIM standards are adopted for the circuits of all above monitors considering easy maintenance, economy and interchangeability. Notwithstanding the above described systems, these monitors are not sufficient to complete the measurement of whole radiations over wide energy region radiated from the accelerators. Hence separate radiation field measurement is required periodically. An example of the monitoring systems in National Accelerator Laboratory (U.S.) is referred at the last section. (Wakatsuki, Y.)

  14. Decommissioning Technology Development for Nuclear Research Facilities

    International Nuclear Information System (INIS)

    Lee, K. W.; Kang, Y. A.; Kim, G. H.

    2007-06-01

    It is predicted that the decommissioning of a nuclear power plant would happen in Korea since 2020 but the need of partial decommissioning and decontamination for periodic inspection and life extension still has been on an increasing trend and its domestic market has gradually been extended. Therefore, in this project we developed following several essential technologies as a decommissioning R and D. The measurement technology for in-pipe radioactive contamination was developed for measuring alpha/beta/gamma emitting nuclides simultaneously inside a in-pipe and it was tested into the liquid waste transfer pipe in KRR-2. And the digital mock-up system for KRR-1 and 2 was developed for choosing the best scenarios among several scenarios on the basis of various decommissioning information(schedule, waste volume, cost, etc.) that are from the DMU and the methodology of decommissioning cost estimation was also developed for estimating a research reactor's decommissioning cost and the DMU and the decommissioning cost estimation system were incorporated into the decommissioning information integrated management system. Finally the treatment and management technology of the irradiated graphites that happened after decommissioning KRR-2 was developed in order to treat and manage the irradiated graphites safely

  15. Decommissioning Technology Development for Nuclear Research Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lee, K. W.; Kang, Y. A.; Kim, G. H. (and others)

    2007-06-15

    It is predicted that the decommissioning of a nuclear power plant would happen in Korea since 2020 but the need of partial decommissioning and decontamination for periodic inspection and life extension still has been on an increasing trend and its domestic market has gradually been extended. Therefore, in this project we developed following several essential technologies as a decommissioning R and D. The measurement technology for in-pipe radioactive contamination was developed for measuring alpha/beta/gamma emitting nuclides simultaneously inside a in-pipe and it was tested into the liquid waste transfer pipe in KRR-2. And the digital mock-up system for KRR-1 and 2 was developed for choosing the best scenarios among several scenarios on the basis of various decommissioning information(schedule, waste volume, cost, etc.) that are from the DMU and the methodology of decommissioning cost estimation was also developed for estimating a research reactor's decommissioning cost and the DMU and the decommissioning cost estimation system were incorporated into the decommissioning information integrated management system. Finally the treatment and management technology of the irradiated graphites that happened after decommissioning KRR-2 was developed in order to treat and manage the irradiated graphites safely.

  16. Irradiation Facilities of the Takasaki Advanced Radiation Research Institute

    Directory of Open Access Journals (Sweden)

    Satoshi Kurashima

    2017-03-01

    Full Text Available The ion beam facility at the Takasaki Advanced Radiation Research Institute, the National Institutes for Quantum and Radiological Science and Technology, consists of a cyclotron and three electrostatic accelerators, and they are dedicated to studies of materials science and bio-technology. The paper reviews this unique accelerator complex in detail from the viewpoint of its configuration, accelerator specification, typical accelerator, or irradiation technologies and ion beam applications. The institute has also irradiation facilities for electron beams and 60Co gamma-rays and has been leading research and development of radiation chemistry for industrial applications in Japan with the facilities since its establishment. The configuration and utilization of those facilities are outlined as well.

  17. Accelerator and Technical Sector Seminar: Future neutrino facilities: the neutrino factory

    CERN Multimedia

    2012-01-01

    Thursday 19.January 2012 at 14:15  -  IT Auditorium (bldg. 31 3-004) Future neutrino facilities: the neutrino factory by Gersende Prior / University of Geneva and CERN EN/MEF The neutrino factory is one of the proposed designs for a future intense neutrino beam facility. In its current layout, a high-power proton beam impinges on an Hg jet target producing pions, decaying in turn into muons. In order to reduce the particle beam emittance, the muon transverse momentum is reduced through ionization cooling by a technically demanding set-up made of closely-packed RF cavities alternating with absorbers. In this talk I will present the motivation for building an intense neutrino beam and some of the proposed neutrino facilities' design. I will discuss the challenges inherent to the cooling of muons, possible optimization of the current baseline and the on-going R&D. ________________ ATS Seminars Organisers: H. Burkhardt (BE), S. Sgobba (EN), G. deRijk (TE)

  18. Remote operations in a Fusion Engineering Research Facility (FERF)

    International Nuclear Information System (INIS)

    Doggett, J.N.

    1975-01-01

    The proposed Fusion Engineering Research Facility (FERF) has been designed for the test and evaluation of materials that will be exposed to the hostile radiation environment created by fusion reactors. Because the FERF itself must create a very hostile radiation environment, extensive remote handling procedures will be required as part of its routine operations as well as for both scheduled and unscheduled maintenance. This report analyzes the remote-handling implications of a vertical- rather than horizontal-orientation of the FERF magnet, describes the specific remote-handling facilities of the proposed FERF installation and compares the FERF remote-handling system with several other existing and proposed facilities. (U.S.)

  19. A new facility for advanced rocket propulsion research

    Science.gov (United States)

    Zoeckler, Joseph G.; Green, James M.; Raitano, Paul

    1993-06-01

    A new test facility was constructed at the NASA Lewis Research Center Rocket Laboratory for the purpose of conducting rocket propulsion research at up to 8.9 kN (2000 lbf) thrust, using liquid oxygen and gaseous hydrogen propellants. A laser room adjacent to the test cell provides access to the rocket engine for advanced laser diagnostic systems. The size and location of the test cell provide the ability to conduct large amounts of testing in short time periods, with rapid turnover between programs. These capabilities make the new test facility an important asset for basic and applied rocket propulsion research.

  20. A safety decision analysis for Saudi Arabian nuclear research facility

    International Nuclear Information System (INIS)

    Abulfaraj, W.H.; Abdul-Fattah, A.F.

    1985-01-01

    Establishment of a nuclear research facility should be the first step in planning for introducing the nuclear energy to Saudi Arabia. The fuzzy set decision theory is selected among different decision theories to be applied for this analysis. Four research reactors from USA are selected for the present study. The IFDA computer code, based on the fuzzy set theory is applied. Results reveal that the FNR reactor is the best alternative for the case of Saudi Arabian nuclear research facility, and MITR is the second best. 17 refs

  1. Seven layers of security to help protect biomedical research facilities.

    Science.gov (United States)

    Mortell, Norman

    2010-04-01

    In addition to risks such as theft and fire that can confront any type of business, the biomedical research community often faces additional concerns over animal rights extremists, infiltrations, data security and intellectual property rights. Given these concerns, it is not surprising that the industry gives a high priority to security. This article identifies security threats faced by biomedical research companies and shows how these threats are ranked in importance by industry stakeholders. The author then goes on to discuss seven key 'layers' of security, from the external environment to the research facility itself, and how these layers all contribute to the creation of a successfully secured facility.

  2. A pulsed neutron facility for condensed matter research

    International Nuclear Information System (INIS)

    Hobbis, L.C.W.; Rees, G.H.; Stirling, G.C.

    1977-06-01

    The scientific and technical basis of the project is presented, as follows: broad synopsis of the proposal for a spallation neutron facility; description of neutron scattering and current work in the UK; scientific applications of the Spallation Neutron Source; discussion of various types of neutron sources; outline description of the SNS and its neutron performance parameters; appendix dealing in more detail with utilization (solid state physics, fluids and amorphous solids, structure determination, molecular and biological sciences); appendix dealing in more detail with the project design (800 MeV synchrotron, target station, shielding, radioactivity and radiation damage, utilization, overall programme). (U.K.)

  3. Facilities for Research and Development of Medical Radioisotopes

    International Nuclear Information System (INIS)

    Shin, Byung Chul; Choung, Won Myung; Park, Jin Ho

    2003-03-01

    This study is carried out by KAERI(Korea Atomic Energy Research Institute) to construct the basic facilities for development and production of medical radioisotope. For the characteristics of radiopharmaceuticals, the facilities should be complied with the radiation shield and GMP(Good Manufacturing Practice) guideline. The KAERI, which has carried out the research and development of the radiopharmaceuticals, made a design of these facilities and built them in the HANARO Center and opened the technique and facilities to the public to give a foundation for research and development of the radiopharmaceuticals. In the facilities, radiation shielding utilities and GMP instruments were set up and their operating manuals were documented. Every utilities and instruments were performed the test to confirm their efficiency and the approval for use of the facilities will be achieved from MOST(Ministry of Science and Technology). It is expected to be applied in development of therapeutic radioisotope such as Re-188 generator and Ho-166, as well as Tc-99m generator and Sr-89 chloride for medical use. And it also looks forward to the contribution to the related industry through the development of product in high demand and value

  4. Space facilities: Meeting future needs for research, development, and operations

    Science.gov (United States)

    The National Facilities Study (NFS) represents an interagency effort to develop a comprehensive and integrated long-term plan for world-class aeronautical and space facilities that meet current and projected needs for commercial and government aerospace research and development and space operations. At the request of NASA and the DOD, the National Research Council's Committee on Space Facilities has reviewed the space related findings of the NFS. The inventory of more than 2800 facilities will be an important resource, especially if it continues to be updated and maintained as the NFS report recommends. The data in the inventory provide the basis for a much better understanding of the resources available in the national facilities infrastructure, as well as extensive information on which to base rational decisions about current and future facilities needs. The working groups have used the inventory data and other information to make a set of recommendations that include estimates of cast savings and steps for implementation. While it is natural that the NFS focused on cost reduction and consolidations, such a study is most useful to future planning if it gives equal weight to guiding the direction of future facilities needed to satisfy legitimate national aspirations. Even in the context of cost reduction through facilities closures and consolidations, the study is timid about recognizing and proposing program changes and realignments of roles and missions to capture what could be significant savings and increased effectiveness. The recommendations of the Committee on Space Facilities are driven by the clear need to be more realistic and precise both in recognizing current incentives and disincentives in the aerospace industry and in forecasting future conditions for U.S. space activities.

  5. Review of TSOs technical needs in safety research and development

    International Nuclear Information System (INIS)

    Rintamaa, R.; Bruna, G.

    2012-01-01

    ETSON is the network of European Technical Safety Organizations. The ETSON members have elaborated together a position paper which identifies and ranks the main research and development fields of endeavor in a short, mid and long term perspective. The main research areas and major needs are grouped in 7 areas: 1) safety assessment methods, 2) multi-physics safety approach (several disciplines, macroscopic and microscopic level), 3) Ageing of materials, 4) fuel behaviour, 5) human and organisational factors, 6) instrumentation and control, 7) Severe accidents: phenomenology and methodology, and severe accidents: crisis preparedness and major needs. ETSON has coordinated the activities with other European platforms and has widely contributed to the NUGENIA (Nuclear Generation 2 and 3 Association) topic research and development areas. The next step will be a prioritization of these needs

  6. Research reactor RB, technical characteristics and experimental possibilities

    International Nuclear Information System (INIS)

    Sotic, O.; Vranic, S.

    1978-01-01

    Nuclear research reactor RB tn the Nuclear Engineering Laboratory at the Institute of Nuclear Sciences 'Boris Kidric' in Vinca is the first reactor system built in Yugoslavia in 1958. In this report, the basic technical characteristics of this reactor are described, as well as the experimental possibilities it offers to the users. Its relatively simple construction and flexibility enables direct measurements of a series of physical parameters, and the absence of the biological protection shield makes it very useful for Various biological and other irradiations and dosimetric measurements Where strong neutron source is required. (author) [sr

  7. Technical feasibility of a concept radioactive waste disposal facility in Boom clay in the Netherlands

    International Nuclear Information System (INIS)

    Vardon, P.J.; Hicks, M.A.; Fokker, P.A.; Fokkens, J.H.

    2012-01-01

    Document available in extended abstract form only. The current management strategy in the Netherlands for radioactive waste is interim storage for approximately 100 years, followed by final deep geological disposal. At present, both Boom Clay and Salt formations are being considered and investigated via the OPERA (Onderzoeks Programma Eindberging Radioactief Afval) and CORA (Commissie Opberging Radioactief Afval) research programmes respectively, instigated by COVRA (Centrale Organisatie Voor Radioactief Afval). This paper outlines the on-going investigation into the initial technical feasibility of a high-level radioactive waste disposal facility, located within a stratum of Boom Clay, as part of the OPERA research programme. The feasibility study is based on the current Belgian Super-container concept, incorporating specific features relevant to the Netherlands, including the waste inventory and possible future glaciation. The repository is designed to be situated at approximately 500 m depth in a Boom Clay stratum of approximately 100 m thickness, and will co-host vitrified High Level Waste (HLW), spent fuel from research reactors, non-heat generating HLW, Low and Intermediate Level Waste (LILW) and depleted uranium. The total footprint is designed to be 3050 m by 1300 m, and will be segregated by waste type. The waste will be stored in drifts drilled perpendicular to the main galleries and will vary in length and diameter depending upon waste type. The repository life-cycle can be considered in three phases: (i) the pre-operation phase, including the conceptual development, site investigation and selection, design and construction; (ii) the operational phase, including waste emplacement and any period of time prior to closure; and (iii) the post-operational phase. The research on the technical feasibility of the repository will investigate whether the repository can be constructed and whether it is able to perform the appropriate safety functions and meet

  8. Atmospheric Radiation Measurement (ARM) Climate Research Facility Management Plan

    Energy Technology Data Exchange (ETDEWEB)

    Mather, James [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-04-01

    Mission and Vision Statements for the U.S. Department of Energy (DOE)’s Atmospheric Radiation Measurement (ARM) Climate Research Facility Mission The ARM Climate Research Facility, a DOE scientific user facility, provides the climate research community with strategically located in situ and remote-sensing observatories designed to improve the understanding and representation, in climate and earth system models, of clouds and aerosols as well as their interactions and coupling with the Earth’s surface. Vision To provide a detailed and accurate description of the Earth atmosphere in diverse climate regimes to resolve the uncertainties in climate and Earth system models toward the development of sustainable solutions for the nation's energy and environmental challenges.

  9. 76 FR 18624 - Research, Technical Assistance and Training Programs: Notice of Final Circular

    Science.gov (United States)

    2011-04-04

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

  10. Earthquake research for the safer siting of critical facilities

    Energy Technology Data Exchange (ETDEWEB)

    Cluff, J.L. (ed.)

    1980-01-01

    The task of providing the necessities for living, such as adequate electrical power, water, and fuel, is becoming more complicated with time. Some of the facilities that provide these necessities would present potential hazards to the population if serious damage were to occur to them during earthquakes. Other facilities must remain operable immediately after an earthquake to provide life-support services to people who have been affected. The purpose of this report is to recommend research that will improve the information available to those who must decide where to site these critical facilities, and thereby mitigate the effects of the earthquake hazard. The term critical facility is used in this report to describe facilities that could seriously affect the public well-being through loss of life, large financial loss, or degradation of the environment if they were to fail. The term critical facility also is used to refer to facilities that, although they pose a limited hazard to the public, are considered critical because they must continue to function in the event of a disaster so that they can provide vital services.

  11. In-pile experimental facility needs for LMFR safety research

    International Nuclear Information System (INIS)

    Kawata, Norio; Niwa, Hajime

    1994-01-01

    Although the achievement of the safety research during the past years has been significant, there still exists a strong need for future research, especially when there is prospect for future LMFR commercialization. In this paper, our current views are described on future research needs especially with a new in-pile experimental facility. The basic ideas and progress are outlined of a preliminary feasibility study. (author)

  12. Investigation on proper materials of a liner system for trench type disposal facilities of radioactive wastes from research, industrial and medical facilities

    International Nuclear Information System (INIS)

    Nakata, Hisakazu; Amazawa, Hiroya; Sakai, Akihiro; Arikawa, Masanobu; Sakamoto, Yoshiaki

    2011-08-01

    The Low-level Radioactive Waste Disposal Project Center of Japan Atomic Energy Agency will settle on near surface disposal facilities with and without engineered barriers for radioactive wastes from research, industrial and medical facilities. Both of them are so called 'concrete pit type' and 'trench type', respectively. The technical standard of constructing and operating a disposal facility based on 'Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors' have been regulated partly by referring to that of 'Waste Management and Public Cleansing Law'. This means that the concrete pit type and the trench type disposal facility resemble an isolated type for specified industrial wastes and a non leachate controlled type final disposal site for stable industrial wastes, respectively. On the other, We plan to design a disposal facility with a liner system corresponding to a leachate controlled type final disposal site on a crucial assumption that radioactive wastes other than stable industrial wastes to be disposed into the trench type disposal facility is generated. By current nuclear related regulations in Japan, There are no technical standard of constructing the disposal facility with the liner system referring to that of 'Waste Management and Public Cleansing Law'. We investigate the function of the liner system in order to design a proper liner system for the trench type disposal facility. In this report, We investigated liner materials currently in use by actual leachate controlled type final disposal sites in Japan. Thereby important items such as tensile strength, durability from a view point of selecting proper liner materials were studied. The items were classified into three categories according to importance. We ranked proper liner materials for the trench type disposal facility by evaluating the important items per material. As a result, high density polyethylene(HDPE) of high elasticity type polymetric sheet was selected

  13. The Effect of Technical Assistance on Involvement and Use: The Case of a Research, Evaluation, and Technical Assistance Project

    Science.gov (United States)

    Roseland, Denise; Volkov, Boris B.; Callow-Heusser, Catherine

    2011-01-01

    In contrast to typical National Science Foundation program evaluations, the Utah State Math Science Partnership-Research, Evaluation and Technical Assistance Project (MSP-RETA) provided technical assistance (TA) in two forms: direct TA for up to 10 projects a year, and professional development sessions for a larger number of project staff. Not…

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    Miller, Michael C.

    2012-01-01

    the INL. Pratap Sadasivan, and his team have been working on the new metrics for proliferation and security. They have defined the basic structure and method, implementation strategy, needed data, and approach to application. Initial drafting of several sections of the milestone document was started. The MPACT Working Group meeting was hosted at SRS on March 13-15, 2012. Approximately 65 researchers from national labs, industry and universities attended the technical meetings at the Center for Hydrogen Research on March 13-14 with a working lunch each day. 37 persons participated in a site tour, including H-Canyon and the MOX Facility, on March 15. As part of the WG meeting, a presentation by SRNL was given on H-Canyon history, capabilities and opportunities for its use as an MPACT technology test bed. Used fuels storage security analysis, guidance and best practices - Coordination discussions continued for the MPACT used fuel security work packages.

  16. Technical and economic assessment for asbestos abatement within Facility 20470, Wright-Patterson Air Force Base, Ohio

    International Nuclear Information System (INIS)

    Gibson, S.M.; Ogle, R.B.

    1988-03-01

    This report presents the results of a technical and economic assessment of available alternatives for asbestos abatement within Facility 20470 at the Wright-Patterson Air Force Base in Dayton, Ohio. Each alternative was screened on the basis of technical feasibility, environmental impact, economics, and fulfillment of the IRP goals. Four alternatives for study are: establishing a special operations and maintenance program; enclosure; encapsulation with sealants; and removal, disposal, and replacement. Each of these alternatives was assessed for capability to control the release of asbestos fibers within Facility 20470. Alternatives 1 and 4 were determined to be acceptable, while Alternatives 2 and 3 were found to be unacceptable. 2 refs., 6 figs

  17. Research Support Facility (RSF): Leadership in Building Performance (Brochure)

    Energy Technology Data Exchange (ETDEWEB)

    2011-09-01

    This brochure/poster provides information on the features of the Research Support Facility including a detailed illustration of the facility with call outs of energy efficiency and renewable energy technologies. Imagine an office building so energy efficient that its occupants consume only the amount of energy generated by renewable power on the building site. The building, the Research Support Facility (RSF) occupied by the U.S. Department of Energy's National Renewable Energy Laboratory (NREL) employees, uses 50% less energy than if it were built to current commercial code and achieves the U.S. Green Building Council's Leadership in Energy and Environmental Design (LEED{reg_sign}) Platinum rating. With 19% of the primary energy in the U.S. consumed by commercial buildings, the RSF is changing the way commercial office buildings are designed and built.

  18. A possible biomedical facility at the European Organization for Nuclear Research (CERN).

    Science.gov (United States)

    Dosanjh, M; Jones, B; Myers, S

    2013-05-01

    A well-attended meeting, called "Brainstorming discussion for a possible biomedical facility at CERN", was held by the European Organization for Nuclear Research (CERN) at the European Laboratory for Particle Physics on 25 June 2012. This was concerned with adapting an existing, but little used, 78-m circumference CERN synchrotron to deliver a wide range of ion species, preferably from protons to at least neon ions, with beam specifications that match existing clinical facilities. The potential extensive research portfolio discussed included beam ballistics in humanoid phantoms, advanced dosimetry, remote imaging techniques and technical developments in beam delivery, including gantry design. In addition, a modern laboratory for biomedical characterisation of these beams would allow important radiobiological studies, such as relative biological effectiveness, in a dedicated facility with standardisation of experimental conditions and biological end points. A control photon and electron beam would be required nearby for relative biological effectiveness comparisons. Research beam time availability would far exceed that at other facilities throughout the world. This would allow more rapid progress in several biomedical areas, such as in charged hadron therapy of cancer, radioisotope production and radioprotection. The ethos of CERN, in terms of open access, peer-reviewed projects and governance has been so successful for High Energy Physics that application of the same to biomedicine would attract high-quality research, with possible contributions from Europe and beyond, along with potential new funding streams.

  19. Safety Research Experiment Facility Project. Conceptual design report. Volume II. Building and facilities

    International Nuclear Information System (INIS)

    1975-12-01

    The conceptual design of Safety Research Experiment Facility (SAREF) site system includes a review and evaluation of previous geotechnical reports for the area where SAREF will be constructed and the conceptual design of access and in-plant roads, parking, experiment-transport-vehicle maneuvering areas, security fencing, drainage, borrow area development and restoration, and landscaping

  20. Management and Development of the RT Research Facilities and Infrastructures

    International Nuclear Information System (INIS)

    Kim, Won Ho; Nho, Young Chang; Kim, Jae Sung

    2009-01-01

    The purpose of this project are to operate the core facilities of the research for the Radiation Technology in stable and to assist the research activities efficiently in the industry, academic, and research laboratory. By developing the infrastructure of the national radio technology industry, we can activate the researching area of the RT and the related industry, and obtain the primary and original technology. The key point in the study of the RT and the assistance of the industry, academic, and research laboratory for the RT area smoothly, is managing the various of unique radiation facilities in our country. The gamma Phytotron and Gene Bank are essential in the agribiology because these facilities are used to preserve and utilize the genes and to provide an experimental field for the environment and biotechnology. The Radiation Fusion Technology research supporting facilities are the core support facilities, and are used to develop the high-tech fusion areas. In addition, the most advanced analytical instruments, whose costs are very high, should be managed in stable and be utilized in supporting works, and the experimental animal supporting laboratory and Gamma Cell have to be maintained in high level and managed in stable also. The ARTI have been developed the 30MeV cyclotron during 2005∼2006, aimed to produce radioisotopes and to research the beam applications as a result of the project, 'Establishment of the Infrastructure for the Atomic Energy Research Expansion', collaborated with the Korea Institute of Radiological and Medical Sciences. In addition, the ARTI is in the progress of establishing cyclotron integrated complex as a core research facility, using a proton beam to produce radioisotopes and to support a various research areas. The measurement and evaluation of the irradiation dose, and irradiation supporting technology of the Good Irradiation Practice(GIP) are essential in various researching areas. One thing to remember is that the publicity

  1. Status of the support researches for the regulation of nuclear facilities decommissioning in Japan

    International Nuclear Information System (INIS)

    Masuda, Yusuke; Iguchi, Yukihiro; Kawasaki, Satoru; Kato, Masami

    2011-01-01

    In Japan, 4 nuclear power stations are under decommissioning and some nuclear fuel cycle facilities are expected to be decommissioned in the future. On the other hand, the safety regulation of decommissioning of nuclear facilities was changed by amending act in 2005. An approval system after review process of decommissioning plan was adopted and applied to the power stations above. In this situation, based on the experiences of the new regulatory system, the system should be well established and moreover, it should be improved and enhanced in the future. Nuclear Industry and Safety Agency (NISA) is in charge of regulation of commercial nuclear facilities in Japan and decommissioning of them is included. Japan Nuclear Energy Safety Organization (JNES) is in charge of technical supports for NISA as a TSO (Technical Support Organization) also in this field. As for decommissioning, based on regulatory needs, JNES has been continuing research activities from October 2003, when JNES has been established. Considering the 'Prioritized Nuclear Safety Research Plan (August 2009)' of the Nuclear Safety Commission of Japan and the situation of operators facilities, 'Regulatory Support Research Plan between FY 2010-2014' was established in November 2009, which shows the present regulatory needs and a research program. This program consists of researches for 1. review process of decommissioning plan of power reactors, 2. review process of decommissioning plan of nuclear fuel cycle facilities, 3. termination of license at the end of decommissioning and 4. management of decommissioning waste. For the item 1, JNES studied safety assessment methods of dismantling, e.g. obtaining data and analysis of behavior of dust diffusion and risk assessment during decommissioning, which are useful findings for the review process. For the item 2, safety requirements for the decommissioning of nuclear fuel cycle facilities was compiled, which will be used in the future review. For the item 3

  2. The International Facility for Antiproton and Ion Research FAIR

    International Nuclear Information System (INIS)

    Gutbrod, H. H.

    2008-01-01

    The proposed project FAIR (Facility for Antiproton and Ion Research) is an international accelerator facility of the next generation and will be built as a new company FAIR GmbH next to the site of GSI. About 15 countries have expressed their intention to become shareholders. FAIR builds on the experience and technological developments already made at the existing GSI facility, and at the FAIR partner institutes world wide and incorporates new technological concepts. At its heart is a double ring facility with a circumference of 1100 meters. A system of cooler-storage rings for effective beam cooling at high energies and various experimental halls will be connected to the facility. The existing GSI accelerators - together with the planned proton-linac - serve as injector for the new facility. The double-ring synchrotron will provide ion beams of unprecedented intensities as well as of considerably increased energy. Thereby intense beams of secondary beams - unstable nuclei or antiprotons - can be produced. The system of storage-cooler rings allows the quality of these secondary beams - their energy spread and emittance - to be drastically improved. Moreover, in connection with the double ring synchrotron, an efficient parallel operation of up to four scientific programs can be realized at a time. The project is based on many technological innovations, the most important of which are five beam properties: Highest Beam Intensities, Brilliant Beam Quality, Higher Beam Energies, Highest Beam Power, Parallel Operation

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

    International Nuclear Information System (INIS)

    1994-01-01

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

  4. ADDRESSING POLLUTION PREVENTION ISSUES IN THE DESIGN OF A NEW NUCLEAR RESEARCH FACILITY

    International Nuclear Information System (INIS)

    Cournoyer, Michael E.; Corpion, Juan; Nelson, Timothy O.

    2003-01-01

    The Chemistry and Metallurgical Research (CMR) Facility was designed in 1949 and built in 1952 at Los Alamos National Laboratory (LANL) to support analytical chemistry, metallurgical studies, and actinide research and development on samples of plutonium and other nuclear materials for the Atomic Energy Commission's nuclear weapons program. These primary programmatic uses of the CMR Facility have not changed significantly since it was constructed. In 1998, a seismic fault was found to the west of the CMR Facility and projected to extend beneath two wings of the building. As part of the overall Risk Management Strategy for the CMR Facility, the Department of Energy (DOE) proposed to replace it by 2010 with what is called the CMR Facility Replacement (CMRR). In an effort to make this proposed new nuclear research facility environmentally sustainable, several pollution prevention/waste minimization initiatives are being reviewed for potential incorporation during the design phase. A two-phase approach is being adopted; the facility is being designed in a manner that integrates pollution prevention efforts, and programmatic activities are being tailored to minimize waste. Processes and procedures that reduce waste generation compared to current, prevalent processes and procedures are identified. Some of these ''best practices'' include the following: (1) recycling opportunities for spent materials; (2) replacing lithium batteries with alternate current adaptors; (3) using launderable contamination barriers in Radiological Control Areas (RCAs); (4) substituting mercury thermometers and manometers in RCAs with mercury-free devices; (5) puncturing and recycling aerosol cans; (6) using non-hazardous low-mercury fluorescent bulbs where available; (7) characterizing low-level waste as it is being generated; and (8) utilizing lead alternatives for radiological shielding. Each of these pollution prevention initiatives are being assessed for their technical validity, relevancy

  5. Electronic battlespace facility for research, develoment and engineering

    NARCIS (Netherlands)

    Jense, Hans; Kuijpers, N.H.L.; Elias, R.J.D.

    1997-01-01

    In order to support its research, development and engineering activities in the area of distributed simulation for training and command & control, TNO Physics and Electronics Laboratory has developed (and continues to enhance) an Electronic Battlespace Facility (EBF). This paper presents an overview

  6. Dynamic research of masonry vault in a technical scale

    Science.gov (United States)

    Golebiewski, Michal; Lubowiecka, Izabela; Kujawa, Marcin

    2017-03-01

    The paper presents preliminary results of dynamic tests of the masonry barrel vault in a technical scale. Experimental studies are intended to identify material properties of homogenized masonry vaults under dynamic loads. The aim of the work is to create numerical models to analyse vault's dynamic response to dynamic loads in a simplest and accurate way. The process of building the vault in a technical scale is presented in the paper. Furthermore a excitation of vibrations with an electrodynamic modal exciter placed on the vault, controlled by an arbitrary waveform function generator, is discussed. Finally paper presents trends in the research for homogenization algorithm enabling dynamic analysis of masonry vaults. Experimental results were compared with outcomes of so-called macromodels (macromodel of a brick masonry is a model in which masonry, i.e. a medium consisting of two different fractions - bricks and mortar, is represented by a homogenized, uniformed, material). Homogenization entail significant simplifications, nevertheless according to the authors, can be a useful approach in a static and dynamic analysis of masonry structures.

  7. Detailed description of an SSAC at the facility level for research laboratory facilities

    International Nuclear Information System (INIS)

    Jones, R.J.

    1985-08-01

    The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in a research laboratory facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

  8. The actual research of radioprotective education on the educational facilities for radiological technologists

    International Nuclear Information System (INIS)

    Miura, Tadashi; Koga, Sukehiko.

    1997-01-01

    The aim of this study was to grasp the actual conditions of the radioprotective education in the educational facilities for radiological technologists, and to discuss the ideal way of radioprotective education toward the 21st century. For this purpose, we sent out the questionnaire concerning the circumstances of radioprotective education to 38 educational facilities for radiological technologists in Japan, including 6 universities, 15 junior colleges and 15 technical schools. This research was carried out on March, 1997, and the answers were obtained total 34 educational facilities (86.8%) (6 universities, 15 junior colleges and 13 technical schools) in total. Among the educational facilities in Japan, universities were much richer than the other two facilities in every respect on the educational circumstances including number and the quality of teaching staffs, educational institutions and equipment, practical training facilities and equipment, the number of collection of books in the library, etc. In the process of education for radiological technologists, the background to cause problems concerning the radioprotective education was largely dependent on the difference of educational schemes in Japan. From the view point of the elevation of educational standard for radiological technologists, it is better to transfer all educational processes to the universities, and give high and full level of radioprotective education in universities. And in the field of the medical radiology, the radioprotection and the management system should also be strengthened. For this purpose, it is also required to revise the related laws drastically, to strengthen lessons related to the radioprotection and to plan the richness in contents of the radioprotective education. (K.H.)

  9. Research on decommissioning of nuclear facilities (Joint research)

    International Nuclear Information System (INIS)

    Shibahara, Yuji; Morishita, Yoshitsugu; Ishigami, Tsutomu; Yanagihara, Satoshi; Arita, Yuji

    2011-07-01

    To implement a decommissioning project reasonably, it is necessary and important to beforehand evaluate project management data as well as to select an optimum dismantling scenario among various scenarios postulated. Little study on the subject of selecting an optimum scenario has been carried out, and it is one of the most important subjects in terms of decision making. In FY 2009, Japan Atomic Energy Agency and University of Fukui launched the joint research of a decision making method which is important to determine a decommissioning plan. The purpose of the research is to construct a methodology for selecting an optimum dismantling scenario among various scenarios postulated based on calculated results of project management data for FUGEN. Project management data for several dismantling scenarios postulated at FUGEN were evaluated based on actual dismantling work for feed water heater at FUGEN, and an optimum scenario was discussed using the SMART, one of Multi-Criteria Decision Analysis Method. This report describes the results of the joint research in FY 2009. (author)

  10. ARM Climate Research Facility Monthly Instrument Report August 2010

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2010-09-28

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  11. ARM Climate Research Facility Instrumentation Status and Information October 2009

    Energy Technology Data Exchange (ETDEWEB)

    JW Voyles

    2009-10-01

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  12. ARM Climate Research Facility Instrumentation Status and Information April 2010

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2010-05-15

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  13. ARM Climate Research Facility Instrumentation Status and Information January 2010

    Energy Technology Data Exchange (ETDEWEB)

    JW Voyles

    2010-02-28

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  14. ARM Climate Research Facility Monthly Instrument Report September 2010

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2010-10-18

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  15. ARM Climate Research Facility Instrumentation Status and Information March 2010

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2010-04-19

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  16. ARM Climate Research Facility Monthly Instrument Report May 2010

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2010-06-21

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  17. ARM Climate Research Facility Instrumentation Status and Information February 2010

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2010-03-25

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  18. ARM Climate Research Facility Monthly Instrument Report June 2010

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2010-07-13

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  19. ARM Climate Research Facility Instrumentation Status and Information December 2009

    Energy Technology Data Exchange (ETDEWEB)

    JW Voyles

    2010-12-30

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  20. ARM Climate Research Facility Monthly Instrument Report July 2010

    Energy Technology Data Exchange (ETDEWEB)

    Voyles, JW

    2010-08-18

    The purpose of this report is to provide a concise but comprehensive overview of Atmospheric Radiation Measurement Climate Research Facility instrumentation status. The report is divided into the following five sections: (1) new instrumentation in the process of being acquired and deployed, (2) field campaigns, (3) existing instrumentation and progress on improvements or upgrades, (4) proposed future instrumentation, and (5) Small Business Innovation Research instrument development.

  1. Research for the safety of existing nuclear facilities

    International Nuclear Information System (INIS)

    Teschendorff, Victor; Bruna, Giovanni B.; Gelder, Pieter de

    2007-01-01

    The essential role of research for maintaining the high safety standard for the existing nuclear installations is outlined in the context of internationally agreed needs. The three co-authoring Technical Safety Organisations are committed to continued safety research, recognising operational experience and new technologies as the main driving forces. The safety margin concept is introduced and new trends in traditional and new areas of safety research are identified. The importance of a sufficient experimental infrastructure and international co-operation in sustainable networks is highlighted. (orig.)

  2. Hardware Development Process for Human Research Facility Applications

    Science.gov (United States)

    Bauer, Liz

    2000-01-01

    The simple goal of the Human Research Facility (HRF) is to conduct human research experiments on the International Space Station (ISS) astronauts during long-duration missions. This is accomplished by providing integration and operation of the necessary hardware and software capabilities. A typical hardware development flow consists of five stages: functional inputs and requirements definition, market research, design life cycle through hardware delivery, crew training, and mission support. The purpose of this presentation is to guide the audience through the early hardware development process: requirement definition through selecting a development path. Specific HRF equipment is used to illustrate the hardware development paths. The source of hardware requirements is the science community and HRF program. The HRF Science Working Group, consisting of SCientists from various medical disciplines, defined a basic set of equipment with functional requirements. This established the performance requirements of the hardware. HRF program requirements focus on making the hardware safe and operational in a space environment. This includes structural, thermal, human factors, and material requirements. Science and HRF program requirements are defined in a hardware requirements document which includes verification methods. Once the hardware is fabricated, requirements are verified by inspection, test, analysis, or demonstration. All data is compiled and reviewed to certify the hardware for flight. Obviously, the basis for all hardware development activities is requirement definition. Full and complete requirement definition is ideal prior to initiating the hardware development. However, this is generally not the case, but the hardware team typically has functional inputs as a guide. The first step is for engineers to conduct market research based on the functional inputs provided by scientists. CommerCially available products are evaluated against the science requirements as

  3. Agency Data on User Facilities

    Data.gov (United States)

    National Aeronautics and Space Administration — The purpose of the Aerospace Technical Facility Inventory is to facilitate the sharing of specialized capabilities within the aerospace research/engineering...

  4. Building a 'data repository' for heterogenous technical research communities through collaborations

    NARCIS (Netherlands)

    Rombouts, J.; Princic, A.

    2010-01-01

    The paper describes the project ‘3TU.Datacentrum’, an initiative of the libraries of the three Dutch Technical Universities. Its aim is to build a data curation facility for the improvement of data management, providing data curation services for data producers of the Technical Universities and

  5. Joint Assessment of ETRR-2 Research Reactor Operations Program, Capabilities, and Facilities

    International Nuclear Information System (INIS)

    Bissani, M; O'Kelly, D S

    2006-01-01

    A joint assessment meeting was conducted at the Egyptian Atomic Energy Agency (EAEA) followed by a tour of Egyptian Second Research Reactor (ETRR-2) on March 22 and 23, 2006. The purpose of the visit was to evaluate the capabilities of the new research reactor and its operations under Action Sheet 4 between the U.S. DOE and the EAEA, ''Research Reactor Operation'', and Action Sheet 6, ''Technical assistance in The Production of Radioisotopes''. Preliminary Recommendations of the joint assessment are as follows: (1) ETRR-2 utilization should be increased by encouraging frequent and sustained operations. This can be accomplished in part by (a) Improving the supply-chain management for fresh reactor fuel and alleviating the perception that the existing fuel inventory should be conserved due to unreliable fuel supply; and (b) Promulgating a policy for sample irradiation priority that encourages the use of the reactor and does not leave the decision of when to operate entirely at the discretion of reactor operations staff. (2) Each experimental facility in operation or built for a single purpose should be reevaluated to focus on those that most meet the goals of the EAEA strategic business plan. Temporary or long-term elimination of some experimental programs might be necessary to provide more focused utilization. There may be instances of emerging reactor applications for which no experimental facility is yet designed or envisioned. In some cases, an experimental facility may have a more beneficial use than the purpose for which it was originally designed. For example, (a) An effective Boron Neutron Capture Therapy (BNCT) program requires nearby high quality medical facilities. These facilities are not available and are unlikely to be constructed near the Inshas site. Further, the BNCT facility is not correctly designed for advanced research and therapy programs using epithermal neutrons. (b) The ETRR-2 is frequently operated to provide color-enhanced gemstones but is

  6. Procedures for economic distribution of radionuclides in research facilities

    International Nuclear Information System (INIS)

    Perry, N.A.

    1979-01-01

    A radionuclide accountability system for use in a research facility is described. It can be operated manually or adapted for computer use. All radionuclides are ordered, received, distributed and paid for by the Radiological Control Office who keep complete records of date of order, receipt, calibration use, transfer and/or disposal. Wipe leak tests, specific activity and lot number are also recorded. The procedure provides centralized total accountability records, including financial records, of all radionuclide orders, and the economic advantages of combined purchasing. The use of this system in two medical facilities has resulted in considerable financial savings in the first year of operation. (author)

  7. Introducing COSS: A new and unique oil spill research facility

    International Nuclear Information System (INIS)

    Kitchen, R. B.; Bonner, J. S.; Autenrieth, R. L.; Donnelly, K. C.; Ernest, A. N. S.

    1997-01-01

    A new oil spill research facility in Corpus Christi, Texas began operation in April 1997 to address the appropriate use, application and effectiveness of chemical, physical and biological oil spill response agents. The Coastal Oil Spill Simulation (COSS) facility consists of nine meso scale wave tanks and will offer to science and industry a unique opportunity to spill oil in a controlled environment and to study fate, transport and remediation of oil releases in simulated coastal, intertidal, lagunal, channel and porous media. 1 ref

  8. Division of Biological and Medical Research annual technical report, 1981

    International Nuclear Information System (INIS)

    Rosenthal, M.W.

    1982-06-01

    This report summarizes research during 1981 in the Division of Biological and Medical Research, Argonne National Laboratory. Studies in Low Level Radiation include comparison of lifetime effects in mice of low level neutron and gamma irradiation, delineation of the responses of dogs to continuous low level gamma irradiation, elucidation of mechanisms of radiation damage and repair in mammalian cells, and study of the genetic effects of high LET radiations. Carcinogenesis research addresses mechanisms of tumor initiation and promotion in rat liver, chemical carcinogenesis in cultured mammalian cells, and molecular and genetic mechanisms of chemical and ultraviolet mutagenesis in bacteria. Research in Toxicology uses a variety of cellular, whole animal, and chronobiological end points, chemical separations, and statistical models to evaluate the hazards and mechanisms of actions of metals, coal gasification by products, and other energy-related pollutants. Human Protein Index studies develop two-dimensional electrophoresis systems for diagnosis and detection of cancer and other disease. Biophysics research includes fundamental structural and biophysical investigations of immunoglobulins and key biological molecules using NMR, crystallographic, and x-ray and neutron small-angle scattering techniques. The final sections cover support facilities, educational activities, seminars, staff talks, staff, and funding agencies

  9. Division of Biological and Medical Research annual technical report, 1981

    Energy Technology Data Exchange (ETDEWEB)

    Rosenthal, M.W. (ed.)

    1982-06-01

    This report summarizes research during 1981 in the Division of Biological and Medical Research, Argonne National Laboratory. Studies in Low Level Radiation include comparison of lifetime effects in mice of low level neutron and gamma irradiation, delineation of the responses of dogs to continuous low level gamma irradiation, elucidation of mechanisms of radiation damage and repair in mammalian cells, and study of the genetic effects of high LET radiations. Carcinogenesis research addresses mechanisms of tumor initiation and promotion in rat liver, chemical carcinogenesis in cultured mammalian cells, and molecular and genetic mechanisms of chemical and ultraviolet mutagenesis in bacteria. Research in Toxicology uses a variety of cellular, whole animal, and chronobiological end points, chemical separations, and statistical models to evaluate the hazards and mechanisms of actions of metals, coal gasification by products, and other energy-related pollutants. Human Protein Index studies develop two-dimensional electrophoresis systems for diagnosis and detection of cancer and other disease. Biophysics research includes fundamental structural and biophysical investigations of immunoglobulins and key biological molecules using NMR, crystallographic, and x-ray and neutron small-angle scattering techniques. The final sections cover support facilities, educational activities, seminars, staff talks, staff, and funding agencies.

  10. Design strategies for the International Space University's variable gravity research facility

    Science.gov (United States)

    Bailey, Sheila G.; Chiaramonte, Francis P.; Davidian, Kenneth J.

    1990-01-01

    A variable gravity research facility named 'Newton' was designed by 58 students from 13 countries at the International Space University's 1989 summer session at the Universite Louis Pasteur, Strasbourge, France. The project was comprehensive in scope, including a political and legal foundation for international cooperation, development and financing; technical, science and engineering issues; architectural design; plausible schedules; and operations, crew issues and maintenance. Since log-term exposure to zero gravity is known to be harmful to the human body, the main goal was to design a unique variable gravity research facility which would find a practical solution to this problem, permitting a manned mission to Mars. The facility would not duplicate other space-based facilities and would provide the flexibility for examining a number of gravity levels, including lunar and Martian gravities. Major design alternatives included a truss versus a tether based system which also involved the question of docking while spinning or despinning to dock. These design issues are described. The relative advantages or disadvantages are discussed, including comments on the necessary research and technology development required for each.

  11. The SARAF Project - Soreq Applied Research Accelerator Facility

    International Nuclear Information System (INIS)

    Nagler, A.; Mardor, I.; Berkovits, D.; Piel, C.

    2004-01-01

    The relevance of particle accelerators to society, in the use of their primary and secondary beams for the analysis of physical, chemical and biological samples and for modification of properties of materials, is well recognized and documented. Nevertheless, apart of the construction of small accelerators for nuclear research in the 1960's and 70's, Israel has so far neglected this important and growing field. Furthermore, there is an urgent need in Israel for a state of the art research facility to attract and introduce students to current advanced physics techniques and technologies and to train the next generation of experimental scientists in various branches and disciplines. Therefore, Soreq NRC recently initiated the establishment of a new accelerator facility, named SARAF Soreq Applied Research Accelerator Facility. SARAF will be a continuous wave (CW), proton and deuteron RF superconducting linear accelerator with variable energy (5 - 40 MeV) and current (0.04 -2 mA). SARAF is designed to enable hands-on maintenance, which means that its beam loss will be below 10 -5 for the entire accelerator. These specifications will place SARAF in line with the next generation of accelerators world wide. Soreq expects that this fact will attract the Israeli and international research communities to use this facility extensively. Soreq NRC intends to use SARAF for basic, medical and biological research, and non-destructive testing (NDT). Another major activity will be the research and development of radio-isotopes production techniques. Given the availability of high current (up to 2 mA) protons and deuterons, a major activity will be research and development of high power density (up to 80 kW on a few cm 2 ) irradiation targets

  12. Commercial products and services of research reactors. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2013-07-01

    Although the number of operational research reactors is steadily decreasing, more than half of those that remain are greatly underutilized and, in most cases, underfunded. To continue to play a key role in the development of peaceful uses of nuclear technology, the remaining research reactors will need to provide useful products and services to private, national and regional customers, in some cases with adequate revenue generation for reliable, safe and secure facility management and operation. In the light of declining governmental financial support and the need for improved physical security and conversion to low enriched uranium (LEU) fuel, many research reactors have been challenged to generate income to offset increasing operational and maintenance costs. The renewed interest in nuclear power (and therefore in nuclear education and training), the global expansion of diagnostic and therapeutic nuclear medicine, and the extensive use of semiconductors in electronics and in other areas have created new opportunities for research reactors, prominent among them, markets for products and services in regions and countries without such facilities. It is clear that such initiatives towards greater self-reliance will need to address such aspects as market surveys, marketing and business plans, and cost of delivery services. It will also be important to better inform present and future potential end users of research reactor services of the capabilities and products that can be provided. This publication is a compilation of material from an IAEA technical meeting on “Commercial Products and Services of Research Reactors”, held in Vienna, Austria, from 28 June to 2 July 2010. The overall objective of the meeting was to exchange information on good practices and to provide concrete examples, in technical presentations and brainstorming discussions, to promote and facilitate the development of commercial applications of research reactors. The meeting also aimed to

  13. Research Facility for Mechanical Press Closed Gap Adjuster

    Directory of Open Access Journals (Sweden)

    A. A. Ancifirov

    2016-01-01

    Full Text Available The article describes an example of the research facility for closed gap adjustment mechanism based on the KD2128 closed-die forging press. Its rated force with a servo drive used is 630kN. The servo drive consists of a motor with nominal power of 1.57kW and a frequency converter with power of 7.5kW, which has functions of the programmable logic controller.The article notes that such a facility is expedient and useful for practical classes on forging-andstamping machines at the BMSTU Department of «Technology processing by pressure» to demonstrate the capabilities of existing technological facility, learn a design of forging-andstamping machine units, solve the problems of automatic control, monitoring, and diagnostics in blank manufacturing.The article presents a detailed facility diagram of the closed gap adjustment mechanism and its photograph, describes the mechanism and its basic parameters, gives characteristics of the synchronous motor to drive the mechanism, reviews practical works, which the research facility may provide.Based on the four experiments the article estimates an efficiency of the research facilityuse under consideration, especially when modeling a servo motor shaft under the maximum load. The relevant diagrams confirm experimental results, namely: control current, angle of motor shaft and its speed versus time. Thus, upon the diagram analysis it can be noted that the research facility design allows providing kinematics and dynamics of the press closed gap adjuster.This article describes how to determine the closed gap adjusting accuracy of the press. Eight experiments have been conducted to evaluate a working out control signal to the linear movement of the press punch when using the research facility. It is noted that the linear positioning accuracy of the press punch reaches the hundredth parts of a millimeter of the adjustment value that is sufficient to achieve the required precision when performing operations such as

  14. 76 FR 11414 - Defense Federal Acquisition Regulation Supplement; Independent Research and Development Technical...

    Science.gov (United States)

    2011-03-02

    ... Acquisition Regulation Supplement; Independent Research and Development Technical Descriptions (DFARS Case... (DFARS) to require contractors to report independent research and development (IR&D) projects generating... to the Defense Technical Information Center (DTIC). Beginning in the 1990s, DoD reduced its technical...

  15. BALU: Largest autoclave research facility in the world

    Directory of Open Access Journals (Sweden)

    Hakan Ucan

    2016-03-01

    Full Text Available Among the large-scale facilities operated at the Center for Lightweight-Production-Technology of the German Aerospace Center in Stade BALU is the world's largest research autoclave. With a loading length of 20m and a loading diameter of 5.8 m the main objective of the facility is the optimization of the curing process operated by components made of carbon fiber on an industrial scale. For this reason, a novel dynamic autoclaving control has been developed that is characterized by peripheral devices to expend the performance of the facility for differential applications, by sensing systems to detect the component state throughout the curing process and by a feedback system, which is capable to intervene into the running autoclave process.

  16. Research in decommissioning techniques for nuclear fuel cycle facilities in JNC. 7. JWTF decommissioning techniques

    International Nuclear Information System (INIS)

    Ogawa, Ryuichiro; Ishijima, Noboru

    1999-02-01

    Decommissioning techniques such as radiation measuring and monitoring, decontamination, dismantling and remote handling in the world were surveyed to upgrading technical know-how database for decommissioning of Joyo Waste Treatment Facility (JWTF). As the result, five literatures for measuring and monitoring techniques, 14 for decontamination and 22 for dismantling feasible for JWTF decommissioning were obtained and were summarized in tables. On the basis of the research, practical applicability of those techniques to decommissioning of JWTF was evaluated. This report contains brief surveyed summaries related to JWTF decommissioning. (H. Itami)

  17. NEW IRRADIATION RESEARCH FACILITIES AT THE ARMY NATICK LABORATORIES

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, R. D.; Brynjolfsson, A.

    1963-03-15

    New facilities built by the U. S. Army for research on the preservation of food by ionizing radiation consist of a food processing and packaging facility and a radiation sources laboratory with two powerful low-energy radiation sources. One is a 1.3 million-curie Co/sup 60/ source consisting of 98 tubes each containing four doubly encapsulated Co/sup 60/ slugs. The second source is an electron linear accelerator with energy variable between 2 and 32 Mev. Research with the Co/sup 60/ source is concentrated on investigation of macroscopic and microscopic dose distribution in different materials irradiated with Co/sup 60/ gamma rays. Research with the linear accelerator is concentrated on dosimetry and photonuclear reactions. (A.G.W.)

  18. The reactor and cold neutron research facility at NIST

    Energy Technology Data Exchange (ETDEWEB)

    Prask, H J; Rowe, J M [Reactor Radiation Division, National Institute of Standards and Technology, Gaithersburg, MD (United States)

    1992-07-01

    The NIST Reactor (NBSR) is a 20 MW research reactor located at the Gaithersburg, MD site, and has been in operation since 1969. It services 26 thermal neutron facilities which are used for materials science, chemical analysis, nondestructive evaluation, neutron standards work, and irradiations. In 1987 the Department of Commerce and NIST began development of the CNRF - a $30M National Facility for cold neutron research -which will provide fifteen new experimental stations with capabilities currently unavailable in this country. As of May 1992, four of the planned seven guides and a cold port were installed, eight cold neutron experimental stations were operational, and the Call for Proposals for the second cycle of formally-reviewed guest-researcher experiments had been sent out. Some details of the performance of instrumentation are described, along with the proposed design of the new hydrogen cold source which will replace the present D{sub 2}O/H{sub 2}O ice cold source. (author)

  19. The reactor and cold neutron research facility at NIST

    International Nuclear Information System (INIS)

    Prask, H.J.; Rowe, J.M.

    1992-01-01

    The NIST Reactor (NBSR) is a 20 MW research reactor located at the Gaithersburg, MD site, and has been in operation since 1969. It services 26 thermal neutron facilities which are used for materials science, chemical analysis, nondestructive evaluation, neutron standards work, and irradiations. In 1987 the Department of Commerce and NIST began development of the CNRF - a $30M National Facility for cold neutron research -which will provide fifteen new experimental stations with capabilities currently unavailable in this country. As of May 1992, four of the planned seven guides and a cold port were installed, eight cold neutron experimental stations were operational, and the Call for Proposals for the second cycle of formally-reviewed guest-researcher experiments had been sent out. Some details of the performance of instrumentation are described, along with the proposed design of the new hydrogen cold source which will replace the present D 2 O/H 2 O ice cold source. (author)

  20. Division of Biological and Medical Research annual technical report 1982

    International Nuclear Information System (INIS)

    Rosenthal, M.W.

    1983-05-01

    This report summarizes research during 1982 in the Division of Biological and Medical Research, Argonne National Laboratory. Studies in Carcinogenesis address mechanisms of chemical and radiation carcinogenesis including the processes of tumor initiation and promotion. The studies employ rat liver and mouse skin models as well as human rodent cell culture systems. The use of liposomes for metal mobilization is also explored. Low Level Radiation studies include delineation of the hematopoietic and other responses of dogs to continuous low level gamma irradiation, comparison of lifetime effects in mice of low level neutron and gamma irradiation, and study of the genetic effects of high LET radiation. Molecular Biology research develops two-dimensional electrophoresis systems for diagnosis and detection of cancer and other diseases. Fundamental structural and biophysical investigations of immunoglobulins and other key proteins are included, as are studies of cell growth, and of molecular and cellular effects of solar uv light. Research in Toxicology uses cellular, physiological, whole animal, and chronobiological end points and chemical separations to elucidate mechanisms and evaluate hazards of coal conversion by-products, actinides, and toxic metals. The final sections cover support facilities, educational activities, seminars, staff talks, staff, and funding agencies

  1. Division of Biological and Medical Research annual technical report 1982

    Energy Technology Data Exchange (ETDEWEB)

    Rosenthal, M.W. (ed.)

    1983-05-01

    This report summarizes research during 1982 in the Division of Biological and Medical Research, Argonne National Laboratory. Studies in Carcinogenesis address mechanisms of chemical and radiation carcinogenesis including the processes of tumor initiation and promotion. The studies employ rat liver and mouse skin models as well as human rodent cell culture systems. The use of liposomes for metal mobilization is also explored. Low Level Radiation studies include delineation of the hematopoietic and other responses of dogs to continuous low level gamma irradiation, comparison of lifetime effects in mice of low level neutron and gamma irradiation, and study of the genetic effects of high LET radiation. Molecular Biology research develops two-dimensional electrophoresis systems for diagnosis and detection of cancer and other diseases. Fundamental structural and biophysical investigations of immunoglobulins and other key proteins are included, as are studies of cell growth, and of molecular and cellular effects of solar uv light. Research in Toxicology uses cellular, physiological, whole animal, and chronobiological end points and chemical separations to elucidate mechanisms and evaluate hazards of coal conversion by-products, actinides, and toxic metals. The final sections cover support facilities, educational activities, seminars, staff talks, staff, and funding agencies.

  2. Safeguards systems analysis research and development and the practice of safeguards at DOE facilities

    International Nuclear Information System (INIS)

    Zack, N.R.; Thomas, K.E.; Markin, J.T.; Tape, J.W.

    1991-01-01

    Los Alamos Safeguards Systems Group personnel interact with Department of Energy (DOE) nuclear materials processing facilities in a number of ways. Among them are training courses, formal technical assistance such as developing information management or data analysis software, and informal ad hoc assistance especially in reviewing and commenting on existing facility safeguards technology and procedures. These activities are supported by the DOE Office of Safeguards and Security, DOE Operations Offices, and contractor organizations. Because of the relationships with the Operations Office and facility personnel, the Safeguards Systems Group research and development (R and D) staff have developed an understanding of the needs of the entire complex. Improved safeguards are needed in areas such as materials control activities, accountability procedures and techniques, systems analysis and evaluation methods, and material handling procedures. This paper surveys the generic needs for efficient and cost effective enhancements in safeguards technologies and procedures at DOE facilities, identifies areas where existing safeguards R and D products are being applied or could be applied, and sets a direction for future systems analysis R and D to address practical facility safeguards needs

  3. Report of researches by common utilization of facilities in Kyoto University Research Reactor Institute, first half of fiscal year 1981

    International Nuclear Information System (INIS)

    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 57 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 neutron radiography using a research reactor, measurement of Zr/Hf ratio in zirconium, interstitial germanium atoms in thermal neutron irradiation study, measurement of induced radioactivity due to neutrons in Nagasaki and Hiroshima atomic bombings, properties of semiconductor electrons in radiation study, induction of mutation in crops by neutron irradiation and utilization for breeding, thermal fluorescence mechanism of alkali halide and MgO single crystals, atomic configuration in PZT rhombohedron phase, modulated structure of Cu-Co alloys, excitation of nuclei by positron annihilation and others. (Kako, I.)

  4. International Space Station Research and Facilities for Life Sciences

    Science.gov (United States)

    Robinson, Julie A.; Ruttley, Tara M.

    2009-01-01

    Assembly of the International Space Station is nearing completion in fall of 2010. Although assembly has been the primary objective of its first 11 years of operation, early science returns from the ISS have been growing at a steady pace. Laboratory facilities outfitting has increased dramatically 2008-2009 with the European Space Agency s Columbus and Japanese Aerospace Exploration Agency s Kibo scientific laboratories joining NASA s Destiny laboratory in orbit. In May 2009, the ISS Program met a major milestone with an increase in crew size from 3 to 6 crewmembers, thus greatly increasing the time available to perform on-orbit research. NASA will launch its remaining research facilities to occupy all 3 laboratories in fall 2009 and winter 2010. To date, early utilization of the US Operating Segment of the ISS has fielded nearly 200 experiments for hundreds of ground-based investigators supporting international and US partner research. With a specific focus on life sciences research, this paper will summarize the science accomplishments from early research aboard the ISS- both applied human research for exploration, and research on the effects of microgravity on life. We will also look ahead to the full capabilities for life sciences research when assembly of ISS is complete in 2010.

  5. Technical justification for a request to reclassify the former CCC/USDA facility at Canada, Kansas.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M.; Environmental Science Division

    2007-12-21

    Contamination in groundwater at Canada, Kansas, was discovered in 1997, during limited private well sampling near former grain storage facilities of the Commodity Credit Corporation, U.S. Department of Agriculture (CCC/USDA). Subsequent investigations by the Kansas Department of Health and Environment (KDHE) confirmed carbon tetrachloride and nitrate concentrations in groundwater above the respective maximum contaminant levels (MCLs) of 5.0 {micro}g/L and 10.0 mg/L. The KDHE investigations identified both the former CCC/USDA grain storage facility and a private grain storage facility as likely sources for the carbon tetrachloride contamination. The CCC/USDA funded extension of a rural water district line to provide a permanent alternate water supply, and the KDHE has conducted long-term monitoring under the State Water Plan. This document presents an analysis of the available information for the Canada site, acquired in previous investigations and the long-term KDHE monitoring. This analysis forms the technical justification for a request to reclassify the former CCC/USDA grain storage facility at Canada as a site requiring no further action under the Intergovernmental Agreement (IGA) between the KDHE and the USDA's Farm Service Agency. The KDHE's long-term water level monitoring results indicate a consistent groundwater flow direction to the east-southeast. Consequently, the wells with the highest overall concentrations of carbon tetrachloride are downgradient from the private grain storage facility but not downgradient from the former CCC/USDA facility. The KDHE criterion for reclassification of a site is that contamination there should not pose an unacceptable risk, on the basis of analytical results for four consecutive, equally timed, sequenced sampling episodes over a period of no less than two years. In seven KDHE sampling events over a period of six years (2001-2007), the concentrations of carbon tetrachloride in the monitoring well on the former

  6. Criticality safety research on nuclear fuel cycle facility

    Energy Technology Data Exchange (ETDEWEB)

    Miyoshi, Yoshinori [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2004-07-01

    This paper present d s current status and future program of the criticality safety research on nuclear fuel cycle made by Japan Atomic Energy Research Institute. Experimental research on solution fuel treated in reprocessing plant has been performed using two critical facilities, STACY and TRACY. Fundamental data of static and transient characteristics are accumulated for validation of criticality safety codes. Subcritical measurements are also made for developing a monitoring system for criticality safety. Criticality safety codes system for solution and power system, and evaluation method related to burnup credit are developed. (author)

  7. Recent development on Malaysian Small Angle Neutron Scattering (MySANS) facility upgrading and related research activities

    International Nuclear Information System (INIS)

    Abdul Aziz Bin Mohamed; Rafayudi Jamro; Razali Kassim; Muhammad Rawi Mat Zin; Azali Bin Muhammad; Muhd Noor Yunus; Dahlan Hj Mohd; Faridah Md Idris

    2006-01-01

    This paper describes the recent progress of the MySANS - 'mini' SANS facility and its present applications in materials science and technology research and education. Both management and technical strategies are generally explained. The formation of Reactor Interest Group (RIG) has lead to several experimental projects which collaborative work between MINT and local universities/research institutes. In addition a future work plan is also noted. (author)

  8. Massachusetts Institute of Technology, Plasma Fusion Center, technical research programs

    International Nuclear Information System (INIS)

    1982-02-01

    Research programs have produced significant results on four fronts: (1) the basic physics of high-temperature fusion plasmas (plasma theory, RF heating, development of advanced diagnostics and small-scale experiments on the Versator tokamak and Constance mirror devices); (2) major confinement results on the Alcator A and C tokamaks, including pioneering investigations of the equilibrium, stability, transport and radiation properties of fusion plasmas at high densities, temperatures and magnetic fields; (3) development of a new and innovative design for axisymmetric tandem mirrors with inboard thermal barriers, with initial operation of the TARA tandem mirror experimental facility scheduled for 1983; and (4) a broadly based program of fusion technology and engineering development that addresses problems in several critical subsystem areas

  9. Conversion of research and test reactors to low enriched uranium fuel: technical overview and program status

    International Nuclear Information System (INIS)

    Roglans-Ribas, J.

    2008-01-01

    Many of the nuclear research and test reactors worldwide operate with high enriched uranium fuel. In response to worries over the potential use of HEU from research reactors in nuclear weapons, the U.S Department of Energy (DOE) initiated a program - the Reduced Enrichment for Research and Test Reactors (RERTR) - in 1978 to develop the technology necessary to reduce the use of HEU fuel by converting research reactors to low enriched uranium (LEU) fuel. The Reactor Conversion program is currently under the DOE's National Nuclear Security Administration's Global Threat Reduction Initiative (GTRI). 55 of the 129 reactors included in the scope have been already converted to LEU fuel or have shutdown prior to conversion. The major technical activities of the Conversion Program include: (1) the development of advanced LEU fuels; (2) conversion analysis and conversion support; and (3) technology development for the production of Molybdenum-99 (Mo 99 ) with LEU targets. The paper provides an overview of the status of the program, the technical challenges and accomplishments, and the role of international collaborations in the accomplishment of the Conversion Program objectives. Nuclear research and test reactors worldwide have been in operation for over 60 years. Many of these facilities operate with high enriched uranium fuel. In response to increased worries over the potential use of HEU from research reactors in the manufacturing of nuclear weapons, the U.S Department of Energy (DOE) initiated a program - the Reduced Enrichment for Research and Test Reactors (RERTR) - in 1978 to develop the technology necessary to reduce the use of HEU fuel in research reactors by converting them to low enriched uranium (LEU) fuel. The reactor conversion program was initially focused on U.S.-supplied reactors, but in the early 1990s it expanded and began to collaborate with Russian institutes with the objective of converting Russian supplied reactors to the use of LEU fuel.

  10. FORMATION OF RESEARCH COMPETENCE IN TECHNICAL COLLEGE POSTGRADUATES

    Directory of Open Access Journals (Sweden)

    Dmitry Vladimirovich Katchalov

    2015-05-01

    Full Text Available The modern model of professional education is geared to meet the challenges of innovation development of economy and society and is an important element in the training of specialists who are ready to the transformation of the world and reality.Until recently, the goals of higher education formulated by studying a set of knowledge and skills. But today’s situation is that now the order of the society is fixed on reclaiming the gra-duates who are ready to actively participate in the production process, showing the ability to solve practical problems that they faced with.In order to solve the existing contradictions between society’s need for qualified professionals and the existing system of training modern higher professional education is focused on achieving the goal of quality of education, the result of which is the formation of a strong knowledge and skills, the ability to operate in a rapidly changing environment, readiness to implement continuing education. This leads to the fact that amplifies an urgent need in the formation at university students general and professional competencies.Despite the large number of studies devoted to the problems of formation of general and professional competences, the question of determining the specificity of the content, conditions, ways and means of forming research competence of postgraduates remains open. There is a need for scientific substantiation and development of pedagogical bases of formation of research competence in technical college postgraduates.

  11. Small-scale hot facility for reprocessing and alpha research

    International Nuclear Information System (INIS)

    Abdel-Rassoul, A.A.

    1976-01-01

    The experimental hot facility at Inchas is planned for research activities related to the decontamination of radioactive wastes, analytical chemistry of alpha emitters and chemical treatment of spent UO 2 -Mg fuel samples. The design concept permits safe handling of source materials with radioactivity levels up to 10000Ci. The laboratory includes a reception area, process hall, a number of research laboratories and other facilities for chemical and physical analysis, nuclear measurements and health physics control. The radioactive waste management plant allows for control and decontamination of intermediate- and low-level laboratory effluents. Fixation of radioactive residues will be carried out in the sludge immobilization plant. High-level fission-product waste liquors are subject to preconcentration and transformation to a glassy matrix before ultimate storage. (author)

  12. Recent activities at the ORNL multicharged ion research facility (MIRF)

    International Nuclear Information System (INIS)

    Meyer, F.W.; Bannister, M.E.; Hale, J.W.; Havener, C.C.; Krause, H.F.; Vane, C.R.; Deng, S.; Draganic, I.N.; Harris, P.R.

    2012-01-01

    Recent activities at the ORNL Multicharged Ion Research Facility (MIRF) are summarized. A brief summary of the MIRF high voltage (HV) platform and floating beam line upgrade is provided. An expansion of our research program to the use of molecular ion beams in heavy-particle and electron collisions, as well as in ion surface interactions is described, and a brief description is provided of the most recently added Ion Cooling and Characterization End-station (ICCE) trap. With the expansion to include molecular ion beams, the acronym MIRF for the facility, however, remains unchanged: 'M' can now refer to either 'Multicharged' or 'Molecular'. The paper is followed by the slides of the presentation. (authors)

  13. A test matrix sequencer for research test facility automation

    Science.gov (United States)

    Mccartney, Timothy P.; Emery, Edward F.

    1990-01-01

    The hardware and software configuration of a Test Matrix Sequencer, a general purpose test matrix profiler that was developed for research test facility automation at the NASA Lewis Research Center, is described. The system provides set points to controllers and contact closures to data systems during the course of a test. The Test Matrix Sequencer consists of a microprocessor controlled system which is operated from a personal computer. The software program, which is the main element of the overall system is interactive and menu driven with pop-up windows and help screens. Analog and digital input/output channels can be controlled from a personal computer using the software program. The Test Matrix Sequencer provides more efficient use of aeronautics test facilities by automating repetitive tasks that were once done manually.

  14. An assessment of research opportunities and the need for synchrotron radiation facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    The workshop focused on six topics, all of which are areas of active research: (1) speciation, reactivity and mobility of contaminants in aqueous systems, (2) the role of surfaces and interfaces in molecular environmental science, (3) the role of solid phases in molecular environmental science, (4) molecular biological processes affecting speciation, reactivity, and mobility of contaminants in the environment, (5) molecular constraints on macroscopic- and field-scale processes, and (6) synchrotron radiation facilities and molecular environmental sciences. These topics span a range of important issues in molecular environmental science. They focus on the basic knowledge required for understanding contaminant transport and fate and for the development of science-based remediation and waste management technologies. Each topic was assigned to a working group charged with discussing recent research accomplishments, significant research opportunities, methods required for obtaining molecular-scale information on environmental contaminants and processes, and the value of synchrotron x-ray methods relative to other methods in providing this information. A special working group on synchrotron radiation facilities was convened to provide technical information about experimental facilities at the four DOE-supported synchrotron radiation sources in the US (NSLS, SSRL, AS and UPS) and synchrotron- based methods available for molecular environmental science research. Similar information on the NSF-funded Cornell High Energy synchrotron Source (CHESS) was obtained after the workshop was held.

  15. An assessment of research opportunities and the need for synchrotron radiation facilities

    International Nuclear Information System (INIS)

    1995-01-01

    The workshop focused on six topics, all of which are areas of active research: (1) speciation, reactivity and mobility of contaminants in aqueous systems, (2) the role of surfaces and interfaces in molecular environmental science, (3) the role of solid phases in molecular environmental science, (4) molecular biological processes affecting speciation, reactivity, and mobility of contaminants in the environment, (5) molecular constraints on macroscopic- and field-scale processes, and (6) synchrotron radiation facilities and molecular environmental sciences. These topics span a range of important issues in molecular environmental science. They focus on the basic knowledge required for understanding contaminant transport and fate and for the development of science-based remediation and waste management technologies. Each topic was assigned to a working group charged with discussing recent research accomplishments, significant research opportunities, methods required for obtaining molecular-scale information on environmental contaminants and processes, and the value of synchrotron x-ray methods relative to other methods in providing this information. A special working group on synchrotron radiation facilities was convened to provide technical information about experimental facilities at the four DOE-supported synchrotron radiation sources in the US (NSLS, SSRL, AS and UPS) and synchrotron- based methods available for molecular environmental science research. Similar information on the NSF-funded Cornell High Energy synchrotron Source (CHESS) was obtained after the workshop was held

  16. The WIPP research and development program: providing the technical basis for defense waste disposal

    International Nuclear Information System (INIS)

    Hunter, Th.O.

    1983-01-01

    The Waste Isolation Pilot Plant (WIPP), located in southeastern New Mexico, is being developed by the US Department of Energy as a research and development facility to demonstrate the safe disposal of radioactive wastes from the defense programs of the United States. Underground workings are at a depth of 660 in a bedded-salt formation. Site investigations began in the early 1970s and are culminating with the completion of the Site and Preliminary Design Validation (SPDV) program in 1983 in which two shafts and several thousand feet of underground drifts are being constructed. The underground facility will be used for in situ tests and demonstrations that address technical issues associated with the disposal of transuranic and defense high-level wastes (DHLW) in bedded salt. These tests are based on several years of laboratory tests, field tests in mines, and analytical modeling studies. They primarily address repository development in bedded salt, including thermal-structural interactions plugging and sealing, and facility operations; and waste package interactions, including the effects of the waste on local rock salt and the evaluation of waste package materials. In situ testing began in the WIPP with the initiation of the SPDV program in 1981. In 1983, a major series of tests will begin to investigate the response of the rock salt without the use of any radioactivity

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

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

  18. Report of researches by common utilization of facilities in Kyoto University Research Reactor Institute, latter half of fiscal year 1981

    International Nuclear Information System (INIS)

    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 61 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 radioactivation analysis of trace elements in rocks and minerals, anodic oxidation films of GaAs and structure, measurement of yield of uranium isotopes produced by reactor neutron irradiation of thorium, geochemical study of trace elements in hydrosphere by radio-activation analysis, various diseases and variation of elements in rat furs, Moessbauer spectroscopic study of gold compounds with singular coupling by Au-197, measurement of grass-eating quantity and rate of digestion of cows using Au and Eu, sickness biochemical study of trace elements in hair samples of patients and others. (Kako, I.)

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

    International Nuclear Information System (INIS)

    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 65 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 Moessbauer spectroscopic study of ferrocene and its derivative iodides by I-129, decomposition of cadmium telluride during heat treatment, element distribution in resource living things and environmental substances produced in northern ocean, radioactivation analysis of trace elements in blood of tumor-bearing animals, radioactivation analysis of noble metal elements in geochemical samples, relaxation phenomena by gamma-gamma perturbation angle correlation, separation of components in Allende meteorite and their radioactivation analysis, measurement of cross section of Pa-231 (n, gamma) reaction and others. (Kako, I.)

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

    International Nuclear Information System (INIS)

    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.)

  1. ARM Climate Research Facility Quarterly Value-Added Product Report

    Energy Technology Data Exchange (ETDEWEB)

    Sivaraman, Chitra

    2014-01-14

    The purpose of this report is to provide a concise status update for value-added products (VAP) implemented by the Atmospheric Radiation Measurement Climate Research Facility. The report is divided into the following sections: (1) new VAPs for which development has begun, (2) progress on existing VAPs, (3) future VAPs that have been recently approved, (4) other work that leads to a VAP, and (5) top requested VAPs from the archive.

  2. Basic Design of the Cold Neutron Research Facility in HANARO

    International Nuclear Information System (INIS)

    Kim, Hark Rho; Lee, K. H.; Kim, Y. K.

    2005-09-01

    The HANARO Cold Neutron Research Facility (CNRF) Project has been embarked in July 2003. The CNRF project has selected as one of the radiation technology development project by National Science and Technology Committee in June 2002. In this report, the output of the second project year is summarized as a basic design of cold neutron source and related systems, neutron guide, and neutron scattering instruments

  3. Basic Design of the Cold Neutron Research Facility in HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hark Rho; Lee, K. H.; Kim, Y. K. (and others)

    2005-09-15

    The HANARO Cold Neutron Research Facility (CNRF) Project has been embarked in July 2003. The CNRF project has selected as one of the radiation technology development project by National Science and Technology Committee in June 2002. In this report, the output of the second project year is summarized as a basic design of cold neutron source and related systems, neutron guide, and neutron scattering instruments.

  4. ARM Climate Research Facility Quarterly Ingest Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Koontz, A. [DOE ARM Climate Research Facility, Washington, DC (United States); Sivaraman, C. [DOE ARM Climate Research Facility, Washington, DC (United States)

    2016-10-01

    The purpose of this report is to provide a concise status update for ingests maintained by the Atmospheric Radiation Measurement (ARM) Climate Research Facility. The report is divided into the following sections: (1) new ingests for which development has begun, (2) progress on existing ingests, (3) future ingests that have been recently approved, (4) other work that leads to an ingest, and (5) top requested ingests from the ARM Data Archive. New information is highlighted in blue text.

  5. ARM Climate Research Facility Quarterly Ingest Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Koontz, A. [ARM Climate Reesearch Facility, Washington, DC (United States); Sivaraman, C. [ARM Climate Reesearch Facility, Washington, DC (United States)

    2016-07-01

    The purpose of this report is to provide a concise status update for ingests maintained by the Atmospheric Radiation Measurement (ARM) Climate Research Facility. The report is divided into the following sections: (1) new ingests for which development has begun, (2) progress on existing ingests, (3) future ingests that have been recently approved, (4) other work that leads to an ingest, and (5) top requested ingests from the ARM Data Archive. New information is highlighted in blue text.

  6. Technical specifications for the Oak Ridge Research Reactor

    International Nuclear Information System (INIS)

    1982-03-01

    Technical specifications are presented concerning safety limits and limiting safety system settings; limiting conditions for operation; surveillance requirements; design features; and administrative controls

  7. Identification of Vital Areas at Nuclear Facilities. Technical Guidance (French Edition)

    International Nuclear Information System (INIS)

    2015-01-01

    The possibility that nuclear or other radioactive material could be used for malicious purposes cannot be ruled out in the current global situation. States have responded to this risk by engaging in a collective commitment to strengthen the protection and control of such material and to effectively respond to nuclear security events. States have agreed to strengthen existing and established new international legal instruments to enhance nuclear security around the world. Nuclear security is fundamental in the management of nuclear technologies and in applications where nuclear or other radioactive material is used or transported. Through its nuclear security programme, the IAEA supports States to establish, maintain and sustain an effective nuclear security regime. The IAEA has adopted a comprehensive approach to nuclear security. This recognizes that an effective national nuclear security regime builds on: the implementation of relevant international legal instruments; information protection; physical protection; material accounting and control; detection of and response to trafficking in such material; national response plans; and contingency measures. With its nuclear security series, the IAEA aims to assist States to implement and sustain such a regime in a coherent and integrated manner. The IAEA Nuclear Security Series comprises: Nuclear Security Fundamentals, which include objectives and essential elements of a State?s nuclear security regime; Recommendations; Implementing Guides; and Technical Guidance publications. Each State carries the full responsibility for nuclear security, i.e. to provide for the security of nuclear and other radioactive material and associated facilities and activities; to ensure the security of such material in use, storage or in transport; and to combat illicit trafficking and the inadvertent movement of such material. It should also be prepared to respond to a nuclear security event. The IAEA recommendations for the protection of

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

    International Nuclear Information System (INIS)

    2013-11-01

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

  9. "Atmospheric Radiation Measurement (ARM) Research Facility at Oliktok Point Alaska"

    Science.gov (United States)

    Helsel, F.; Ivey, M.; Hardesty, J.; Roesler, E. L.; Dexheimer, D.

    2017-12-01

    Scientific Infrastructure To Support Atmospheric Science, Aerosol Science and UAS's for The Department Of Energy's Atmospheric Radiation Measurement Programs At The Mobile Facility 3 Located At Oliktok Point, Alaska.The Atmospheric Radiation Measurement (ARM) Program's Mobile Facility 3 (AMF3) located at Oliktok Point, Alaska is a U.S. Department of Energy (DOE) site designed to collect data and help determine the impact that clouds and aerosols have on solar radiation. AMF3 provides a scientific infrastructure to support instruments and collect arctic data for the international arctic research community. The infrastructure at AMF3/Oliktok is designed to be mobile and it may be relocated in the future to support other ARM science missions. AMF3's present base line instruments include: scanning precipitation Radars, cloud Radar, Raman Lidar, Eddy correlation flux systems, Ceilometer, Balloon sounding system, Atmospheric Emitted Radiance Interferometer (AERI), Micro-pulse Lidar (MPL) Along with all the standard metrological measurements. In addition AMF3 provides aerosol measurements with a Mobile Aerosol Observing System (MAOS). Ground support for Unmanned Aerial Systems (UAS) and tethered balloon flights. Data from these instruments and systems are placed in the ARM data archives and are available to the international research community. This poster will discuss what instruments and systems are at the ARM Research Facility at Oliktok Point Alaska.

  10. Atmospheric Radiation Measurement Climate Research Facility (ACRF) Annual Report 2007

    Energy Technology Data Exchange (ETDEWEB)

    LR Roeder

    2007-12-01

    This annual report describes the purpose and structure of the program, and presents key accomplishments in 2007. Notable achievements include: • Successful review of the ACRF as a user facility by the DOE Biological and Environmental Research Advisory Committee. The subcommittee reinforced the importance of the scientific impacts of this facility, and its value for the international research community. • Leadership of the Cloud Land Surface Interaction Campaign. This multi-agency, interdisciplinary field campaign involved enhanced surface instrumentation at the ACRF Southern Great Plains site and, in concert with the Cumulus Humilis Aerosol Processing Study sponsored by the DOE Atmospheric Science Program, coordination of nine aircraft through the ARM Aerial Vehicles Program. • Successful deployment of the ARM Mobile Facility in Germany, including hosting nearly a dozen guest instruments and drawing almost 5000 visitors to the site. • Key advancements in the representation of radiative transfer in weather forecast models from the European Centre for Medium-Range Weather Forecasts. • Development of several new enhanced data sets, ranging from best estimate surface radiation measurements from multiple sensors at all ACRF sites to the extension of time-height cloud occurrence profiles to Niamey, Niger, Africa. • Publication of three research papers in a single issue (February 2007) of the Bulletin of the American Meteorological Society.

  11. Progress in developing the concept for the irradiation research facility

    International Nuclear Information System (INIS)

    Lee, A.G.; Bishop, W.E.; Gillespie, G.E.; Zeng, Y.

    1996-04-01

    At the 16th annual Canadian Nuclear Society conference, AECL presented the case for replacing the NRU reactor with an Irradiation Research Facility (IRF) to test CANDU fuels and materials and to perform advanced materials research using neutrons. AECL developed a cost estimate of $500 million for the reference IRF concept, and estimated that it would require 87 months to complete. AECL has initiated a pre-project program to develop the IRF concept and to minimize uncertainties related to feasibility and licensability, and to examine options for reducing the overall project cost before project implementation begins. (author) 10 refs., 2 figs

  12. The neutron radiography facility at Tehran Research Reactor (TRR)

    International Nuclear Information System (INIS)

    Ali Pazirandeh

    2009-01-01

    Full text: Non-destructive testing in many fields of industry including detection of explosives, at the airports, testing for micro-cracks on airplane wings and turbine blades cracks is badly needed. Thermal neutron beam is one of preferable method to detect the micro-cracks, reveals the internal structure of components and explosives. The purpose of this paper is to present the neutron radiography facility at Tehran Research Reactor (TRR), Science and Technology Research Institute, and in particular to emphasize the industrial applications in wood industry, automobile engine inspection, minerals composition identification, turbine blade cracks detection. (author)

  13. SRTC criticality technical review: Nuclear Criticality Safety Evaluation 93-18 Uranium Solidification Facility's Waste Handling Facility

    International Nuclear Information System (INIS)

    Rathbun, R.

    1993-01-01

    Separate review of NMP-NCS-930058, open-quotes Nuclear Criticality Safety Evaluation 93-18 Uranium Solidification Facility's Waste Handling Facility (U), August 17, 1993,close quotes was requested of SRTC Applied Physics Group. The NCSE is a criticality assessment to determine waste container uranium limits in the Uranium Solidification Facility's Waste Handling Facility. The NCSE under review concludes that the NDA room remains in a critically safe configuration for all normal and single credible abnormal conditions. The ability to make this conclusion is highly dependent on array limitation and inclusion of physical barriers between 2x2x1 arrays of boxes containing materials contaminated with uranium. After a thorough review of the NCSE and independent calculations, this reviewer agrees with that conclusion

  14. The neutron beam facility at the Australian replacement research reactor

    International Nuclear Information System (INIS)

    Hunter, B.; Kennedy, S.

    1999-01-01

    Full text: The Australian federal government gave ANSTO final approval to build a research reactor to replace HIFAR on August 25th 1999. The replacement reactor is to be a multipurpose reactor with a thermal neutron flux of 3 x 10 14 n.cm -2 .s -1 and having improved capabilities for neutron beam research and for the production of radioisotopes for pharmaceutical, scientific and industrial use. The replacement reactor will commence operation in 2005 and will cater for Australian scientific, industrial and medical needs well into the 21st century. The scientific capabilities of the neutron beams at the replacement reactor are being developed in consultation with representatives from academia, industry and government research laboratories to provide a facility for condensed matter research in physics, chemistry, materials science, life sciences, engineering and earth sciences. Cold, thermal and hot neutron sources are to be installed, and neutron guides will be used to position most of the neutron beam instruments in a neutron guide hall outside the reactor confinement building. Eight instruments are planned for 2005, with a further three to be developed by 2010. A conceptual layout for the neutron beam facility is presented including the location of the planned suite of neutron beam instruments. The reactor and all the associated infrastructure, with the exception of the neutron beam instruments, is to be built by an accredited reactor builder in a turnkey contract. Tenders have been called for December 1999, with selection of contractor planned by June 2000. The neutron beam instruments will be developed by ANSTO and other contracted organisations in consultation with the user community and interested overseas scientists. The facility will be based, as far as possible, around a neutron guide hall that is be served by three thermal and three cold neutron guides. Efficient transportation of thermal and cold neutrons to the guide hall requires the use of modern super

  15. Development of Regulatory Technical Requirements for the Advanced Integral Type Research Reactor

    International Nuclear Information System (INIS)

    Jo, Jong Chull; Yune, Young Gill; Kim, Woong Sik; Kim, Hho Jung

    2004-01-01

    This paper presents the current status of the study on the development of regulatory technical requirements for the licensing review of an advanced integral type research reactor of which the license application is expected in a few years. According to the Atomic Energy Act of Korea, both research and education reactors are subject to the technical requirements for power reactors in the licensing review. But, some of the requirements may not be applicable or insufficient for the licensing reviews of reactors with unique design features. Thus it is necessary to identify which review topics or areas can not be addressed by the existing requirements and to develop the required ones newly or supplement appropriately. Through the study performed so far, it has been identified that the following requirements need to be developed newly for the licensing review of SMART-P: the use of proven technology, the interfacial facility, the non-safety systems, and the metallic fuels. The approach and basis for the development of each of the requirements are discussed. (authors)

  16. Scientist, Single Cell Analysis Facility | Center for Cancer Research

    Science.gov (United States)

    The Cancer Research Technology Program (CRTP) develops and implements emerging technology, cancer biology expertise and research capabilities to accomplish NCI research objectives.  The CRTP is an outward-facing, multi-disciplinary hub purposed to enable the external cancer research community and provides dedicated support to NCI’s intramural Center for Cancer Research (CCR).  The dedicated units provide electron microscopy, protein characterization, protein expression, optical microscopy and nextGen sequencing. These research efforts are an integral part of CCR at the Frederick National Laboratory for Cancer Research (FNLCR).  CRTP scientists also work collaboratively with intramural NCI investigators to provide research technologies and expertise. KEY ROLES AND RESPONSIBILITIES We are seeking a highly motivated Scientist II to join the newly established Single Cell Analysis Facility (SCAF) of the Center for Cancer Research (CCR) at NCI. The SCAF will house state of the art single cell sequencing technologies including 10xGenomics Chromium, BD Genomics Rhapsody, DEPPArray, and other emerging single cell technologies. The Scientist: Will interact with close to 200 laboratories within the CCR to design and carry out single cell experiments for cancer research Will work on single cell isolation/preparation from various tissues and cells and related NexGen sequencing library preparation Is expected to author publications in peer reviewed scientific journals

  17. Scientific and technical information output of the Langley Research Center for calendar year 1984

    Science.gov (United States)

    1985-01-01

    The scientific and technical information that the Langley Research Center produced during the calendar year 1984 is compiled. Approximately 1650 citations are included comprising formal reports, quick-release technical memorandums, contractor reports, journal articles and other publications, meeting presentations, technical talks, computer programs, tech briefs, and patents.

  18. Scientific and technical information output of the Langley Research Center for Calendar Year 1985

    Science.gov (United States)

    1986-01-01

    A compilation of the scientific and technical information that the Langley Research Center has produced during the calendar year 1985 is presented. Included are citations for Formal Reports, Quick-Release Technical Memorandums, Contractor Reports, Journal Articles and Other Publications, Meeting Presentations, Technical Talks, Computer Programs, Tech Briefs, and Patents.

  19. Planning and management for the decommissioning of research reactors and other small nuclear facilities

    International Nuclear Information System (INIS)

    1993-01-01

    Many research reactors and other small nuclear facilities throughout the world date from the original nuclear research programmes in the Member States. Consequently, a large number of these plants have either been retired from service or will soon reach the end of their useful lives and are likely to become significant decommissioning tasks for those Members States. In recognition of this situation and in response to considerable interest shown by Member States, the IAEA has produced this document on planning and management for the decommissioning of research reactors and other small nuclear facilities. While not directed specifically at large nuclear installations, it is likely that much of the information presented will also be of interest to those involved in the decommissioning of such facilities. Current views, information and experience on the planning and management of decommissioning projects in Member States were collected and assessed during a Technical Committee Meeting held by the IAEA in Vienna from 29 July to 2 August 1991. It was attended by 22 participants from 14 Member States and one international organization. 28 refs, 2 figs, 3 tabs

  20. Technical Safety Requirements for the B695 Segment of the Decontamination and Waste Treatment Facility

    International Nuclear Information System (INIS)

    Larson, H L

    2007-01-01

    This document contains Technical Safety Requirements (TSRs) for the Radioactive and Hazardous Waste Management (RHWM) Division's B695 Segment of the Decontamination and Waste Treatment Facility (DWTF) at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the B695 Segment of the DWTF. The TSRs are derived from the Documented Safety Analysis (DSA) for the B695 Segment of the DWTF (LLNL 2004). The analysis presented there determined that the B695 Segment of the DWTF is a low-chemical hazard, Hazard Category 3, nonreactor nuclear facility. The TSRs consist primarily of inventory limits as well as controls to preserve the underlying assumptions in the hazard analyses. Furthermore, appropriate commitments to safety programs are presented in the administrative controls section of the TSRs. The B695 Segment of the DWTF (B695 and the west portion of B696) is a waste treatment and storage facility located in the northeast quadrant of the LLNL main site. The approximate area and boundary of the B695 Segment of the DWTF are shown in the B695 Segment of the DWTF DSA. Activities typically conducted in the B695 Segment of the DWTF include container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. B695 is used to store and treat radioactive, mixed, and hazardous waste, and it also contains equipment used in conjunction with waste processing operations to treat various liquid and solid wastes. The portion of the building called Building 696 Solid Waste Processing Area (SWPA), also referred to as B696S in this report, is used primarily to manage solid radioactive waste. Operations specific to the SWPA include sorting and segregating low-level waste (LLW) and transuranic (TRU) waste, lab-packing, sampling, and crushing empty drums that previously contained LLW. A permit modification for B696S was submitted to DTSC in January 2004 to store and treat hazardous and mixed

  1. Technical Safety Requirements for the B695 Segment of the Decontamination and Waste Treatment Facility

    Energy Technology Data Exchange (ETDEWEB)

    Larson, H L

    2007-09-07

    This document contains Technical Safety Requirements (TSRs) for the Radioactive and Hazardous Waste Management (RHWM) Division's B695 Segment of the Decontamination and Waste Treatment Facility (DWTF) at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the B695 Segment of the DWTF. The TSRs are derived from the Documented Safety Analysis (DSA) for the B695 Segment of the DWTF (LLNL 2004). The analysis presented there determined that the B695 Segment of the DWTF is a low-chemical hazard, Hazard Category 3, nonreactor nuclear facility. The TSRs consist primarily of inventory limits as well as controls to preserve the underlying assumptions in the hazard analyses. Furthermore, appropriate commitments to safety programs are presented in the administrative controls section of the TSRs. The B695 Segment of the DWTF (B695 and the west portion of B696) is a waste treatment and storage facility located in the northeast quadrant of the LLNL main site. The approximate area and boundary of the B695 Segment of the DWTF are shown in the B695 Segment of the DWTF DSA. Activities typically conducted in the B695 Segment of the DWTF include container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. B695 is used to store and treat radioactive, mixed, and hazardous waste, and it also contains equipment used in conjunction with waste processing operations to treat various liquid and solid wastes. The portion of the building called Building 696 Solid Waste Processing Area (SWPA), also referred to as B696S in this report, is used primarily to manage solid radioactive waste. Operations specific to the SWPA include sorting and segregating low-level waste (LLW) and transuranic (TRU) waste, lab-packing, sampling, and crushing empty drums that previously contained LLW. A permit modification for B696S was submitted to DTSC in January 2004 to store and treat hazardous and

  2. Status of the Holifield Heavy Ion Research Facility

    International Nuclear Information System (INIS)

    Martin, J.A.

    1978-01-01

    The Holifield Heavy Ion Research Facility presently operates the Oak Ridge Isochronous Cyclotron (ORIC). This accelerator provides heavy ions up to argon with energies useful for nuclear physics. The Phase I expansion of this facility, now a year away from completion, includes a 25-MV vertical folded tandem accelerator, beam transport and injection systems to use the ORIC as an energy booster, and additional experiment areas for the beams directly from the tandem. The tandem--cyclotron combination will provide heavy ions with energies up to 25 MeV/A for A 11 particles/sec. Building construction for the project is essentially complete. The accelerator manufacturer, National Electrostatics Corporation, has completed installation and testing of the 10-m-diam by 30-m-high accelerator pressure vessel and has begun installation of the accelerator systems. The accelerator has previously been assembled at the NEC plant and the digital control system operated without voltage on the column. Voltage tests are expected to begin in Oak Ridge in January 1979 with beam tests to begin in March. Completion of the project, including acceptance tests of the tandem and the beam injection system for ORIC is presently scheduled for November 15, 1979. Construction of Phase II for the facility wich will include a much larger booster cyclotron and additional research areas is expected to begin in 1982

  3. Construction of a Solid State Research Facility, Building 3150

    International Nuclear Information System (INIS)

    1993-07-01

    The Department of Energy (DOE) proposes to construct a new facility to house the Materials Synthesis Group (MSG) and the Semiconductor Physics Group (SPG) of the Solid State Division, Oak Ridge National Laboratory (ORNL). The location of the proposed action is Roane County, Tennessee. MSG is involved in the study of crystal growth and the preparation and characterization of advanced materials, such as high-temperature superconductors, while SPG is involved in semiconductor physics research. All MSG and a major pardon of SPG research activities are now conducted in Building 2000, a deteriorating structure constructed in the 1940. The physical deterioration of the roof; the heating, ventilation, and air conditioning (HVAC) system; and the plumbing make this building inadequate for supporting research activities. The proposed project is needed to provide laboratory and office space for MSG and SPG and to ensure that research activities can continue without interruption due to deficiencies in the building and its associated utility systems

  4. NTRCI Legacy Engine Research and Development Project Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Smith-Holbert, Connie [National Transportation Research Center, Inc., Knoxville, TN (United States); Petrolino, Joseph [National Transportation Research Center, Inc., Knoxville, TN (United States); Watkins, Bart [Power Source Technologies Inc., Corvallis, OR (United States); Irick, David [Power Source Technologies Inc., Corvallis, OR (United States)

    2011-12-31

    The Legacy engine is a completely new design, transitional diesel engine, replacing the reciprocating engine with a rotary engine. The Legacy engine offers significant advances over conventional internal combustion engines in 1) power to weight ratio; 2) multiple fuel acceptance; 3) fuel economy; and 4) environmental compliance. These advances are achieved through a combination of innovative design geometry, rotary motion, aspiration simplicity, and manufacturing/part simplicity. The key technical challenge to the Legacy engine's commercialization, and the focus of this project, was the development of a viable roton tip seal. The PST concept for the roton tip seal was developed into a manufacturable design. The design was evaluated using a custom designed and fabricated seal test fixture and further refined. This design was incorporated into the GEN2.5A prototype and tested for achievable compression pressure. The Decision Point at the end of Phase 1 of the project (described below) was to further optimize the existing tip seal design. Enhancements to the tip seal design were incorporated into the GEN2.5B prototype and tested and evaluated using the iterative research strategy described below. Compression pressures adequate for compression ignition of diesel fuel were achieved, although not consistently in all combustion volumes. The variation in compression pressures was characterized versus design features. As the roton tip seal performance was improved, results pointed toward inadequate performance of the housing side seals. Enhancement of the housing side seal system was accomplished using a custom designed side seal test fixture. The design enhancements developed with the test fixture were also incorporated into the GEN2.5B prototype and tested and evaluated using the iterative research strategy described below. Finally, to simplify the requirements for the roton tip seals and to enhance the introduction and combustion of fuel, a flush-mount fuel injector

  5. Radiological Characterization and Final Facility Status Report Tritium Research Laboratory

    International Nuclear Information System (INIS)

    Garcia, T.B.; Gorman, T.P.

    1996-08-01

    This document contains the specific radiological characterization information on Building 968, the Tritium Research Laboratory (TRL) Complex and Facility. We performed the characterization as outlined in its Radiological Characterization Plan. The Radiological Characterization and Final Facility Status Report (RC ampersand FFSR) provides historic background information on each laboratory within the TRL complex as related to its original and present radiological condition. Along with the work outlined in the Radiological Characterization Plan (RCP), we performed a Radiological Soils Characterization, Radiological and Chemical Characterization of the Waste Water Hold-up System including all drains, and a Radiological Characterization of the Building 968 roof ventilation system. These characterizations will provide the basis for the Sandia National Laboratory, California (SNL/CA) Site Termination Survey .Plan, when appropriate

  6. A research on threat (hazard) categorization method for nuclear facilities

    International Nuclear Information System (INIS)

    Tang Rongyao; Xu Xiaoxiao; Zhang Jiangang; Zhao Bin; Wang Xuexin

    2011-01-01

    The threat categorization method suggested by International Atomic Energy Agency (IAEA) and hazard categorization standard by the Department of Energy of United States (USDOE) for nuclear facilities are compared and discussed in this paper. The research shows the two types of categorization method for nuclear facilities are similar, though each has its own specialty. The categorization method suggested by IAEA for the purpose of emergency planning is quite completed and updated. The categorization method of DOE is advanced in its operability, and fits for safety surveillance. But the dispersible radioactive material thresholds used for categorization need to be updated. The threshold of category 3 is somewhat disputable for many reasons. The recommended categorization method for China is also given in this paper. (author)

  7. Zebra Mussel Research Technical Notes. Section 1 - Environmental Testing

    National Research Council Canada - National Science Library

    1998-01-01

    ...: Biology, Ecology, and Recommended Control Strategies, Larval Monitoring in a Chlorine Treatment Program to Prevent Zebra Mussel Settlement in Hydropower Facilities, Louisville District Initiates...

  8. Training and research reactor facility longevity extension program

    International Nuclear Information System (INIS)

    Carriveau, G.W.

    1991-01-01

    Since 1943, over 550 training and research reactors have been in operation. According to statistics from the International Atomic Energy Agency, ∼325 training and research reactors are currently in service. This total includes a wide variety of designs covering a range of power and research capabilities located virtually around the world. A program has been established at General Atomics (GA) that is dedicated to the support of extended longevity of training and research reactor facilities. Aspects of this program include the following: (1) new instrumentation and control systems; (2) improved and upgraded nuclear monitoring and control channels; (3) facility testing, repair and upgrade services that include (a) pool or tank integrity, (b) cooling system, and (c) water purification system; (4) fuel element testing procedures and replacement; (5) control rod drive rebuilding and upgrades; (6) control and monitoring system calibration and repair service; (7) training services, including reactor operations, maintenance, instrumentation calibration, and repair; and (8) expanded or new uses such as neutron radiography and autoradiography, isotope production, nuclear medicine, activation analysis, and material properties modification

  9. First Materials Science Research Facility Rack Capabilities and Design Features

    Science.gov (United States)

    Cobb, S.; Higgins, D.; Kitchens, L.; Curreri, Peter (Technical Monitor)

    2002-01-01

    The first Materials Science Research Rack (MSRR-1) is the primary facility for U.S. sponsored materials science research on the International Space Station. MSRR-1 is contained in an International Standard Payload Rack (ISPR) equipped with the Active Rack Isolation System (ARIS) for the best possible microgravity environment. MSRR-1 will accommodate dual Experiment Modules and provide simultaneous on-orbit processing operations capability. The first Experiment Module for the MSRR-1, the Materials Science Laboratory (MSL), is an international cooperative activity between NASA's Marshall Space Flight Center (MSFC) and the European Space Agency's (ESA) European Space Research and Technology Center (ESTEC). The MSL Experiment Module will accommodate several on-orbit exchangeable experiment-specific Module Inserts which provide distinct thermal processing capabilities. Module Inserts currently planned for the MSL are a Quench Module Insert, Low Gradient Furnace, and a Solidification with Quench Furnace. The second Experiment Module for the MSRR-1 configuration is a commercial device supplied by MSFC's Space Products Development (SPD) Group. Transparent furnace assemblies include capabilities for vapor transport processes and annealing of glass fiber preforms. This Experiment Module is replaceable on-orbit. This paper will describe facility capabilities, schedule to flight and research opportunities.

  10. ARM Climate Research Facility: Outreach Tools and Strategies

    Science.gov (United States)

    Roeder, L.; Jundt, R.

    2009-12-01

    Sponsored by the Department of Energy, the ARM Climate Research Facility is a global scientific user facility for the study of climate change. To publicize progress and achievements and to reach new users, the ACRF uses a variety of Web 2.0 tools and strategies that build off of the program’s comprehensive and well established News Center (www.arm.gov/news). These strategies include: an RSS subscription service for specific news categories; an email “newsletter” distribution to the user community that compiles the latest News Center updates into a short summary with links; and a Facebook page that pulls information from the News Center and links to relevant information in other online venues, including those of our collaborators. The ACRF also interacts with users through field campaign blogs, like Discovery Channel’s EarthLive, to share research experiences from the field. Increasingly, field campaign Wikis are established to help ACRF researchers collaborate during the planning and implementation phases of their field studies and include easy to use logs and image libraries to help record the campaigns. This vital reference information is used in developing outreach material that is shared in highlights, news, and Facebook. Other Web 2.0 tools that ACRF uses include Google Maps to help users visualize facility locations and aircraft flight patterns. Easy-to-use comment boxes are also available on many of the data-related web pages on www.arm.gov to encourage feedback. To provide additional opportunities for increased interaction with the public and user community, future Web 2.0 plans under consideration for ACRF include: evaluating field campaigns for Twitter and microblogging opportunities, adding public discussion forums to research highlight web pages, moving existing photos into albums on FlickR or Facebook, and building online video archives through YouTube.

  11. Western Canada study of animal health effects associated with exposure to emissions from oil and gas field facilities : technical summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-01-15

    The impact of exposure to emissions from oil and gas field facilities on animal and human health has been a long-standing concern in western Canada. This technical summary presented highlights of the 17 major research appendices of a study examining associations between emissions and important reproductive parameters in beef cattle, including pregnancy rates, frequencies of abortions and stillbirths, and the risk of death among young calves. The effect of exposure to emissions on the respiratory, immune and nervous systems of calves and yearlings was also evaluated. The study was an epidemiological investigation that drew on large blocks of data collected from privately owned cow-calf operations, laboratory analyses of biological samples and samplers from air monitors. Mixed effect regression models were used to investigate whether measures of reproductive, immunological, and pathology outcomes were associated with emissions from the petroleum industry. Appropriate statistical adjustments were made to correct for multiple comparisons following standard statistical practice. An overview of the methods used to analyze the data was presented, as well as an examination of the methods of epidemiology in determining a causal effect, and the limitations of a single study in determining causation with certainty. Information on water quality testing and feeding management and forage testing was provided. 15 tabs., 26 figs.

  12. Western Canada study of animal health effects associated with exposure to emissions from oil and gas field facilities : technical summary

    International Nuclear Information System (INIS)

    2006-01-01

    The impact of exposure to emissions from oil and gas field facilities on animal and human health has been a long-standing concern in western Canada. This technical summary presented highlights of the 17 major research appendices of a study examining associations between emissions and important reproductive parameters in beef cattle, including pregnancy rates, frequencies of abortions and stillbirths, and the risk of death among young calves. The effect of exposure to emissions on the respiratory, immune and nervous systems of calves and yearlings was also evaluated. The study was an epidemiological investigation that drew on large blocks of data collected from privately owned cow-calf operations, laboratory analyses of biological samples and samplers from air monitors. Mixed effect regression models were used to investigate whether measures of reproductive, immunological, and pathology outcomes were associated with emissions from the petroleum industry. Appropriate statistical adjustments were made to correct for multiple comparisons following standard statistical practice. An overview of the methods used to analyze the data was presented, as well as an examination of the methods of epidemiology in determining a causal effect, and the limitations of a single study in determining causation with certainty. Information on water quality testing and feeding management and forage testing was provided. 15 tabs., 26 figs

  13. Seismic evaluation of existing nuclear power plants and other facilities V. 1. Proceedings of the technical committee meeting. Working material

    International Nuclear Information System (INIS)

    2002-01-01

    The objectives of this Tcm are: to review the IAEA Safety Report on Seismic Evaluation of Existing Nuclear Power Plants in order to achieve a consensus among Member States on this matter and to discuss the outlines of an IAEA Co-ordinated Research Programme on specific topics related to this subject. Today the nuclear industry relies much more on existing facilities than on the design of new ones. Nevertheless it appears that safety evaluation against external hazards is not a decreasing activity. The reason being that maintaining an acceptable level of nuclear safety requires periodic re-assessments of facilities, either because of modifications of the environment due to human activity or because of new data or new approaches in the assessment of natural hazards. In this regard, seismic re-evaluation has increasingly become a key issue for several existing nuclear facilities, including not only nuclear power plants but also other plants of the fuel cycle, as well as research reactors or laboratories. The IAEA has already supported development of engineering practices in this field by managing a Co-ordinated Research Programme, launched in 1992, on a Benchmark Study for the seismic analysis and testing of WWER 1000 type NPPs. It is now proposed to investigate other aspects of this issue. Many of these facilities were built according to older standards which did not take into account seismic hazard. Consequently, the seismic re-evaluation of existing facilities is a real challenge for earthquake engineers. In most of the cases, it is impossible to re-evaluate according to the up to date standards because entering these standards implies that some design rules are met, what is generally not the case for older facilities. In the best cases some rules exist for non nuclear buildings. In order to achieve a consensus on this matter, the IAEA intends to edit a Safety Report on 'Seismic Evaluation of existing NPPs'. The TCM will offer the opportunity to review the draft of

  14. Some technical aspects of the nuclear material accounting and control at nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Miller, O.A.; Babaev, N.S.; Gryazev, V.M.; Gadzhiev, G.I.; Gabeskiriya, V.Ya.

    1977-01-01

    The possibilities of nuclear material accounting and control are discussed at nuclear facilities of fuel cycle (WWER-type reactor, fuel fabrication plant, reprocessing plant and uranium enrichment facility) and zero energy fast reactor facility. It is shown that for nuclear material control the main method is the accounting with the application isotopic correlations at the reprocessing plant and enrichment facility. Possibilities and limitations of the application of destructive and non-destructive methods are discussed for nuclear material determinations at fuel facilities and their role in the accounting and safeguards systems as well as possibilities of the application of neutron method at a zero energy fast reactor facility [ru

  15. Neutron beam facilities at the Replacement Research Reactor, ANSTO

    International Nuclear Information System (INIS)

    Kim, S.

    2003-01-01

    The exciting development for Australia is the construction of a modern state-of-the-art 20-MW Replacement Research Reactor which is currently under construction to replace the aging reactor (HIFAR) at ANSTO in 2006. To cater for advanced scientific applications, the replacement reactor will provide not only thermal neutron beams but also a modern cold-neutron source moderated by liquid deuterium at approximately -250 deg C, complete with provision for installation of a hot-neutron source at a later stage. The latest 'supermirror' guides will be used to transport the neutrons to the Reactor Hall and its adjoining Neutron Guide Hall where a suite of neutron beam instruments will be installed. These new facilities will expand and enhance ANSTO's capabilities and performance in neutron beam science compared with what is possible with the existing HIFAR facilities, and will make ANSTO/Australia competitive with the best neutron facilities in the world. Eight 'leading-edge' neutron beam instruments are planned for the Replacement Research Reactor when it goes critical in 2006, followed by more instruments by 2010 and beyond. Up to 18 neutron beam instruments can be accommodated at the Replacement Research Reactor, however, it has the capacity for further expansion, including potential for a second Neutron Guide Hall. The first batch of eight instruments has been carefully selected in conjunction with a user group representing various scientific interests in Australia. A team of scientists, engineers, drafting officers and technicians has been assembled to carry out the Neutron Beam Instrument Project to successful completion. Today, most of the planned instruments have conceptual designs and are now being engineered in detail prior to construction and procurement. A suite of ancillary equipment will also be provided to enable scientific experiments at different temperatures, pressures and magnetic fields. This paper describes the Neutron Beam Instrument Project and gives

  16. Congressional hearing reviews NSF major research and facilities projects

    Science.gov (United States)

    Showstack, Randy

    2012-03-01

    An 8 March congressional hearing about the U.S. National Science Foundation's Major Research Equipment and Facilities Construction (NSF MREFC) account focused on fiscal management and accountability of projects in that account and reviewed concerns raised by NSF's Office of Inspector General (OIG). NSF established the MREFC account in 1995 to better plan and manage investments in major equipment and facilities projects, which can cost from tens of millions to hundreds of millions of dollars, and the foundation has funded 17 MREFC projects since then. The Obama administration's proposed fiscal year (FY) 2013 budget includes funding for four MREFC projects: Advanced Laser Gravitational-Wave Observatory (AdvLIGO), Advanced Technology Solar Telescope (ATST), National Ecological Observatory (NEON), and Ocean Observatories Initiative (OOI). The hearing, held by a subcommittee of the House of Representatives' Committee on Science, Space, and Technology, reviewed management oversight throughout the life cycles of MREFC projects and concerns raised in recent OIG reports about the use of budget contingency funds. NSF's February 2012 manual called "Risk management guide for large facilities" states that cost contingency is "that portion of the project budget required to cover `known unknowns,'" such as planning and estimating errors and omissions, minor labor or material price fluctuations, and design developments and changes within the project scope. Committee members acknowledged measures that NSF has made to improve the MREFC oversight process, but they also urged the agency to continue to take steps to ensure better project management.

  17. The Development of the Acoustic Design of NASA Glenn Research Center's New Reverberant Acoustic Test Facility

    Science.gov (United States)

    Hughes, William O.; McNelis, Mark E.; Hozman, Aron D.; McNelis, Anne M.

    2011-01-01

    The National Aeronautics and Space Administration (NASA) Glenn Research Center (GRC) is leading the design and build of the new world-class vibroacoustic test capabilities at the NASA GRC s Plum Brook Station in Sandusky, Ohio. Benham Companies, LLC is currently constructing modal, base-shake sine and reverberant acoustic test facilities to support the future testing needs of NASA s space exploration program. The large Reverberant Acoustic Test Facility (RATF) will be approximately 101,000 ft3 in volume and capable of achieving an empty chamber acoustic overall sound pressure level (OASPL) of 163 dB. This combination of size and acoustic power is unprecedented amongst the world s known active reverberant acoustic test facilities. The key to achieving the expected acoustic test spectra for a range of many NASA space flight environments in the RATF is the knowledge gained from a series of ground acoustic tests. Data was obtained from several NASA-sponsored test programs, including testing performed at the National Research Council of Canada s acoustic test facility in Ottawa, Ontario, Canada, and at the Redstone Technical Test Center acoustic test facility in Huntsville, Alabama. The majority of these tests were performed to characterize the acoustic performance of the modulators (noise generators) and representative horns that would be required to meet the desired spectra, as well as to evaluate possible supplemental gas jet noise sources. The knowledge obtained in each of these test programs enabled the design of the RATF sound generation system to confidently advance to its final acoustic design and subsequent on-going construction.

  18. Catalogue and classification of technical safety standards, rules and regulations for nuclear power reactors and nuclear fuel cycle facilities

    International Nuclear Information System (INIS)

    Fichtner, N.; Becker, K.; Bashir, M.

    1977-01-01

    The present report is an up-dated version of the report 'Catalogue and Classification of Technical Safety Rules for Light-water Reactors and Reprocessing Plants' edited under code No EUR 5362e, August 1975. Like the first version of the report, it constitutes a catalogue and classification of standards, rules and regulations on land-based nuclear power reactors and fuel cycle facilities. The reasons for the classification system used are given and discussed

  19. Cosmic muon flux measurements at the Kimballton Underground Research Facility

    International Nuclear Information System (INIS)

    Kalousis, L N; Guarnaccia, E; Link, J M; Mariani, C; Pelkey, R

    2014-01-01

    In this article, the results from a series of muon flux measurements conducted at the Kimballton Underground Research Facility (KURF), Virginia, United States, are presented. The detector employed for these investigations, is made of plastic scintillator bars readout by wavelength shifting fibers and multianode photomultiplier tubes. Data was taken at several locations inside KURF, spanning rock overburden values from ∼ 200 to 1450 m.w.e. From the extracted muon rates an empirical formula was devised, that estimates the muon flux inside the mine as a function of the overburden. The results are in good agreement with muon flux calculations based on analytical models and MUSIC

  20. 14MeV facility and research in IPPE

    Energy Technology Data Exchange (ETDEWEB)

    Simakov, S P; Androsenko, A A; Androsenko, P A; Devkin, B V; Kobozev, M G; Lychagin, A A; Sinitca, V V; Talalaev, V A [Institute of Physics and Power Engineering, Obninsk (Russian Federation); Chuvilin, D Yu; Borisov, A A; Zagryadsky, V A [Institute of Atomic Energy, Moscow (Russian Federation)

    1993-07-01

    Review of experimental facility and research, performed at 14MeV incident neutron energy in the Institute of Physics and Power Engineering, are given. These studies cover the next topics: double differential neutron emission cross sections (DDX), neutron-gamma coincidence experiments (n, n'{gamma}) and neutron leakage spectra for spherical assemblies (benchmark). The paper contains description and main parameters of pulsed neutron generator KG-0.3, fast neutron time of flight spectrometer, measuring and data reduction procedures, review of experimental data. Results of experiments are compared with other data; evaluated data files BROND-2, ENDF/B6, JENDL-3; basic theoretical and transport model calculations. (author)

  1. 14MeV facility and research in IPPE

    International Nuclear Information System (INIS)

    Simakov, S.P.; Androsenko, A.A.; Androsenko, P.A.; Devkin, B.V.; Kobozev, M.G.; Lychagin, A.A.; Sinitca, V.V.; Talalaev, V.A.; Chuvilin, D.Yu.; Borisov, A.A.; Zagryadsky, V.A.

    1993-07-01

    Review of experimental facility and research, performed at 14MeV incident neutron energy in the Institute of Physics and Power Engineering, are given. These studies cover the next topics: double differential neutron emission cross sections (DDX), neutron-gamma coincidence experiments (n, n'γ) and neutron leakage spectra for spherical assemblies (benchmark). The paper contains description and main parameters of pulsed neutron generator KG-0.3, fast neutron time of flight spectrometer, measuring and data reduction procedures, review of experimental data. Results of experiments are compared with other data; evaluated data files BROND-2, ENDF/B6, JENDL-3; basic theoretical and transport model calculations. (author)

  2. Nuclear Security Management for Research Reactors and Related Facilities

    International Nuclear Information System (INIS)

    2016-03-01

    This publication provides a single source guidance to assist those responsible for the implementation of nuclear security measures at research reactors and associated facilities in developing and maintaining an effective and comprehensive programme covering all aspects of nuclear security on the site. It is based on national experience and practices as well as on publications in the field of nuclear management and security. The scope includes security operations, security processes, and security forces and their relationship with the State’s nuclear security regime. The guidance is provided for consideration by States, competent authorities and operators

  3. Research reactor facilities, recent developments at Imperial College, London

    International Nuclear Information System (INIS)

    Franklin, S.J.; Goddard, A.J.H.; O Connell, J.

    1998-01-01

    The 100 kW CONSORT pool-type reactor is now the only Research Reactor in the UK. Because of its strategic importance, Imperial College is continuing and accelerating a programme of refurbishment of the control system, and planning for a further fuel charge. These plans are described and the progress to date discussed. To this end, a description of the enhanced Safety Case being written is provided here and refueling plans discussed. The current range of facilities available is described, and future plans highlighted. (author)

  4. The Sondrestrom Research Facility All-sky Imagers

    Science.gov (United States)

    Kendall, E. A.; Grill, M.; Gudmundsson, E.; Stromme, A.

    2010-12-01

    The Sondrestrom Upper Atmospheric Research Facility is located near Kangerlussuaq, Greenland, just north of the Arctic Circle and 100 km inland from the west coast of Greenland. The facility is operated by SRI International in Menlo Park, California, under the auspices of the U.S. National Science Foundation. Operating in Greenland since 1983, the Sondrestrom facility is host to more than 20 instruments, the majority of which provide unique and complementary information about the arctic upper atmosphere. Together these instruments advance our knowledge of upper atmospheric physics and determine how the tenuous neutral gas interacts with the charged space plasma environment. The suite of instrumentation supports many disciplines of research - from plate tectonics to auroral physics and space weather. The Sondrestrom facility has recently acquired two new all-sky imagers. In this paper, we present images from both new imagers, placing them in context with other instruments at the site and detailing to the community how to gain access to this new data set. The first new camera replaces the intensified auroral system which has been on site for nearly three decades. This new all-sky imager (ASI), designed and assembled by Keo Scientific Ltd., employs a medium format 180° fisheye lens coupled to a set of five 3-inch narrowband interference filters. The current filter suite allows operation at the following wavelengths: 750 nm, 557.7 nm, 777.4 nm, 630.0 nm, and 732/3 nm. Monochromatic images from the ASI are acquired at a specific filter and integration time as determined by a unique configuration file. Integrations as short as 0.5 sec can be commanded for exceptionally bright features. Preview images are posted to the internet in near real-time, with final images posted weeks later. While images are continuously collected in a "patrol mode," users can request special collection sequences for targeted experiments. The second new imager installed at the Sondrestrom

  5. Fusion plasma physics research on the H-1 national facility

    International Nuclear Information System (INIS)

    Harris, J.

    1998-01-01

    Full text: Australia has a highly leveraged fusion plasma research program centred on the H-1 National Facility device at the ANU. H-1 is a heliac, a novel helical axis stellarator that was experimentally pioneered in Australia, but has a close correlation with the worldwide research program on toroidal confinement of fusion grade plasma. Experiments are conducted on H-1 by university researchers from the Australian Fusion Research Group (comprising groups from the ANU, the Universities of Sydney, Western Sydney, Canberra, New England, and Central Queensland University) under the aegis of AINSE; the scientists also collaborate with fusion researchers from Japan and the US. Recent experiments on H-1 have focused on improved confinement modes that can be accessed at very low powers in H-1, but allow the study of fundamental physics effects seen on much larger machines at higher powers. H-1 is now being upgraded in magnetic field and heating power, and will be able to confine hotter plasmas beginning in 1999, offering greatly enhanced research opportunities for Australian plasma scientists and engineers, with substantial spillover of ideas from fusion research into other areas of applied physics and engineering

  6. Interim Control Strategy for the Test Area North/Technical Support Facility Sewage Treatment Facility Disposal Pond - Two-year Update

    International Nuclear Information System (INIS)

    L. V. Street

    2007-01-01

    The Idaho Cleanup Project has prepared this interim control strategy for the U.S. Department of Energy Idaho Operations Office pursuant to DOE Order 5400.5, Chapter 11.3e (1) to support continued discharges to the Test Area North/Technical Support Facility Sewage Treatment Facility Disposal Pond. In compliance with DOE Order 5400.5, a 2-year review of the Interim Control Strategy document has been completed. This submittal documents the required review of the April 2005 Interim Control Strategy. The Idaho Cleanup Project's recommendation is unchanged from the original recommendation. The Interim Control Strategy evaluates three alternatives: (1) re-route the discharge outlet to an uncontaminated area of the TSF-07; (2) construct a new discharge pond; or (3) no action based on justification for continued use. Evaluation of Alternatives 1 and 2 are based on the estimated cost and implementation timeframe weighed against either alternative's minimal increase in protection of workers, the public, and the environment. Evaluation of Alternative 3, continued use of the TSF-07 Disposal Pond under current effluent controls, is based on an analysis of four points: - Record of Decision controls will protect workers and the public - Risk of increased contamination is low - Discharge water will be eliminated in the foreseeable future - Risk of contamination spread is acceptable. The Idaho Cleanup Project recommends Alternative 3, no action other than continued implementation of existing controls and continued deactivation, decontamination, and dismantlement efforts at the Test Area North/Technical Support Facility

  7. Joint Assessment of Renewable Energy and Water Desalination Research Center (REWDC) Program Capabilities and Facilities In Radioactive Waste Management

    International Nuclear Information System (INIS)

    Bissani, M; Fischer, R; Kidd, S; Merrigan, J

    2006-01-01

    The primary goal of this visit was to perform a joint assessment of the Renewable Energy and Water Desalination Center's (REWDC) program in radioactive waste management. The visit represented the fourth technical and scientific interaction with Libya under the DOE/NNSA Sister Laboratory Arrangement. Specific topics addressed during the visit focused on Action Sheet P-05-5, ''Radioactive Waste Management''. The Team, comprised of Mo Bissani (Team Lead), Robert Fischer, Scott Kidd, and Jim Merrigan, consulted with REWDC management and staff. The team collected information, discussed particulars of the technical collaboration and toured the Tajura facility. The tour included the waste treatment facility, waste storage/disposal facility, research reactor facility, hot cells and analytical labs. The assessment team conducted the first phase of Task A for Action Sheet 5, which involved a joint assessment of the Radioactive Waste Management Program. The assessment included review of the facilities dedicated to the management of radioactive waste at the Tourja site, the waste management practices, proposed projects for the facility and potential impacts on waste generation and management

  8. Integrating stakeholders' issues and concerns into Nirex's technical research

    International Nuclear Information System (INIS)

    Atherton, Elisabeth

    2004-01-01

    This note outlines some of the activities that Nirex has undertaken to try and integrate stakeholders' issues and concerns into the technical research we have undertaken and how we are attempting to address their issues. Nirex arranges a range of dialogue activities including workshops, meetings, interviews and focus groups with a wide range of stakeholders. These events are coordinated under what is called the Nirex Involvement Programme. The feedback and inputs we have received at these events have been used to influence the work that we undertake. Nirex's interactions with stakeholders, particularly members of the public and local councillors in the aftermath of losing the 1997 rock characterisation facility public inquiry at Sellafield, has been fundamental to changing our whole approach. We are now trying to understand people's issues and recognising that Nirex is accountable to a wide constituency of stakeholders, but particularly the general public and their elected representatives. It has also enabled Nirex to attempt to integrate people's issues and concerns into its work programmes. Specific examples of where stakeholders' issues have impacted on the technical work Nirex undertakes are outlined. (author)

  9. Importance of Pharmaceutical Training and Clinical Research at Medical Facilities.

    Science.gov (United States)

    Myotoku, Michiaki

    2017-01-01

    To respond to advancements in medical techniques, and to address the separation of medical and dispensary practices, clinical professors are required to educate human resource staff to become highly-skilled pharmacists. For this purpose, it is extremely important for these professors to learn about cutting-edge practical skills and knowledge, as well as to advance their expertise. In addition, they need to conduct clinical research in cooperation with relevant facilities. As our university does not have its own hospital or pharmacy, it is important to provide training for clinical professors in clinical facilities. Such training mainly involves medical teams' in-hospital rounds and participation in conferences (nutrition support team; NST), operation of the pharmacy department, and intervention targeting improvement in the department's duties. We have conducted collaborative studies, provided research instructions, implemented studies aimed at improving the department's work (pharmacists appointed on wards at all times to ensure medical safety) as well as studies regarding team medical care (nutritional evaluation during outpatient chemotherapy), and resolved issues regarding this work (drug solution mixability in a hand-held constant infusion pump, and a safe pump-filling methods). Thus, it has become possible to keep track of the current state of a pharmacists' work within team medical care, to access information about novel drugs, to view clinical and prescription-claim data, to cooperate with other professionals (e.g., doctors and nurses), to promote pharmacists' self-awareness of their roles in cooperative medical practice, and to effectively maintain the hospital's clinical settings.

  10. Brookhaven National Laboratory's Accelerator Test Facility: research highlights and plans

    Science.gov (United States)

    Pogorelsky, I. V.; Ben-Zvi, I.

    2014-08-01

    The Accelerator Test Facility (ATF) at Brookhaven National Laboratory has served as a user facility for accelerator science for over a quarter of a century. In fulfilling this mission, the ATF offers the unique combination of a high-brightness 80 MeV electron beam that is synchronized to a 1 TW picosecond CO2 laser. We unveil herein our plan to considerably expand the ATF's floor space with an upgrade of the electron beam's energy to 300 MeV and the CO2 laser's peak power to 100 TW. This upgrade will propel the ATF even further to the forefront of research on advanced accelerators and radiation sources, supporting the most innovative ideas in this field. We discuss emerging opportunities for scientific breakthroughs, including the following: plasma wakefield acceleration studies in research directions already active at the ATF; laser wakefield acceleration (LWFA), where the longer laser wavelengths are expected to engender a proportional increase in the beam's charge while our linac will assure, for the first time, the opportunity to undertake detailed studies of seeding and staging of the LWFA; proton acceleration to the 100-200 MeV level, which is essential for medical applications; and others.

  11. Quality Assurance of ARM Program Climate Research Facility Data

    Energy Technology Data Exchange (ETDEWEB)

    Peppler, RA; Kehoe, KE; Sonntag, KL; Bahrmann, CP; Richardson, SJ; Christensen, SW; McCord, RA; Doty, DJ; Wagener, Richard [BNL; Eagan, RC; Lijegren, JC; Orr, BW; Sisterson, DL; Halter, TD; Keck, NN; Long, CN; Macduff, MC; Mather, JH; Perez, RC; Voyles, JW; Ivey, MD; Moore, ST; Nitschke, DL; Perkins, BD; Turner, DD

    2008-03-01

    This report documents key aspects of the Atmospheric Radiation Measurement (ARM) Climate Research Facility (ACRF) data quality assurance program as it existed in 2008. The performance of ACRF instruments, sites, and data systems is measured in terms of the availability, usability, and accessibility of the data to a user. First, the data must be available to users; that is, the data must be collected by instrument systems, processed, and delivered to a central repository in a timely manner. Second, the data must be usable; that is, the data must be inspected and deemed of sufficient quality for scientific research purposes, and data users must be able to readily tell where there are known problems in the data. Finally, the data must be accessible; that is, data users must be able to easily find, obtain, and work with the data from the central repository. The processes described in this report include instrument deployment and calibration; instrument and facility maintenance; data collection and processing infrastructure; data stream inspection and assessment; the roles of value-added data processing and field campaigns in specifying data quality and haracterizing the basic measurement; data archival, display, and distribution; data stream reprocessing; and engineering and operations management processes and procedures. Future directions in ACRF data quality assurance also are presented.

  12. Introduction of hot cell facility in research center Rez - Poster

    International Nuclear Information System (INIS)

    Petrickova, A.; Srba, O.; Miklos, M.; Svoboda, P.

    2015-01-01

    This poster presents the hot cell facility which is being constructed as part of the SUSEN project at the Rez research center (Czech Republic). Within this project a new complex of 10 hot cells and one semi-hot cell will be built. There will be 8 gamma hot cells and 2 alpha hot cells. In each hot cell a hermetic, removable box made of stainless steel will home different type of devices. The hot cells and semi hot cell will be equipped with devices for processing samples (cutting, welding, drilling, machining) as well as equipment for testing (sample preparation area, stress testing machine, fatigue machine, electromechanical creep machine, high frequency resonance pulsator...) and equipment for studying material microstructure (nano-indenter with nano-scratch tester and scanning electron microscope). An autoclave with water loop, installed in a cell will allow mechanical testing in control environment of water, pressure and temperature. A scheme shows the equipment of each cell. This hot laboratory will be able to cover all the process to study radioactive materials: receiving the material, the preparation of the samples, mechanical testing and microstructure observation. Our hot cells will be close to the research nuclear reactor LVR-15 and new irradiation facility (high irradiation by cobalt source) is planned to be built within the SUSEN project

  13. Quality Assurance of ARM Program Climate Research Facility Data

    International Nuclear Information System (INIS)

    Peppler, R.A.; Kehoe, K.E.; Sonntag, K.L.; Bahramann, C.P.; Richardson, S.J.; Christensen, S.W.; McCord, R.A.; Doty, D.J.; Wagener, R.; Eagan, R.C.; Lijegren, J.C.; Orr, B.W.; Sisterson, D.L.; Halter, T.D.; Keck, N.N.; Long, C.N.; Macduff, M.C.; Mather, J.H.; Perez, R.C.; Voyles, J.W.; Ivey, M.D.; Moore, S.T.; Nitschke, D.L.; Perkins, B.D.; Turner, D.D.

    2008-01-01

    This report documents key aspects of the Atmospheric Radiation Measurement (ARM) Climate Research Facility (ACRF) data quality assurance program as it existed in 2008. The performance of ACRF instruments, sites, and data systems is measured in terms of the availability, usability, and accessibility of the data to a user. First, the data must be available to users; that is, the data must be collected by instrument systems, processed, and delivered to a central repository in a timely manner. Second, the data must be usable; that is, the data must be inspected and deemed of sufficient quality for scientific research purposes, and data users must be able to readily tell where there are known problems in the data. Finally, the data must be accessible; that is, data users must be able to easily find, obtain, and work with the data from the central repository. The processes described in this report include instrument deployment and calibration; instrument and facility maintenance; data collection and processing infrastructure; data stream inspection and assessment; the roles of value-added data processing and field campaigns in specifying data quality and characterizing the basic measurement; data archival, display, and distribution; data stream reprocessing; and engineering and operations management processes and procedures. Future directions in ACRF data quality assurance also are presented

  14. Magnetic spectrograph for the Holifield heavy ion research facility

    International Nuclear Information System (INIS)

    Ford, J.L.C. Jr.; Enge, H.A.; Erskine, J.R.; Hendrie, D.L.; LeVine, M.J.

    1977-01-01

    The need for a new generation magnetic spectrograph for the Holifield Heavy Ion Research Facility is discussed. The advantages of a magnetic spectrograph for heavy ion research are discussed, as well as some of the types of experiments for which such an instrument is suited. The limitations which the quality of the incident beam, target and spectrograph itself impose on high resolution heavy ion measurements are discussed. Desired features of an ideal new spectrograph are: (1) intrinsic resolving power E/ΔE greater than or equal to 3000; (2) maximum solid angle greater than or equal to 20 msr; (3) dispersion approx. 4-8m; (4) maximum energy interval approx. 30%; and (5) mass-energy product greater than or equal to 200. Various existing and proposed spectrographs are compared with the specifications for a new heavy ion magnet design

  15. H-1NF: Australian national fusion plasma research facility

    International Nuclear Information System (INIS)

    Blackwell, B.D.; Borg, G.G.; Dewar, R.L.; Howard, J.; Gardner, H.J.; Rudakov, D.L.; Sharp, L.E.; Shats, M.G.; Warr, G.B.

    1997-01-01

    The H-1 heliac is a helical axis stellarator of moderate size and novel, flexible configuration. Since commissioning, H-1 has operated in quasi-continuous mode at low magnetic field. For higher fields ≤1T an ECRH heating system (28GHz, 200kW) has been installed under a collaborative agreement between ANU and NIFS. H-1 has recently been promoted to national facility status (H-1NF), which will include upgrades of the rf and ech heating systems to megawatt powers, and power supply and diagnostic and data system enhancements. This facilitates collaborative research locally (through the Australian Fusion Research Group consortium) and internationally. Results of a number of basic experiments in quasi-continuous mode are presented. (author)

  16. High temperature engineering research facilities and experiments in Russia

    International Nuclear Information System (INIS)

    Kodochigov, N.G.; Kuzavkov, N.G.; Sukharev, Y.P.; Chudin, A.G.

    1998-01-01

    An overview is given of the characteristics of the experimental facilities and experiments in the Russian Federation: the HTGR neutron-physical investigation facilities ASTRA and GROG; facilities for fuel, graphite and other elements irradiation; and thermal hydraulics experimental facilities. The overview is presented in the form of copies of overhead sheets

  17. CSU's MWV Observatory: A Facility for Research, Education and Outreach

    Science.gov (United States)

    Hood, John; Carpenter, N. D.; McCarty, C. B.; Samford, J. H.; Johnson, M.; Puckett, A. W.; Williams, R. N.; Cruzen, S. T.

    2014-01-01

    The Mead Westvaco Observatory (MWVO), located in Columbus State University's Coca-Cola Space Science Center, is dedicated to education and research in astronomy through hands-on engagement and public participation. The MWVO has recently received funding to upgrade from a 16-inch Meade LX-200 telescope to a PlaneWave CDK 24-inch Corrected Dall-Kirkham Astrograph telescope. This and other technological upgrades will allow this observatory to stream live webcasts for astronomical events, allowing a worldwide public audience to become a part of the growing astronomical community. This poster will explain the upgrades that are currently in progress as well as the results from the current calibrations. The goal of these upgrades is to provide facilities capable of both research-class projects and widespread use in education and public outreach. We will present our initial calibration and tests of the observatory equipment, as well as its use in webcasts of astronomical events, in solar observing through the use of specialized piggy-backed telescopes, and in research into such topics as asteroids, planetary and nebula imaging. We will describe a pilot research project on asteroid orbit refinement and light curves, to be carried out by Columbus State University students. We will also outline many of the K-12 educational and public outreach activities we have designed for these facilities. Support and funding for the acquisition and installation of the new PlaneWave CDK 24 has been provided by the International Museum and Library Services via the Museums for America Award.

  18. Filling the gaps in SCWR materials research: advanced nuclear corrosion research facilities in Hamilton

    International Nuclear Information System (INIS)

    Krausher, J.L.; Zheng, W.; Li, J.; Guzonas, D.; Botton, G.

    2011-01-01

    Research efforts on materials selection and development in support of the design of supercritical water-cooled reactors (SCWRs) have produced a considerable amount of data on corrosion, creep and other related properties. Summaries of the data on corrosion [1] and stress corrosion cracking [2] have recently been produced. As research on the SCWR advances, gaps and limitations in the published data are being identified. In terms of corrosion properties, these gaps can be seen in several areas, including: 1) the test environment, 2) the physical and chemical severity of the tests conducted as compared with likely reactor service/operating conditions, and 3) the test methods used. While some of these gaps can be filled readily using existing facilities, others require the availability of advanced test facilities for specific tests and assessments. In this paper, highlights of the new materials research facilities jointly established in Hamilton by CANMET Materials Technology Laboratory and McMaster University are presented. (author)

  19. Survey of radioactive effluent releases from byproduct material facilities. Technical report

    International Nuclear Information System (INIS)

    Cook, J.R.

    1981-08-01

    A survey of over 3,000 NRC byproduct material licensees was conducted in late 1980 to collect data on annual effluent releases of radioactivity. The survey was conducted through a questionnaire, which was sent to NRC licensees who handle radioactive material in unsealed form, i.e., research, medical, and industrial institutions. Principal findings from the survey analysis are as follows: More than 98% of the reported annual releases to air (484 to 490) yield calculated average concentrations at the boundary of the unrestricted area that were at 1% or less than the maximum permissible concentration (MPC) of Appendix B, Table II, Column 1 of 10 CFR 20. The largest reported annual release was estimated to yield a concentration that was approximately 12% of MPC, the 5 other releases ranged from 1 to 10% of MPC. All reported annual releases of liquid waste were within the limits specified by NRC with most facilities reporting annual releases of only a fraction of a curie. Based on the data provided by licensees and analyzed in this report, it appears that in general the environmental impacts from research, medical and industrial institutions and organizations licensed by the NRC to possess and use byproduct materials are minimal and correspond to a small fraction of that from natural background

  20. Expanding and Redirecting Historical Research in Technical Writing: In Search of Our Past.

    Science.gov (United States)

    Tebeaux, Elizabeth; Killingsworth, M. Jimmie

    1992-01-01

    Suggests an approach for expanding and integrating research to produce a history of technical writing. Defines problems that reside in writing such a history, suggests research premises and questions, and then applies these questions to technical writing as it existed in the English Renaissance, 1475-1640. (SR)