WorldWideScience

Sample records for facilities preliminary results

  1. Preliminary results from direct-to-facility vaccine deliveries in Kano, Nigeria.

    Science.gov (United States)

    Aina, Muyi; Igbokwe, Uchenna; Jegede, Leke; Fagge, Rabiu; Thompson, Adam; Mahmoud, Nasir

    2017-04-19

    As part of its vaccine supply chain redesign efforts, Kano state now pushes vaccines directly from 6 state stores to primary health centers equipped with solar refrigerators. Our objective is to describe preliminary results from the first 20months of Kano's direct vaccine delivery operations. This is a retrospective review of Kano's direct vaccine delivery program. We analyzed trends in health facility vaccine stock levels, and examined the relationship between stock-out rates and each of cascade vaccine deliveries and timeliness of deliveries. Analysis of vaccination trends was based on administrative data from 27 sentinel health facilities. Costs for both the in-sourced and out-sourced approaches were estimated using a bottoms-up model-based approach. Overall stock adequacy increased from 54% in the first delivery cycle to 68% by cycle 33. Conversely, stock-out rates decreased from 41% to 10% over the same period. Similar trends were observed in the out-sourced and in-sourced programs. Stock-out rates rose incrementally with increasing number of cascade facilities, and delays in vaccine deliveries correlated strongly with stock-out rates. Recognizing that stock availability is one of many factors contributing to vaccinations, we nonetheless compared pre- and post- direct deliveries vaccinations in sentinel facilities, and found statistically significant upward trends for 4 out of 6 antigens. 1 antigen (measles) showed an upward trend that was not statistically significant. Hepatitis b vaccinations declined during the period. Overall, there appeared to be a one-year lag between commencement of direct deliveries and the increase in number of vaccinations. Weighted average cost per delivery is US$29.8 and cost per child immunized is US$0.7 per year. Direct vaccine delivery to health facilities in Kano, through a streamlined architecture, has resulted in decreased stock-outs and improved stock adequacy. Concurrent operation of insourced and outsourced programs has

  2. Exploratory shaft facility preliminary designs - Permian Basin

    International Nuclear Information System (INIS)

    1983-09-01

    The purpose of the Preliminary Design Report, Permian Basin, is to provide a description of the preliminary design for an Exploratory Shaft Facility in the Permian Basin, Texas. 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 are included in the Appendix. The report is divided into three principal sections: Design Basis, Facility Description, and Construction Cost Estimate. 30 references, 13 tables

  3. The large-scale vented combustion test facility at AECL-WL: description and preliminary test results

    International Nuclear Information System (INIS)

    Loesel Sitar, J.; Koroll, G.W.; Dewit, W.A.; Bowles, E.M.; Harding, J.; Sabanski, C.L.; Kumar, R.K.

    1997-01-01

    Implementation of hydrogen mitigation systems in nuclear reactor containments requires testing the effectiveness of the mitigation system, reliability and availability of the hardware, potential consequences of its use and the technical basis for hardware placement, on a meaningful scale. Similarly, the development and validation of containment codes used in nuclear reactor safety analysis require detailed combustion data from medium- and large-scale facilities. A Large-Scale Combustion Test Facility measuring 10 m x 4 m x 3 m (volume, 120 m 3 ) has been constructed and commissioned at Whiteshell Laboratories to perform a wide variety of combustion experiments. The facility is designed to be versatile so that many geometrical configurations can be achieved. The facility incorporates extensive capabilities for instrumentation and high speed data acquisition, on-line gas sampling and analysis. Other features of the facility include operation at elevated temperatures up to 150 degrees C, easy access to the interior, and remote operation. Initial thermodynamic conditions in the facility can be controlled to within 0.1 vol% of constituent gases. The first series of experiments examined vented combustion in the full 120 m 3 -volume configuration with vent areas in the range of 0.56 to 2.24 m 2 . The experiments were performed at ∼27 degrees C and near-atmospheric pressures, with hydrogen concentrations in the range of 8 to 12% by volume. This paper describes the Large-Scale Vented Combustion Test Facility and preliminary results from the first series of experiments. (author)

  4. 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

  5. Preliminary design for hot dirty-gas control-valve test facility. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    This report presents the results of a preliminary design and cost estimating effort for a facility for the testing of control valves in Hot Dirty Gas (HDGCV) service. This design was performed by Mittelhauser Corporation for the United States Department of Energy's Morgantown Energy Technology Center (METC). The objective of this effort was to provide METC with a feasible preliminary design for a test facility which could be used to evaluate valve designs under simulated service conditions and provide a technology data base for DOE and industry. In addition to the actual preliminary design of the test facility, final design/construction/operating schedules and a facility cost estimate were prepared to provide METC sufficient information with which to evaluate this design. The bases, assumptions, and limitations of this study effort are given. The tasks carried out were as follows: METC Facility Review, Environmental Control Study, Gas Generation Study, Metallurgy Review, Safety Review, Facility Process Design, Facility Conceptual Layout, Instrumentation Design, Cost Estimates, and Schedules. The report provides information regarding the methods of approach used in the various tasks involved in the completion of this study. Section 5.0 of this report presents the results of the study effort. The results obtained from the above-defined tasks are described briefly. The turnkey cost of the test facility is estimated to be $9,774,700 in fourth quarter 1979 dollars, and the annual operating cost is estimated to be $960,000 plus utilities costs which are not included because unit costs per utility were not available from METC.

  6. Preliminary safety assessment of the WIPP facility

    International Nuclear Information System (INIS)

    Balestri, R.J.; Torres, B.W.; Pahwa, S.B.; Brannen, J.P.

    1979-01-01

    This paper summarizes the efforts to perform a safety assessment of the Waste Isolation Pilot Plant (WIPP) facility being proposed for southeastern New Mexico. This preliminary safety assessment is limited to a consequence assessment in terms of the dose to a maximally exposed individual as a result of introducing the radionuclides into the biosphere. The extremely low doses to the organs as a result of the liquid breach scenarios are contrasted with the background radiation

  7. Preliminary results of the International Fusion Materials Irradiation Facility deuteron injector

    Energy Technology Data Exchange (ETDEWEB)

    Gobin, R.; Adroit, G.; Bogard, D.; Bourdelle, G.; Chauvin, N.; Delferriere, O.; Gauthier, Y.; Girardot, P.; Guiho, P.; Harrault, F.; Jannin, J. L.; Loiseau, D.; Mattei, P.; Roger, A.; Sauce, Y.; Senee, F.; Vacher, T. [Commissariat a l' Energie Atomique et aux Energie Alternatives, CEA/Saclay, DSM/IRFU, 91191-Gif/Yvette (France)

    2012-02-15

    In the framework of the IFMIF-EVEDA project (International Fusion Materials Irradiation Facility-Engineering Validation and Engineering Design Activities), CEA/IRFU is in charge of the design, construction, and characterization of the 140 mA continuous deuteron injector, including the source and the low energy beam line. The electron cyclotron resonance ion source which operates at 2.45 GHz is associated with a 4-electrode extraction system in order to minimize beam divergence at the source exit. Krypton gas injection is foreseen in the 2-solenoid low energy beam line. Such Kr injection will allow reaching a high level of space charge compensation in order to improve the beam matching at the radio frequency quadrupole (RFQ) entrance. The injector construction is now completed on the Saclay site and the first plasma and beam production has been produced in May 2011. This installation will be tested with proton and deuteron beams either in pulsed or continuous mode at Saclay before shipping to Japan. In this paper, after a brief description of the installation, the preliminary results obtained with hydrogen gas injection into the plasma chamber will be reported.

  8. Exploratory shaft facility preliminary designs - Gulf Interior Region salt domes

    International Nuclear Information System (INIS)

    1983-09-01

    The purpose of the Preliminary Design Report, Gulf Interior Region, is to provide a description of the preliminary design for an Exploratory Shaft Facility on the Richton Dome, Mississippi. 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 are included in the Appendix. The report is divided into three principal sections: Design Basis, Facility Description and Construction Cost Estimate

  9. Preliminary conceptual study of engineering-scale pyroprocess demonstration facility

    International Nuclear Information System (INIS)

    Moon, Seong-In; Chong, Won-Myung; You, Gil-Sung; Ku, Jeong-Hoe; Kim, Ho-Dong

    2013-01-01

    Highlights: ► The conceptual design of a pyroprocess demonstration facility was performed. ► The design requirements for the pyroprocess hot cell and equipment were determined. ► The maintenance concept for the pyroprocess hot cell was presented. -- Abstract: The development of an effective management technology of spent fuel is important to enhance environmental friendliness, cost viability and proliferation resistance. In Korea, pyroprocess technology has been considered as a fuel cycle option to solve the spent fuel accumulation problems. PRIDE (PyRoprocess Integrated inactive DEmonstration facility) has been developed from 2007 to 2012 in Korea as a cold test facility to support integrated pyroprocessing and an equipment demonstration, which is essential to verify the pyroprocess technology. As the next stage of PRIDE, the design requirements of an engineering-scale demonstration facility are being developed, and the preliminary conceptual design of the facility is being performed for the future. In this paper, the main design requirements for the engineering-scale pyroprocess demonstration facility were studied in the throughput of 10tHM a year. For the preliminary conceptual design of the facility, the design basis of the pyroprocess hot cell was suggested, and the main equipment, main process area, operation area, maintenance area, and so on were arranged in consideration of the effective operation of the hot cells. Also, the argon system was designed to provide and maintain a proper inert environment for the pyroprocess. The preliminary conceptual design data will be used to review the validity of the engineering-scale pyroprocess demonstration facility that enhances both safety and nonproliferation

  10. Preliminary Cluster Size and Efficiencies results of CMS RPC at GIF++

    CERN Document Server

    Gonzalez Blanco Gonzalez, Genoveva

    2016-01-01

    A brief description and first preliminary results of the Efficiencies and Cluster Size measurements of the CMS Resistive Plate Chambers, will be presented inside the Gamma Irradiation Facility GIF++ at CERN. Preliminary studies that sets the base performance measurements of CMS RPC for starting aging studies.

  11. Preliminary design for a maglev development facility

    Energy Technology Data Exchange (ETDEWEB)

    Coffey, H.T.; He, J.L.; Chang, S.L.; Bouillard, J.X.; Chen, S.S.; Cai, Y.; Hoppie, L.O.; Lottes, S.A.; Rote, D.M. (Argonne National Lab., IL (United States)); Zhang, Z.Y. (Polytechnic Univ., Brooklyn, NY (United States)); Myers, G.; Cvercko, A. (Sterling Engineering, Westchester, IL (United States)); Williams, J.R. (Alfred Benesch and Co., Chicago, IL (United States))

    1992-04-01

    A preliminary design was made of a national user facility for evaluating magnetic-levitation (maglev) technologies in sizes intermediate between laboratory experiments and full-scale systems. A technical advisory committee was established and a conference was held to obtain advice on the potential requirements of operational systems and how the facility might best be configured to test these requirements. The effort included studies of multiple concepts for levitating, guiding, and propelling maglev vehicles, as well as the controls, communications, and data-acquisition and -reduction equipment that would be required in operating the facility. Preliminary designs for versatile, dual 2-MVA power supplies capable of powering attractive or repulsive systems were developed. Facility site requirements were identified. Test vehicles would be about 7.4 m (25 ft) long, would weigh form 3 to 7 metric tons, and would operate at speeds up to 67 m/s (150 mph) on a 3.3-km (2.05-mi) elevated guideway. The facility would utilize modular vehicles and guideways, permitting the substitution of levitation, propulsion, and guideway components of different designs and materials for evaluation. The vehicle would provide a test cell in which individual suspension or propulsion components or subsystems could be tested under realistic conditions. The system would allow economical evaluation of integrated systems under varying weather conditions and in realistic geometries.

  12. Preliminary site requirements and considerations for a monitored retrievable storage facility

    International Nuclear Information System (INIS)

    1991-08-01

    This report presents preliminary requirements and considerations for siting monitored retrievable storage (MRS) facility. It purpose is to provide guidance for assessing the technical suitability of potential sites for the facility. It has been reviewed by the NRC staff, which stated that this document is suitable for ''guidance in making preliminary determinations concerning MRS site suitability.'' The MRS facility will be licensed by the US Nuclear Regulatory Commission. It will receive spent fuel from commercial nuclear power plants and provide a limited amount of storage for this spent fuel. When a geologic repository starts operations, the MRS facility will also stage spent-fuel shipments to the repository. By law, storage at the MRS facility is to be temporary, with permanent disposal provided in a geologic repository to be developed by the DOE

  13. Preliminary assessments the shortcut to remediation (category III-surplus facility assessments)

    International Nuclear Information System (INIS)

    Byars, L.L.

    1995-01-01

    This report presents the details of the preliminary assessments for the shortcut of decontamination of surplus nuclear facilities. Topics discussed include: environment, health and safety concerns; economic considerations; reduction of transition time; preliminary characterization reports; preliminary project plan; health and safety plan; quality assurance plan; surveillance and maintenance plan; and waste management plan

  14. Ultraviolet Free Electron Laser Facility preliminary design report

    Energy Technology Data Exchange (ETDEWEB)

    Ben-Zvi, I. (ed.)

    1993-02-01

    This document, the Preliminary Design Report (PDR) for the Brookhaven Ultraviolet Free Electron Laser (UV FEL) facility, describes all the elements of a facility proposed to meet the needs of a research community which requires ultraviolet sources not currently available as laboratory based lasers. Further, for these experiments, the requisite properties are not extant in either the existing second or upcoming third generation synchrotron light sources. This document is the result of our effort at BNL to identify potential users, determine the requirements of their experiments, and to design a facility which can not only satisfy the existing need, but have adequate flexibility for possible future extensions as need dictates and as evolving technology allows. The PDR is comprised of three volumes. In this, the first volume, background for the development of the proposal is given, including descriptions of the UV FEL facility, and representative examples of the science it was designed to perform. Discussion of the limitations and potential directions for growth are also included. A detailed description of the facility design is then provided, which addresses the accelerator, optical, and experimental systems. Information regarding the conventional construction for the facility is contained in an addendum to volume one (IA).

  15. Ultraviolet Free Electron Laser Facility preliminary design report

    International Nuclear Information System (INIS)

    Ben-Zvi, I.

    1993-02-01

    This document, the Preliminary Design Report (PDR) for the Brookhaven Ultraviolet Free Electron Laser (UV FEL) facility, describes all the elements of a facility proposed to meet the needs of a research community which requires ultraviolet sources not currently available as laboratory based lasers. Further, for these experiments, the requisite properties are not extant in either the existing second or upcoming third generation synchrotron light sources. This document is the result of our effort at BNL to identify potential users, determine the requirements of their experiments, and to design a facility which can not only satisfy the existing need, but have adequate flexibility for possible future extensions as need dictates and as evolving technology allows. The PDR is comprised of three volumes. In this, the first volume, background for the development of the proposal is given, including descriptions of the UV FEL facility, and representative examples of the science it was designed to perform. Discussion of the limitations and potential directions for growth are also included. A detailed description of the facility design is then provided, which addresses the accelerator, optical, and experimental systems. Information regarding the conventional construction for the facility is contained in an addendum to volume one (IA)

  16. The Mixed Waste Management Facility. Preliminary design review

    International Nuclear Information System (INIS)

    1995-01-01

    This document presents information about the Mixed Waste Management Facility. Topics discussed include: cost and schedule baseline for the completion of the project; evaluation of alternative options; transportation of radioactive wastes to the facility; capital risk associated with incineration; radioactive waste processing; scaling of the pilot-scale system; waste streams to be processed; molten salt oxidation; feed preparation; initial operation to demonstrate selected technologies; floorplans; baseline revisions; preliminary design baseline; cost reduction; and project mission and milestones

  17. Light ion production for a future radiobiological facility at CERN: preliminary studies.

    Science.gov (United States)

    Stafford-Haworth, Joshua; Bellodi, Giulia; Küchler, Detlef; Lombardi, Alessandra; Röhrich, Jörg; Scrivens, Richard

    2014-02-01

    Recent medical applications of ions such as carbon and helium have proved extremely effective for the treatment of human patients. However, before now a comprehensive study of the effects of different light ions on organic targets has not been completed. There is a strong desire for a dedicated facility which can produce ions in the range of protons to neon in order to perform this study. This paper will present the proposal and preliminary investigations into the production of light ions, and the development of a radiobiological research facility at CERN. The aims of this project will be presented along with the modifications required to the existing linear accelerator (Linac3), and the foreseen facility, including the requirements for an ion source in terms of some of the specification parameters and the flexibility of operation for different ion types. Preliminary results from beam transport simulations will be presented, in addition to some planned tests required to produce some of the required light ions (lithium, boron) to be conducted in collaboration with the Helmholtz-Zentrum für Materialien und Energie, Berlin.

  18. Environmental Survey preliminary report, Pantex Facility, Amarillo, Texas

    International Nuclear Information System (INIS)

    1987-09-01

    This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Pantex Facility, conducted November 3 through 14, 1986.The Survey is being conducted by an interdisciplinary team of environmental specialist, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team components are outside experts being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the Pantex Facility. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at the Pantex Facility, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The Sampling and Analysis Plan will be executed by the Oak Ridge National Laboratory. When completed, the results will be incorporated into the Pantex Facility Environmental Survey Interim Report. The Interim Report will reflect the final determinations of the Survey for the Pantex Facility. 65 refs., 44 figs., 27 tabs

  19. Environmental Survey preliminary report, Pantex Facility, Amarillo, Texas

    Energy Technology Data Exchange (ETDEWEB)

    1987-09-01

    This report presents the preliminary findings from the first phase of the Environmental Survey of the United States Department of Energy (DOE) Pantex Facility, conducted November 3 through 14, 1986.The Survey is being conducted by an interdisciplinary team of environmental specialist, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. Individual team components are outside experts being supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the Pantex Facility. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations carried on at the Pantex Facility, and interviews with site personnel. The Survey team developed a Sampling and Analysis Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The Sampling and Analysis Plan will be executed by the Oak Ridge National Laboratory. When completed, the results will be incorporated into the Pantex Facility Environmental Survey Interim Report. The Interim Report will reflect the final determinations of the Survey for the Pantex Facility. 65 refs., 44 figs., 27 tabs.

  20. Preliminary exploitation of industrial facility for flue gas treatment

    International Nuclear Information System (INIS)

    Chmielewski, A.G.; Zimek, Z.; Iller, E.; Tyminski, B.; Licki, J.

    2001-01-01

    laboratory and pilot installation in Poland has lead to decision concerning design and construction of the industrial demonstration plant for electron beam flue gas treatment. Industrial demonstration facility for electron beam flue gas treatment was designed and installed in EPS Pomorzany in Szczecin. This flue gas purification installation treats exhaust gases coming from a block which consists of two Benson type boilers of power 56 MWe each, supplying additional steam for heating purposes up to 40 MWth each. The 270,000 Nm 3 /h flue gases (half of produced by the blocks) is treated meet Polish regulations which are imposed since 1997. Four electron accelerators has been constructed by Nissin High Voltage, Kyoto, Japan to provide 1200 kW of total beam power with electron energy 0,8 MeV to be installed in EPS Pomorzany. Two-stage irradiation was applied as it was tested at the pilot plant. The industrial installation located at EPS Pomorzany consist of two independent reaction chambers, humidification tower with water and steam supply systems, ammonia water handling system with ammonia injection, electrostatic precipitator, by product handling system, measuring and control systems. Solid particles which are formed as salts are separated in ESP and byproduct pretreated in handling system with amount up to 700 kg/h. All systems including accelerators were tested separately to meet EPS regulations (72 h continues run) and confirm producer warranted parameters and facility design specification. Some necessary modifications including accelerators were introduced by equipment producers depends on obtained results of performed measurements. The quality of shielding properties of accelerator chamber walls was tested according to national regulation and the license on accelerator exploitation and personnel qualification were issued by polish authorities. The spatial dose distribution and dose rate measurement were carried on with electron energy 700 and 800 keV. Preliminary results

  1. Results of the Preliminary Test in the 1/4-Scale RCCS of the PMR200 VHTR

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jong-Hwan; Bae, Yoon-Yeong; Hong, Sung-Deok; Kim, Chan-Soo; Cho, Bong-Hyun; Kim, Min-Hwan [Nuclear Hydrogen Reactor Technology Development Dep., Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    The Reactor Cavity Cooling System (RCCS) is a key ex-vessel passive safety system that will ensure the safety of the PMR200, and its performance needs to be verified. For the difficulty of the full-scale test, a 1/4-scale RCCS facility, NACEF (Natural Cooling Experimental Facility), has been constructed at KAERI, and a shakedown test has been performed. A brief design and the preliminary test results of this facility are described. A 1/4-scale RCCS mockup of PMR200, NACEF, was constructed and tested preliminarily. The functioning of the facility worked quite well. Moreover, the preliminary test results show a fairly good agreement with past work except for the conductive heat transfer region in the riser bottom. After a remedy such as the installation of more precise flow meters and a more improved insulation, the test facility is likely to work well.

  2. Preliminary Langmuir probe results on the CTX gun experiment

    International Nuclear Information System (INIS)

    Tuszewski, M.

    1981-12-01

    Preliminary results obtained with a double Langmuir probe in the Compact Toroid experiment facility confirm the existence of a gun plasma of n approx. 5 x 10 14 cm -3 and T approx. 10 eV lasting for approx. 250 to 400 μs, which is consistent with interferometry and Thomson scattering data. The probe current characteristics as a function of voltage suggest non-Maxwellian features of the particles distribution functions

  3. Preliminary safety evaluation (PSE) for Sodium Storage Facility at the Fast Flux Test Facility

    International Nuclear Information System (INIS)

    Bowman, B.R.

    1994-01-01

    This evaluation was performed for the Sodium Storage Facility (SSF) which will be constructed at the Fast Flux Test Facility (FFTF) in the area adjacent to the South and West Dump Heat Exchanger (DHX) pits. The purpose of the facility is to allow unloading the sodium from the FFTF plant tanks and piping. The significant conclusion of this Preliminary Safety Evaluation (PSE) is that the only Safety Class 2 components are the four sodium storage tanks and their foundations. The building, because of its imminent risk to the tanks under an earthquake or high winds, will be Safety Class 3/2, which means the building has a Safety Class 3 function with the Safety Class 2 loads of seismic and wind factored into the design

  4. Evaporative removal of sodium: interim progress report and preliminary facility specification

    International Nuclear Information System (INIS)

    Welch, F.H.

    1978-01-01

    A summary of the current Evaporative Removal of Sodium (ERNA) activities at the Energy Systems Group is presented. Also included is a review of earlier work on sodium evaporation. As a result of this work it was concluded that the ERNA process was extremely successful and worthy of future consideration as a recognized process for reactor components. Also included in the report is a Preliminary Outline Specification for a large facility to remove sodium from full size CRBR fuel rod assemblies

  5. LASL experimental engineered waste burial facility: design considerations and preliminary plan

    International Nuclear Information System (INIS)

    DePoorter, G.L.

    1980-01-01

    The LASL Experimental Engineered Waste Burial Facility is a part of the National Low-Level Waste Management Program on Shallow-Land Burial Technology. It is a test facility where basic information can be obtained on the processes that occur in shallow-land burial operations and where new concepts for shallow-land burial can be tested on an accelerated basis on an appropriate scale. The purpose of this paper is to present some of the factors considered in the design of the facility and to present a preliminary description of the experiments that are initially planned. This will be done by discussing waste management philosophies, the purposes of the facility in the context of the waste management philosophy for the facility, and the design considerations, and by describing the experiments initially planned for inclusion in the facility, and the facility site

  6. Preliminary seismic design cost-benefit assessment of the tuff repository waste-handling facilities

    International Nuclear Information System (INIS)

    Subramanian, C.V.; Abrahamson, N.; Hadjian, A.H.

    1989-02-01

    This report presents a preliminary assessment of the costs and benefits associated with changes in the seismic design basis of waste-handling facilities. The objectives of the study are to understand the capability of the current seismic design of the waste-handling facilities to mitigate seismic hazards, evaluate how different design levels and design measures might be used toward mitigating seismic hazards, assess the costs and benefits of alternative seismic design levels, and develop recommendations for possible modifications to the seismic design basis. This preliminary assessment is based primarily on expert judgment solicited in an interdisciplinary workshop environment. The estimated costs for individual attributes and the assumptions underlying these cost estimates (seismic hazard levels, fragilities, radioactive-release scenarios, etc.) are subject to large uncertainties, which are generally identified but not treated explicitly in this preliminary analysis. The major conclusions of the report do not appear to be very sensitive to these uncertainties. 41 refs., 51 figs., 35 tabs

  7. PHOEBUS/UHTREX: a preliminary study of a low-cost facility for transient tests of LMFBR fuel

    International Nuclear Information System (INIS)

    Kirk, W.L.

    1976-08-01

    The results of a brief preliminary design study of a facility for transient nuclear tests of fast breeder reactor fuel are described. The study is based on the use of a reactor building originally built for the UHTREX reactor, and the use of some reactor hardware and reactor design and fabrication technology remaining from the Phoebus-2 reactor of the Rover nulcear rocket propulsion program. The facility is therefore currently identified as the PHOEBUS/UHTREX facility. This facility is believed capable of providing early information regarding fast reactor core accident energetics issues which will be very valuable to the overall LMFBR safety program. Facility performance in conjunction with a reference 127-fuel pin experiment is described. Low cost and early availability of the facility were emphasized in the selection of design features and parameters

  8. PHOEBUS/UHTREX: a preliminary study of a low-cost facility for transient tests of LMFBR fuel

    Energy Technology Data Exchange (ETDEWEB)

    Kirk, W.L. (comp.)

    1976-08-01

    The results of a brief preliminary design study of a facility for transient nuclear tests of fast breeder reactor fuel are described. The study is based on the use of a reactor building originally built for the UHTREX reactor, and the use of some reactor hardware and reactor design and fabrication technology remaining from the Phoebus-2 reactor of the Rover nulcear rocket propulsion program. The facility is therefore currently identified as the PHOEBUS/UHTREX facility. This facility is believed capable of providing early information regarding fast reactor core accident energetics issues which will be very valuable to the overall LMFBR safety program. Facility performance in conjunction with a reference 127-fuel pin experiment is described. Low cost and early availability of the facility were emphasized in the selection of design features and parameters.

  9. Preliminary assessment report for Kent National Guard Facility (Installation 53065), 24410 Military Road, Kent, Washington

    International Nuclear Information System (INIS)

    Ketels, P.; Aggarwal, P.; Rose, C.M.

    1993-08-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Washington Army National Guard property in Kent, Washington. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining site activities, quantities of hazardous substances present, and potential pathways by which contamination could affect public health and the environment

  10. Remote sensing using hydroacoustics preliminary results

    International Nuclear Information System (INIS)

    Hunt, G.; Patrick, P.H.; Sim, B.

    1989-01-01

    A laboratory investigation was conducted to determine the capability and accuracy of a dual beam sonar system in classifying various targets. The ability to classify fish and/or distinguish fish from debris is essential if hydroacoustics are ever to be used truly remotely for hydroelectric power plant fish passage facilities. Preliminary results indicated that considerable filtering was occurring in the sonar sounder which limited its use in target classification. A wideband sonar detection module was developed which allowed for a more detailed reflected signal which probably will be necessary for fish identification. Another advantage that this modification appears to have over the existing system is an improved spatial resolution of targets, which can be significant if biomass estimates are based on echo counting techniques rather than echo integration ones. Based on the results, it may be possible to filter out or remove the influence of air bubbles in echo returns. As a result echo counts could more accurately be defined as fish counts. Target strengths of sturgeon were estimated using both the modified and original sounder. 12 refs., 11 figs., 2 tabs

  11. Preliminary test results for post irradiation examination on the HTTR fuel

    International Nuclear Information System (INIS)

    Ueta, Shohei; Umeda, Masayuki; Sawa, Kazuhiro; Sozawa, Shizuo; Shimizu, Michio; Ishigaki, Yoshinobu; Obata, Hiroyuki

    2007-01-01

    The future post-irradiation program for the first-loading fuel of the HTTR is scheduled using the HTTR fuel handling facilities and the Hot Laboratory in the Japan Materials Testing Reactor (JMTR) to confirm its irradiation resistance and to obtain data on its irradiation characteristics in the core. This report describes the preliminary test results and the future plan for a post-irradiation examination for the HTTR fuel. In the preliminary test, fuel compacts made with the same SiC-coated fuel particle as the first loading fuel were used. In the preliminary test, dimension, weight, fuel failure fraction, and burnup were measured, and X-ray radiograph, SEM, and EPMA observations were carried out. Finally, it was confirmed that the first-loading fuel of the HTTR showed good quality under an irradiation condition. The future plan for the post-irradiation tests was described to confirm its irradiation performance and to obtain data on its irradiation characteristics in the HTTR core. (author)

  12. Preliminary Shielding Assessment for the IFF System in the RAON Heavy-ion Facility

    International Nuclear Information System (INIS)

    Lee, Cheol Woo; Lee, Youngouk; Kim, Jong Won; Kim, Mijung

    2014-01-01

    A heavy-ion accelerator facility is under a development in Korea to use in the basic science research and various application areas. In this facility, the In-Flight Fragment (IFF) target and isotope separator has been designed to produce various isotopes and transport the interesting isotopes into the experimental rooms. In this work, preliminary radiation shielding assessment was performed for the IFF target room

  13. Verification of fire and explosion accident analysis codes (facility design and preliminary results)

    International Nuclear Information System (INIS)

    Gregory, W.S.; Nichols, B.D.; Talbott, D.V.; Smith, P.R.; Fenton, D.L.

    1985-01-01

    For several years, the US Nuclear Regulatory Commission has sponsored the development of methods for improving capabilities to analyze the effects of postulated accidents in nuclear facilities; the accidents of interest are those that could occur during nuclear materials handling. At the Los Alamos National Laboratory, this program has resulted in three computer codes: FIRAC, EXPAC, and TORAC. These codes are designed to predict the effects of fires, explosions, and tornadoes in nuclear facilities. Particular emphasis is placed on the movement of airborne radioactive material through the gaseous effluent treatment system of a nuclear installation. The design, construction, and calibration of an experimental ventilation system to verify the fire and explosion accident analysis codes are described. The facility features a large industrial heater and several aerosol smoke generators that are used to simulate fires. Both injected thermal energy and aerosol mass can be controlled using this equipment. Explosions are simulated with H 2 /O 2 balloons and small explosive charges. Experimental measurements of temperature, energy, aerosol release rates, smoke concentration, and mass accumulation on HEPA filters can be made. Volumetric flow rate and differential pressures also are monitored. The initial experiments involve varying parameters such as thermal and aerosol rate and ventilation flow rate. FIRAC prediction results are presented. 10 figs

  14. 78 FR 63176 - Notice of Preliminary Determination of a Qualifying Conduit Hydropower Facility and Soliciting...

    Science.gov (United States)

    2013-10-23

    ... Preliminary Determination of a Qualifying Conduit Hydropower Facility and Soliciting Comments and Motions To... of intent to construct a qualifying conduit hydropower facility, pursuant to section 30 of the Federal Power Act, as amended by section 4 of the Hydropower Regulatory Efficiency Act of 2013 (HREA). The...

  15. Preliminary study for small animal preclinical hadrontherapy facility

    Energy Technology Data Exchange (ETDEWEB)

    Russo, G. [Institute of Molecular Bioimaging and Physiology, IBFM CNR-LATO, Cefalú (Italy); Pisciotta, P., E-mail: pietro.pisciotta@ibfm.cnr.it [Institute of Molecular Bioimaging and Physiology, IBFM CNR-LATO, Cefalú (Italy); National Institute for Nuclear Physics, Laboratori Nazionali del Sud, INFN-LNS, Catania (Italy); Cirrone, G.A.P.; Romano, F. [National Institute for Nuclear Physics, Laboratori Nazionali del Sud, INFN-LNS, Catania (Italy); Cammarata, F.; Marchese, V.; Forte, G.I.; Lamia, D.; Minafra, L.; Bravatá, V. [Institute of Molecular Bioimaging and Physiology, IBFM CNR-LATO, Cefalú (Italy); Acquaviva, R. [University of Catania, Catania (Italy); Gilardi, M.C. [Institute of Molecular Bioimaging and Physiology, IBFM CNR-LATO, Cefalú (Italy); Cuttone, G. [National Institute for Nuclear Physics, Laboratori Nazionali del Sud, INFN-LNS, Catania (Italy)

    2017-02-21

    Aim of this work is the study of the preliminary steps to perform a particle treatment of cancer cells inoculated in small animals and to realize a preclinical hadrontherapy facility. A well-defined dosimetric protocol was developed to explicate the steps needed in order to perform a precise proton irradiation in small animals and achieve a highly conformal dose into the target. A precise homemade positioning and holding system for small animals was designed and developed at INFN-LNS in Catania (Italy), where an accurate Monte Carlo simulation was developed, using Geant4 code to simulate the treatment in order to choose the best animal position and perform accurately all the necessary dosimetric evaluations. The Geant4 application can also be used to realize dosimetric studies and its peculiarity consists in the possibility to introduce the real target composition in the simulation using the DICOM micro-CT image. This application was fully validated comparing the results with the experimental measurements. The latter ones were performed at the CATANA (Centro di AdroTerapia e Applicazioni Nucleari Avanzate) facility at INFN-LNS by irradiating both PMMA and water solid phantom. Dosimetric measurements were performed using previously calibrated EBT3 Gafchromic films as a detector and the results were compared with the Geant4 simulation ones. In particular, two different types of dosimetric studies were performed: the first one involved irradiation of a phantom made up of water solid slabs where a layer of EBT3 was alternated with two different slabs in a sandwich configuration, in order to validate the dosimetric distribution. The second one involved irradiation of a PMMA phantom made up of a half hemisphere and some PMMA slabs in order to simulate a subcutaneous tumour configuration, normally used in preclinical studies. In order to evaluate the accordance between experimental and simulation results, two different statistical tests were made: Kolmogorov test and

  16. Preliminary study for small animal preclinical hadrontherapy facility

    Science.gov (United States)

    Russo, G.; Pisciotta, P.; Cirrone, G. A. P.; Romano, F.; Cammarata, F.; Marchese, V.; Forte, G. I.; Lamia, D.; Minafra, L.; Bravatá, V.; Acquaviva, R.; Gilardi, M. C.; Cuttone, G.

    2017-02-01

    Aim of this work is the study of the preliminary steps to perform a particle treatment of cancer cells inoculated in small animals and to realize a preclinical hadrontherapy facility. A well-defined dosimetric protocol was developed to explicate the steps needed in order to perform a precise proton irradiation in small animals and achieve a highly conformal dose into the target. A precise homemade positioning and holding system for small animals was designed and developed at INFN-LNS in Catania (Italy), where an accurate Monte Carlo simulation was developed, using Geant4 code to simulate the treatment in order to choose the best animal position and perform accurately all the necessary dosimetric evaluations. The Geant4 application can also be used to realize dosimetric studies and its peculiarity consists in the possibility to introduce the real target composition in the simulation using the DICOM micro-CT image. This application was fully validated comparing the results with the experimental measurements. The latter ones were performed at the CATANA (Centro di AdroTerapia e Applicazioni Nucleari Avanzate) facility at INFN-LNS by irradiating both PMMA and water solid phantom. Dosimetric measurements were performed using previously calibrated EBT3 Gafchromic films as a detector and the results were compared with the Geant4 simulation ones. In particular, two different types of dosimetric studies were performed: the first one involved irradiation of a phantom made up of water solid slabs where a layer of EBT3 was alternated with two different slabs in a sandwich configuration, in order to validate the dosimetric distribution. The second one involved irradiation of a PMMA phantom made up of a half hemisphere and some PMMA slabs in order to simulate a subcutaneous tumour configuration, normally used in preclinical studies. In order to evaluate the accordance between experimental and simulation results, two different statistical tests were made: Kolmogorov test and

  17. Preliminary study for small animal preclinical hadrontherapy facility

    International Nuclear Information System (INIS)

    Russo, G.; Pisciotta, P.; Cirrone, G.A.P.; Romano, F.; Cammarata, F.; Marchese, V.; Forte, G.I.; Lamia, D.; Minafra, L.; Bravatá, V.; Acquaviva, R.; Gilardi, M.C.; Cuttone, G.

    2017-01-01

    Aim of this work is the study of the preliminary steps to perform a particle treatment of cancer cells inoculated in small animals and to realize a preclinical hadrontherapy facility. A well-defined dosimetric protocol was developed to explicate the steps needed in order to perform a precise proton irradiation in small animals and achieve a highly conformal dose into the target. A precise homemade positioning and holding system for small animals was designed and developed at INFN-LNS in Catania (Italy), where an accurate Monte Carlo simulation was developed, using Geant4 code to simulate the treatment in order to choose the best animal position and perform accurately all the necessary dosimetric evaluations. The Geant4 application can also be used to realize dosimetric studies and its peculiarity consists in the possibility to introduce the real target composition in the simulation using the DICOM micro-CT image. This application was fully validated comparing the results with the experimental measurements. The latter ones were performed at the CATANA (Centro di AdroTerapia e Applicazioni Nucleari Avanzate) facility at INFN-LNS by irradiating both PMMA and water solid phantom. Dosimetric measurements were performed using previously calibrated EBT3 Gafchromic films as a detector and the results were compared with the Geant4 simulation ones. In particular, two different types of dosimetric studies were performed: the first one involved irradiation of a phantom made up of water solid slabs where a layer of EBT3 was alternated with two different slabs in a sandwich configuration, in order to validate the dosimetric distribution. The second one involved irradiation of a PMMA phantom made up of a half hemisphere and some PMMA slabs in order to simulate a subcutaneous tumour configuration, normally used in preclinical studies. In order to evaluate the accordance between experimental and simulation results, two different statistical tests were made: Kolmogorov test and

  18. Preliminary Results From a Heavily Instrumented Engine Ice Crystal Icing Test in a Ground Based Altitude Test Facility

    Science.gov (United States)

    Flegel, Ashlie B.; Oliver, Michael J.

    2016-01-01

    Preliminary results from the heavily instrumented ALF502R-5 engine test conducted in the NASA Glenn Research Center Propulsion Systems Laboratory are discussed. The effects of ice crystal icing on a full scale engine is examined and documented. This same model engine, serial number LF01, was used during the inaugural icing test in the Propulsion Systems Laboratory facility. The uncommanded reduction of thrust (rollback) events experienced by this engine in flight were simulated in the facility. Limited instrumentation was used to detect icing on the LF01 engine. Metal temperatures on the exit guide vanes and outer shroud and the load measurement were the only indicators of ice formation. The current study features a similar engine, serial number LF11, which is instrumented to characterize the cloud entering the engine, detect/characterize ice accretion, and visualize the ice accretion in the region of interest. Data were acquired at key LF01 test points and additional points that explored: icing threshold regions, low altitude, high altitude, spinner heat effects, and the influence of varying the facility and engine parameters. For each condition of interest, data were obtained from some selected variations of ice particle median volumetric diameter, total water content, fan speed, and ambient temperature. For several cases the NASA in-house engine icing risk assessment code was used to find conditions that would lead to a rollback event. This study further helped NASA develop necessary icing diagnostic instrumentation, expand the capabilities of the Propulsion Systems Laboratory, and generate a dataset that will be used to develop and validate in-house icing prediction and risk mitigation computational tools. The ice accretion on the outer shroud region was acquired by internal video cameras. The heavily instrumented engine showed good repeatability of icing responses when compared to the key LF01 test points and during day-to-day operation. Other noticeable

  19. Progress in preliminary studies at Ottana Solar Facility

    Science.gov (United States)

    Demontis, V.; Camerada, M.; Cau, G.; Cocco, D.; Damiano, A.; Melis, T.; Musio, M.

    2016-05-01

    The fast increasing share of distributed generation from non-programmable renewable energy sources, such as the strong penetration of photovoltaic technology in the distribution networks, has generated several problems for the management and security of the whole power grid. In order to meet the challenge of a significant share of solar energy in the electricity mix, several actions aimed at increasing the grid flexibility and its hosting capacity, as well as at improving the generation programmability, need to be investigated. This paper focuses on the ongoing preliminary studies at the Ottana Solar Facility, a new experimental power plant located in Sardinia (Italy) currently under construction, which will offer the possibility to progress in the study of solar plants integration in the power grid. The facility integrates a concentrating solar power (CSP) plant, including a thermal energy storage system and an organic Rankine cycle (ORC) unit, with a concentrating photovoltaic (CPV) plant and an electrical energy storage system. The facility has the main goal to assess in real operating conditions the small scale concentrating solar power technology and to study the integration of the two technologies and the storage systems to produce programmable and controllable power profiles. A model for the CSP plant yield was developed to assess different operational strategies that significantly influence the plant yearly yield and its global economic effectiveness. In particular, precise assumptions for the ORC module start-up operation behavior, based on discussions with the manufacturers and technical datasheets, will be described. Finally, the results of the analysis of the: "solar driven", "weather forecasts" and "combined storage state of charge (SOC)/ weather forecasts" operational strategies will be presented.

  20. Preliminary results from a study of the double beta decay of 150Nd

    International Nuclear Information System (INIS)

    Perillo, I.M.C.; Chan, Y.D.; Hurley, D.; Lesko, K.T.; McDonald, R.J.; Moorhead, M.E.; Norman, E.B.; Smith, A.R.; Stokstad, R.G.

    1996-01-01

    We report the preliminary results from a study of the double beta decay of 150 Nd to the first 0 + excited state of 150 Sm. Our data consists of 50 days of counting 5 kg of natural Nd 2 O 3 at the LBNL-Oroville low background facility. The deduced lower limit for the half life of this decay mode is 4.9.10 19 years. (orig.)

  1. Preliminary assessment report for Virginia Army National Guard Army Aviation Support Facility, Richmond International Airport, Installation 51230, Sandston, Virginia

    International Nuclear Information System (INIS)

    Dennis, C.B.

    1993-09-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Virginia Army National Guard (VaARNG) property in Sandston, Virginia. The Army Aviation Support Facility (AASF) is contiguous with the Richmond International Airport. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The PA is designed to characterize the site accurately and determine the need for further action by examining site activities, quantities of hazardous substances present, and potential pathways by which contamination could affect public health and the environment. The AASF, originally constructed as an active Air Force interceptor base, provides maintenance support for VaARNG aircraft. Hazardous materials used and stored at the facility include JP-4 jet fuel, diesel fuel, gasoline, liquid propane gas, heating oil, and motor oil

  2. Preliminary concepts for materials measurement and accounting in critical facilities

    International Nuclear Information System (INIS)

    Cobb, D.D.; Sapir, J.L.

    1978-01-01

    Preliminary concepts are presented for improved materials measurement and accounting in large critical facilities. These concepts will be developed as part of a study that will emphasize international safeguarding of critical facilities. The major safeguards problem is the timely verification of in-reactor inventory during periods of reactor operation. This will require a combination of measurement, statistical sampling, and data analysis techniques. Promising techniques include integral measurements of reactivity and other reactor parameters that are sensitive to the total fissile inventory, and nondestructive assay measurements of the fissile material in reactor fuel drawers and vault storage canisters coupled with statistical sampling plans tailored for the specific application. The effectiveness of proposed measurement and accounting strategies will be evaluated during the study

  3. Preliminary investigation into aerosol mobilization resulting from fusion reactor disruptions

    International Nuclear Information System (INIS)

    Sharpe, J.P.; Bourham, M.A.; Gilligan, J.G.

    1996-01-01

    An experimental system has been developed to study disruption-induced aerosol mobilization for fusion accident analysis. The SIRENS high heat flux facility at North Carolina State University has been modified to closely simulate disruption conditions expected in tokamak reactors. A hot vapor is formed by an ablation-controlled arc and expansion cooled into a glass chamber, where particle condensation and growth occur. The particles are collected and analyzed for relevant transport properties (e.g. size distribution and shape). Particle characterization methods are discussed, and preliminary results based on simple analysis techniques are given. 2 refs., 6 figs

  4. Monte Carlo simulation of a TRIGA source driven core configuration: Preliminary results

    International Nuclear Information System (INIS)

    Burgio, N.; Ciavola, C.; Santagata, A.

    2002-01-01

    The different core configurations with a k eff ranging from 0.93 to 0.98, and their response when driven by a pulsed neutron source were simulated with MCNP4C3 (Los Alamos - Monte Carlo N Particles). Simulation results could be considered both as preliminary check for nuclear data and a conceptual design for 'source jerk' experiments on the frame of TRIGA Accelerator Driven Experiment (TRADE) on the reactor facility of Casaccia research center. (author)

  5. Preliminary investigations of Monte Carlo Simulations of neutron energy and LET spectra for fast neutron therapy facilities

    International Nuclear Information System (INIS)

    Kroc, T.K.

    2009-01-01

    No fast neutron therapy facility has been built with optimized beam quality based on a thorough understanding of the neutron spectrum and its resulting biological effectiveness. A study has been initiated to provide the information necessary for such an optimization. Monte Carlo studies will be used to simulate neutron energy spectra and LET spectra. These studies will be bench-marked with data taken at existing fast neutron therapy facilities. Results will also be compared with radiobiological studies to further support beam quality ptimization. These simulations, anchored by this data, will then be used to determine what parameters might be optimized to take full advantage of the unique LET properties of fast neutron beams. This paper will present preliminary work in generating energy and LET spectra for the Fermilab fast neutron therapy facility.

  6. Preliminary results from the Small Negative Ion Facility (SNIF) at CCFE

    Science.gov (United States)

    Zacks, J.; McAdams, R.; Booth, J.; Flinders, K.; Holmes, A. J. T.; Simmonds, M.; Stevens, B.; Stevenson, P.; Surrey, E.; Warder, S.; Whitehead, A.; Young, D.

    2013-02-01

    At Culham Centre for Fusion Energy, a new beam extraction test facility has been built with the purpose of studying and enhancing negative ion beam production and transport. The multipole hydrogen ion source is based on a RF generated plasma using a continuous 5kW power supply operating at the industrial standard frequency of 13.56MHz. The cylindrical source has a diameter of 30cm and a depth of 20cm, with a flat spiral antenna driving the source through a quartz window. The magnet configuration is arranged to produce a dipole filter field across the ion source close to the plasma grid. The plasma load is matched to the RF generator using a Pi matching network. The accelerator uses a single extraction aperture of 14mm diameter, with a biased insert for electron suppression. The accelerator is a triode design with a beam energy of up to 30kV. The beamline consists of a turbomolecular pumped vacuum tank with an instrumented beam dump and ports for additional diagnostics. The ITER Neutral Beam source operates with the enhancement of caesium, which, when scaled up to a reactor, will be heavily consumed. The small size of SNIF allows for fast turn around of modifications and alternative materials to caesium can be tested. A full description of the facility and planned diagnostics is given. Initial results are presented, including measurements and calculations of the plasma load on the RF generator, and beam extraction measurements.

  7. Preliminary assessment report for Army Aviation Support Facility No. 3, Installation 13307, Hunter Army Airfield, Savannah, Georgia

    International Nuclear Information System (INIS)

    Kolpa, R.; Smith, K.

    1993-07-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Georgia Army National Guard property located on Hunter Army Airfield (HAA) near Savannah, Georgia, known as Army Aviation Support Facility (AASF) No. 3. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining site activities, types and quantities of hazardous substances utilized, the nature and amounts of wastes generated or stored at the facility, and potential pathways by which contamination could affect public health and the environment. This PA satisfies, for the AASF No. 3 property, requirements of the Department of Defense Installation Restoration Program (IRP). The scope of this assessment is limited to the facilities and past activities contained within the area now occupied by AASF No. 3. However, this assessment report is intended to be read in conjunction with a previous IRP assessment of HAA completed in 1992 (USATHAMA 1992) and to provide comprehensive information on AASF No. 3 for incorporation with information contained in that previous assessment for the entirety of HAA

  8. Preliminary Safety Design Report for Remote Handled Low-Level Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Timothy Solack; Carol Mason

    2012-03-01

    A new onsite, remote-handled low-level waste disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled low-level waste disposal for remote-handled low-level waste from the Idaho National Laboratory and for nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled low-level waste in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This preliminary safety design report supports the design of a proposed onsite remote-handled low-level waste disposal facility by providing an initial nuclear facility hazard categorization, by discussing site characteristics that impact accident analysis, by providing the facility and process information necessary to support the hazard analysis, by identifying and evaluating potential hazards for processes associated with onsite handling and disposal of remote-handled low-level waste, and by discussing the need for safety features that will become part of the facility design.

  9. Preliminary assessment report for Redmond Army National Guard Facility, Installation 53120, Redmond, Washington

    International Nuclear Information System (INIS)

    Ketels, P.; Aggarwal, P.

    1993-08-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Washington Army National Guard (WAARNG) property in Redmond, Washington. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining site activities, quantities of hazardous substances present, and potential pathways by which contamination could affect public health and the environment. This PA satisfies, for the Redmond ARNG property, Phase I of the Department of Defense Installation Restoration Program. The environmentally significant operations (ESOs) associated with the property are (1) supply/storage of hazardous materials, (2) weapons cleaning, (3) the underground storage tanks (USTs), and (4) the use of herbicides. These ESOs are no longer active because of the closure of OMS 10 activities in 1988

  10. Comprehensive development plans for the low- and intermediate-level radioactive waste disposal facility in Korea and preliminary safety assessment

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Kang Il; Kim, Jin Hyeong; Kwon, Mi Jin; Jeong, Mi Seon; Hong, Sung Wook; Park, Jin Beak [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of)

    2016-12-15

    The disposal facility in Gyeongju is planning to dispose of 800,000 packages of low- and intermediate- level radioactive waste. This facility will be developed as a complex disposal facility that has various types of disposal facilities and accompanying management. In this study, based on the comprehensive development plan of the disposal facility, a preliminary post-closure safety assessment is performed to predict the phase development of the total capacity for the 800,000 packages to be disposed of at the site. The results for each scenario meet the performance target of the disposal facility. The assessment revealed that there is a significant impact of the inventory of intermediate-level radionuclide waste on the safety evaluation. Due to this finding, we introduce a disposal limit value for intermediate-level radioactive waste. With stepwise development of safety case, this development plan will increase the safety of disposal facilities by reducing uncertainties within the future development of the underground silo disposal facilities.

  11. Suggestions and comments about preliminary plans of ABNT 20:04.002-001 standard 'Seismic actions for nuclear facilities project'

    International Nuclear Information System (INIS)

    Soares, W.A.

    1984-01-01

    This paper presents an analysis of preliminary plans of standard 'seismic actions for nuclear facilities project'. This document presents since seismic event characterization up to details of structural project of nuclear facilities construction. (C.M.)

  12. Preliminary design of a production automation framework for a pyroprocessing facility

    Directory of Open Access Journals (Sweden)

    Moonsoo Shin

    2018-04-01

    Full Text Available Pyroprocessing technology has been regarded as a promising solution for recycling spent fuel in nuclear power plants. The Korea Atomic Energy Research Institute has been studying the current status of equipment and facilities for pyroprocessing and found that existing facilities are manually operated; therefore, their applications have been limited to laboratory scale because of low productivity and safety concerns. To extend the pyroprocessing technology to a commercial scale, the facility, including all the processing equipment and the material-handling devices, should be enhanced in view of automation. In an automated pyroprocessing facility, a supervised control system is needed to handle and manage material flow and associated operations. This article provides a preliminary design of the supervising system for pyroprocessing. In particular, a manufacturing execution system intended for an automated pyroprocessing facility, named Pyroprocessing Execution System, is proposed, by which the overall production process is automated via systematic collaboration with a planning system and a control system. Moreover, a simulation-based prototype system is presented to illustrate the operability of the proposed Pyroprocessing Execution System, and a simulation study to demonstrate the interoperability of the material-handling equipment with processing equipment is also provided. Keywords: Manufacturing Execution System, Material-handling, Production Automation, Production Planning and Control, Pyroprocessing, Pyroprocessing Execution System

  13. Los Alamos National Laboratory corregated metal pipe saw facility preliminary safety analysis report. Volume I

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-09-19

    This Preliminary Safety Analysis Report addresses site assessment, facility design and construction, and design operation of the processing systems in the Corrugated Metal Pipe Saw Facility with respect to normal and abnormal conditions. Potential hazards are identified, credible accidents relative to the operation of the facility and the process systems are analyzed, and the consequences of postulated accidents are presented. The risk associated with normal operations, abnormal operations, and natural phenomena are analyzed. The accident analysis presented shows that the impact of the facility will be acceptable for all foreseeable normal and abnormal conditions of operation. Specifically, under normal conditions the facility will have impacts within the limits posted by applicable DOE guidelines, and in accident conditions the facility will similarly meet or exceed the requirements of all applicable standards. 16 figs., 6 tabs.

  14. A new gas stripper system for BARC-TIFR Pelletron Accelerator facility: installation and preliminary results

    International Nuclear Information System (INIS)

    Sharma, S.C.; Ninawe, N.G.; Yadav, M.L.; Ekambaram, M.; Ramjilal; Matkar, U.V.; Ansari, Q.N.; Lokare, R.N.; Ramlal; Gupta, A.K.; Bhagwat, P.V.; Pillay, R.G.

    2009-01-01

    The gas-stripper plays a key role in stripping the heavy and molecular ion beams in a tandem accelerator. Efficiency of gas stripper depends on its supporting vacuum pumps. A new recirculating turbo molecular pump-based gas stripper has been installed in the high voltage terminal of Pelletron Accelerator. Re-circulating the stripper gas reduces the flow of gas into the accelerating tubes reducing the transmission losses. Preliminary results obtained using the new gas stripper system are discussed. (author)

  15. Waste Receiving and Processing Facility Module 1: Volume 1, Preliminary Design report

    International Nuclear Information System (INIS)

    1992-03-01

    The Preliminary Design Report (Title 1) for the Waste Receiving and Processing (WRAP) Module 1 provides a comprehensive narrative description of the proposed facility and process systems, the basis for each of the systems design, and the engineering assessments that were performed to support the technical basis of the Title 1 design. The primary mission of the WRAP 1 Facility is to characterize and certify contact-handled (CH) waste in 55-gallon drums for disposal. Its secondary function is to certify CH waste in Standard Waste Boxes (SWBs) for disposal. The preferred plan consist of retrieving the waste and repackaging as necessary in the Waste Receiving and Processing (WRAP) facility to certify TRU waste for shipment to the Waste Isolation Pilot Plant (WIPP) in New Mexico. WIPP is a research and development facility designed to demonstrate the safe and environmentally acceptable disposal of TRU waste from National Defense programs. Retrieved waste found to be Low-Level Waste (LLW) after examination in the WRAP facility will be disposed of on the Hanford site in the low-level waste burial ground. The Hanford Site TRU waste will be shipped to the WIPP for disposal between 1999 and 2013

  16. Preliminary studi on neutronic aspect of a conceptual design of the Kartini reactor base ADS facility

    International Nuclear Information System (INIS)

    Tegas Sutondo

    2012-01-01

    A preliminary study on neutronic aspect of a conceptual design of ADS facility with the basis of Kartini Reaktor, has been performed. The study was intended to see the feasibility from neutronic point of view of Kartini reactor, to be used as a small scale of NPP’s waste transmutation experimental facility. A SRAC code was used as the basis of calculations. The results indicate that the presence of minor actinides (MA) will give a positive reactivity, which tends to increase with the increase of MA concentrations. Based on the defined criteria of subcriticality and by considering the core power distributions and the level of reactivity contribution of MA element, it is concluded that Kartini reactor is potential enough to be used as an ADS experimental facility, mainly for MA concentration between 30 to 50 % of the assumed mixture of C-MA matrix. (author)

  17. The preliminary planning for decommissioning nuclear facilities in Taiwan

    International Nuclear Information System (INIS)

    Li, K.K.

    1993-01-01

    During the congressional hearing in 1992 for a $7 billion project for approval of the fourth nuclear power plant, the public was concerned about the decommissioning of the operating plants. In order to facilitate the public acceptance of nuclear energy and to secure the local capability for appropriate nuclear backend management, both technologically and financially, it is important to have preliminary planning for decommissioning the nuclear facilities. This paper attempted to investigate the possible scope of decommissioning activities and addressed the important regulatory, financial, and technological aspects. More research and development works regarding the issue of decommissioning are needed to carry out the government's will of decent management of nuclear energy from the cradle to the grave

  18. 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

  19. Preliminary results with the CLAMSUD pion spectrometer at the Moscow Meson Factory

    International Nuclear Information System (INIS)

    Badala, A.; Barbera, R.; Librizzi, F.; Longhitano, A.; Nicotra, D.; Palmeri, A.; Pappalardo, G.S.; Riggi, F.; Santoro, A.; Turrisi, R.; Aseev, V.; Feschenko, A.; Gavrilov, Yu.; Guber, F.; Golubeva, M.; Karavicheva, T.; Kurepin, A.; Ostroumov, P.; Potapov, V.; Tiflov, V.; Zhuravlev, A.

    1995-01-01

    A magnetic spectrometer has been recently installed at the new proton beam facility of the Moscow Meson Factory, to study charged pion production from proton-nucleus interactions at 200-400 MeV bombarding energy. Preliminary reults obtained during the first runs are reported. The planned physics program is also discussed. (orig.)

  20. Preliminary dismantling for the decommissioning of nuclear licensed facilities at the CEA Centre in Fontenay aux Roses

    International Nuclear Information System (INIS)

    Estivie, D.; Bohar, M.P.; Jeanjacques, M.; Binet, C.

    2008-01-01

    Under the perimeter modification programme for the Nuclear Licensed Facilities (NLFs) of the French Atomic Energy Commission centre at Fontenay aux Roses (CEN-FAR), preliminary dismantling work proved necessary to decommission the buildings outside the nuclear perimeter and create interim storage areas for waste packages. This summary describes the dismantling of Buildings 07, 53 and 91/54, which are the most representative of the preliminary dismantling work. (author)

  1. The X-Ray Pebble Recirculation Experiment (X-PREX): Facility Description, Preliminary Discrete Element Method Simulation Validation Studies, and Future Test Program

    International Nuclear Information System (INIS)

    Laufer, Michael R.; Bickel, Jeffrey E.; Buster, Grant C.; Krumwiede, David L.; Peterson, Per F.

    2014-01-01

    This paper presents a facility description, preliminary results, and future test program of the new X-Ray Pebble Recirculation Experiment (X-PREX), which is now operational and being used to collect data on the behavior of slow dense granular flows relevant to pebble bed reactor core designs. The X-PREX facility uses digital x-ray tomography methods to track both the translational and rotational motion of spherical pebbles, which provides unique experimental results that can be used to validate discrete element method (DEM) simulations of pebble motion. The validation effort supported by the X-PREX facility provides a means to build confidence in analysis of pebble bed configuration and residence time distributions that impact the neutronics, thermal hydraulics, and safety analysis of pebble bed reactor cores. Preliminary experimental and DEM simulation results are reported for silo drainage, a classical problem in the granular flow literature, at several hopper angles. These studies include conventional converging and novel diverging geometries that provide additional flexibility in the design of pebble bed reactor cores. Excellent agreement is found between the X-PREX experimental and DEM simulation results. Finally, this paper discusses additional studies in progress relevant to the design and analysis of pebble bed reactor cores including pebble recirculation in cylindrical core geometries and evaluation of forces on shut down blades inserted directly into a packed pebble bed. (author)

  2. Cell emulation and preliminary results.

    Science.gov (United States)

    2016-07-01

    This report details preliminary results of the testing plan implemented by the Hawaii Natural Energy Institute to evaluate Electric Vehicle (EV) battery durability and reliability under electric utility grid operations. Commercial EV battery cells ar...

  3. Occupational exposure assessment in a radioactive facility: a preliminary evaluation

    International Nuclear Information System (INIS)

    Alves, Alice dos Santos; Gerulis, Eduardo; Sanches, Matias P.; Carneiro, Janete C.G.G.

    2013-01-01

    The risk that a worker has found on the job is a function of the hazards present and his exposure level to those hazards. Exposure and risk assessment is therefore the heart of all occupational health and industrial hygiene programs involving a continuous process of information gathering. The use of a systematic method to characterize workplace exposures to chemical, physical and biological risks is a fundamental part of this process. This study aims to carry out a preliminary evaluation in a radioactive facility, identifying potential exposures and consequently the existing occupational hazards (risk/agent) in the workplace which the employee is subject. The study is based on proposal to carry out a basic characterization of the facility, which could be the first step in the investigation of occupational exposure. For this study was essential to know the workplace, potential risks and agents; workforce profile including assignment of tasks, sources of exposure processes, and control measures. The main tool used in this study was based on references, records, standards, procedures, interviews with the workers and with management. Since the basic characterization of the facility has been carried out, consequently the potential exposure to the agents of risks to workers has been identified. The study provided an overview of the perception of risk founded at facility studied. It is expected to contribute with the occupational health program resources for welfare of the worker. (author)

  4. Occupational exposure assessment in a radioactive facility: a preliminary evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Alves, Alice dos Santos; Gerulis, Eduardo; Sanches, Matias P.; Carneiro, Janete C.G.G., E-mail: alicesante@hotmail.com [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2013-07-01

    The risk that a worker has found on the job is a function of the hazards present and his exposure level to those hazards. Exposure and risk assessment is therefore the heart of all occupational health and industrial hygiene programs involving a continuous process of information gathering. The use of a systematic method to characterize workplace exposures to chemical, physical and biological risks is a fundamental part of this process. This study aims to carry out a preliminary evaluation in a radioactive facility, identifying potential exposures and consequently the existing occupational hazards (risk/agent) in the workplace which the employee is subject. The study is based on proposal to carry out a basic characterization of the facility, which could be the first step in the investigation of occupational exposure. For this study was essential to know the workplace, potential risks and agents; workforce profile including assignment of tasks, sources of exposure processes, and control measures. The main tool used in this study was based on references, records, standards, procedures, interviews with the workers and with management. Since the basic characterization of the facility has been carried out, consequently the potential exposure to the agents of risks to workers has been identified. The study provided an overview of the perception of risk founded at facility studied. It is expected to contribute with the occupational health program resources for welfare of the worker. (author)

  5. Experiments, conceptual design, preliminary cost estimates and schedules for an underground research facility

    International Nuclear Information System (INIS)

    Korbin, G.; Wollenberg, H.; Wilson, C.; Strisower, B.; Chan, T.; Wedge, D.

    1981-09-01

    Plans for an underground research facility are presented, incorporating techniques to assess the hydrological and thermomechanical response of a rock mass to the introduction and long-term isolation of radioactive waste, and to assess the effects of excavation on the hydrologic integrity of a repository and its subsequent backfill, plugging, and sealing. The project is designed to utilize existing mine or civil works for access to experimental areas and is estimated to last 8 years at a total cost for contruction and operation of $39.0 million (1981 dollars). Performing the same experiments in an existing underground research facility would reduce the duration to 7-1/2 years and cost $27.7 million as a lower-bound estimate. These preliminary plans and estimates should be revised after specific sites are identified which would accommodate the facility

  6. Antares: preliminary demonstrator results

    International Nuclear Information System (INIS)

    Kouchner, A.

    2000-05-01

    The ANTARES collaboration is building an undersea neutrino telescope off Toulon (Mediterranean sea) with effective area ∼ 0.1 km 2 . An extensive study of the site properties has been achieved together with software analysis in order to optimize the performance of the detector. Results are summarized here. An instrumented line, linked to shore for first time via an electro-optical cable, has been immersed late 1999. The preliminary results of this demonstrator line are reported. (author)

  7. Preliminary assessment report for Army Aviation Support Facility No. 3, Installation 13307, Hunter Army Airfield, Savannah, Georgia. Installation Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Kolpa, R.; Smith, K.

    1993-07-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Georgia Army National Guard property located on Hunter Army Airfield (HAA) near Savannah, Georgia, known as Army Aviation Support Facility (AASF) No. 3. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining site activities, types and quantities of hazardous substances utilized, the nature and amounts of wastes generated or stored at the facility, and potential pathways by which contamination could affect public health and the environment. This PA satisfies, for the AASF No. 3 property, requirements of the Department of Defense Installation Restoration Program (IRP). The scope of this assessment is limited to the facilities and past activities contained within the area now occupied by AASF No. 3. However, this assessment report is intended to be read in conjunction with a previous IRP assessment of HAA completed in 1992 (USATHAMA 1992) and to provide comprehensive information on AASF No. 3 for incorporation with information contained in that previous assessment for the entirety of HAA.

  8. Preliminary siting activities for new waste handling facilities at the Idaho National Engineering Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, D.D.; Hoskinson, R.L.; Kingsford, C.O.; Ball, L.W.

    1994-09-01

    The Idaho Waste Processing Facility, the Mixed and Low-Level Waste Treatment Facility, and the Mixed and Low-Level Waste Disposal Facility are new waste treatment, storage, and disposal facilities that have been proposed at the Idaho National Engineering Laboratory (INEL). A prime consideration in planning for such facilities is the selection of a site. Since spring of 1992, waste management personnel at the INEL have been involved in activities directed to this end. These activities have resulted in the (a) identification of generic siting criteria, considered applicable to either treatment or disposal facilities for the purpose of preliminary site evaluations and comparisons, (b) selection of six candidate locations for siting,and (c) site-specific characterization of candidate sites relative to selected siting criteria. This report describes the information gathered in the above three categories for the six candidate sites. However, a single, preferred site has not yet been identified. Such a determination requires an overall, composite ranking of the candidate sites, which accounts for the fact that the sites under consideration have different advantages and disadvantages, that no single site is superior to all the others in all the siting criteria, and that the criteria should be assigned different weighing factors depending on whether a site is to host a treatment or a disposal facility. Stakeholder input should now be solicited to help guide the final selection. This input will include (a) siting issues not already identified in the siting, work to date, and (b) relative importances of the individual siting criteria. Final site selection will not be completed until stakeholder input (from the State of Idaho, regulatory agencies, the public, etc.) in the above areas has been obtained and a strategy has been developed to make a composite ranking of all candidate sites that accounts for all the siting criteria.

  9. Preliminary siting activities for new waste handling facilities at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Taylor, D.D.; Hoskinson, R.L.; Kingsford, C.O.; Ball, L.W.

    1994-09-01

    The Idaho Waste Processing Facility, the Mixed and Low-Level Waste Treatment Facility, and the Mixed and Low-Level Waste Disposal Facility are new waste treatment, storage, and disposal facilities that have been proposed at the Idaho National Engineering Laboratory (INEL). A prime consideration in planning for such facilities is the selection of a site. Since spring of 1992, waste management personnel at the INEL have been involved in activities directed to this end. These activities have resulted in the (a) identification of generic siting criteria, considered applicable to either treatment or disposal facilities for the purpose of preliminary site evaluations and comparisons, (b) selection of six candidate locations for siting,and (c) site-specific characterization of candidate sites relative to selected siting criteria. This report describes the information gathered in the above three categories for the six candidate sites. However, a single, preferred site has not yet been identified. Such a determination requires an overall, composite ranking of the candidate sites, which accounts for the fact that the sites under consideration have different advantages and disadvantages, that no single site is superior to all the others in all the siting criteria, and that the criteria should be assigned different weighing factors depending on whether a site is to host a treatment or a disposal facility. Stakeholder input should now be solicited to help guide the final selection. This input will include (a) siting issues not already identified in the siting, work to date, and (b) relative importances of the individual siting criteria. Final site selection will not be completed until stakeholder input (from the State of Idaho, regulatory agencies, the public, etc.) in the above areas has been obtained and a strategy has been developed to make a composite ranking of all candidate sites that accounts for all the siting criteria

  10. Preliminary results of steel containment vessel model test

    International Nuclear Information System (INIS)

    Matsumoto, T.; Komine, K.; Arai, S.

    1997-01-01

    A high pressure test of a mixed-scaled model (1:10 in geometry and 1:4 in shell thickness) of a steel containment vessel (SCV), representing an improved boiling water reactor (BWR) Mark II containment, was conducted on December 11-12, 1996 at Sandia National Laboratories. This paper describes the preliminary results of the high pressure test. In addition, the preliminary post-test measurement data and the preliminary comparison of test data with pretest analysis predictions are also presented

  11. Preliminary clinical results from the EORTC 11961 trial at the petten irradiation facility

    International Nuclear Information System (INIS)

    Sauerwein, W.; Hideghety, K.; Vries, M.J. de

    2000-01-01

    Based on the pre-clinical work of the European Collaboration on Boron Neutron Capture Therapy a study protocol was prepared in 1995 to initiate Boron Neutron Capture Therapy (BNCT) in patients at the High Flux Reactor (HFR) in Petten. Bio-distribution and pharmacokinetics data of the boron drug Na 2 B 12 H 11 SH (BSH) as well as the radiobiological effects of BNCT with BSH in healthy brain tissue of dogs were considered in designing the strategy for this clinical Phase I trial. The primary goal of the radiation dose escalation study is the investigation of possible adverse events due to BNCT; i.e. to establish the dose limiting toxicity and the maximal tolerated radiation dose. The treatment is delivered in 4 fractions at a defined average boron concentration in blood. After an observation period of at least 6 months, the dose is increased by 10% for the next cohort. The preliminary results of the first cohort are presented here. The evaluated dose level can be considered to be safe. (author)

  12. Preliminary validation of RELAP5/Mod4.0 code for LBE cooled NACIE facility

    Energy Technology Data Exchange (ETDEWEB)

    Kumari, Indu; Khanna, Ashok, E-mail: akhanna@iitk.ac.in

    2017-04-01

    Highlights: • Detail discussion of thermo physical properties of Lead Bismuth Eutectic incorporated in the code RELAP5/Mod4.0 included. • Benchmarking of LBE properties in RELAP5/Mod4.0 against literature. • NACIE facility for three different power levels (10.8, 21.7 and 32.5 kW) under natural circulation considered for benchmarking. • Preliminary validation of the LBE properties against experimental data. • NACIE facility for power level 22.5 kW considered for validation. - Abstract: The one-dimensional thermal hydraulic computer code RELAP5 was developed for thermal hydraulic study of light water reactor as well as for nuclear research reactors. The purpose of this work is to evaluate the code RELAP5/Mod4.0 for analysis of research reactors. This paper consists of three major sections. The first section presents detailed discussions on thermo-physical properties of Lead Bismuth Eutectic (LBE) incorporated in RELAP5/Mod4.0 code. In the second section, benchmarking of RELAP5/Mod4.0 has been done with the Natural Circulation Experimental (NACIE) facility in comparison with Barone’s simulations using RELAP5/Mod3.3. Three different power levels (10.8 kW, 21.7 kW and 32.5 kW) under natural circulation conditions are considered. Results obtained for LBE temperatures, temperature difference across heat section, pin surface temperatures, mass flow rates and heat transfer coefficients in heat section heat exchanger are in agreement with Barone’s simulation results within 7% of average relative error. Third section presents validation of RELAP5/Mod4.0 against the experimental data of NACIE facility performed by Tarantino et al. test number 21 at power of 22.5 kW comparing the profiles of temperatures, mass flow rate and velocity of LBE. Simulation and experimental results agree within 7% of average relative error.

  13. Wastewater characterization of IPEN facilities - a preliminary study

    International Nuclear Information System (INIS)

    Monteiro, Lucilena R.; Goncalves, Cristina; Terazan, Wagner R.; Cotrim, Marycel E.B.; Pires, Maria Aparecida F.

    2011-01-01

    As part of IPEN's Environmental Monitoring Program, wastewater sample collection and analysis was implemented on a daily basis. CQMA- Centro de Quimica e Meio Ambiente was responsible for the determination of total, fixed and volatile solids, pH, metals (as Al, Sb, Ba, Cd, Pb, Co, Cu, Cr, Hg, Mo, Ni, Ag, Na, Zn, Ca, Mg, Be, Sn, Li, K, Sr, Ti and V), semimetals (As, B, Se and Si) and anions (such as chloride, nitrate, sulfate and fluoride). The results were compared to the legal values established by the Sao Paulo State regulation 8,468/76, which defines the maximum permitted values for most of the studied substances in wastewater, aiming its releasing in public wastewater treatment system. The evaluation of this parameters concentration on Ipen's effluent implies that 50% of the wastewater corresponds to organic matter due to the sanitary load and inorganic macro elements, mainly as sodium, potassium, calcium. The only parameter not found in accordance with Brazilian legislation was pH in four out of the one hundred and seven samples collected throughout 2009 (2.8% of the samples analyzed). This preliminary study showed the effluents generated at Ipen's facility is characterized by the presence of organic matter and macro elements, commonly found in sanitary wastewater and it is in compliance with Sao Paulo regulations. (author)

  14. Posiva's application for a decision in principle concerning a disposal facility for spent nuclear fuel. STUK's statement and preliminary safety appraisal

    International Nuclear Information System (INIS)

    Ruokola, E.

    2000-03-01

    In May 1999, Posiva Ltd submitted to the Government an application, pursuant to the Nuclear Energy Act, for a Decision in Principle on a disposal facility for spent nuclear fuel from the Finnish nuclear power plants. The Ministry of Trade and Industry requested the Radiation and Nuclear Safety Authority (STUK) to draw up a preliminary safety appraisal concerning the proposed disposal facility. In the beginning of this report, STUK's statement to the Ministry and Industry concerning the proposed disposal facility is given. In that statement, STUK concludes that the Decision in Principle is currently justified from the standpoint of safety. The statement is followed by a safety appraisal, where STUK deems, how the proposed disposal concept, site and facility comply with the safety requirements included in the Government's Decision (478/1999). STUK's preliminary safety appraisal was supported by contributions from a number of outside experts. A collective opinion by an international group of ten distinguished experts is appended to this report. (orig.)

  15. PRELIMINARY STUDY TO PRIMARY EDUCATION FACILITIES (A Comparison Study between Indonesia and Developed Countries

    Directory of Open Access Journals (Sweden)

    Lucy Yosita

    2006-01-01

    Full Text Available This writing is a preliminary study to condition of primary education facilities in Indonesia, and then comparing these with theories as well as various relevant cases aimed to know the problem more obviously. Basically, there is difference between primary education facilities in Indonesia with those in developed countries. Meanwhile on the other hand, the condition as well as the completion of education facility is actually as the main factor contributes to address the purpose of learning process. If building design, interior and also site plan were dynamic in form, space, colour and tools, those would be probably more stimulate activity and influence into the growth of students. However, lastly, it is still required further analysis, as an example analysis to student's behaviour in spaces of learning environment, more detail and within enough time, not only at indoor but also at outdoor.

  16. Preliminary study for treatment methodology establishment of liquid waste containing uranium in refining facility lagoon

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Byung Jik; Lee, Kune Woo; Won, Hui Jun; Ahn, Byung Gil; Shim, Joon Bo

    1999-12-01

    The preliminary study which establishes the treatment methodology of the sludge waste containing uranium in the conversion facility lagoon was performed. The property of lagoon liquid waste such as the initial water content, the density including radiochemical analysis results were obtained using the samples taken from the lagoon. The objective of this study is to provide some basically needed materials for selection of the most proper lagoon waste treatment methodology by reviewing the effective processes and methods for minimizing the secondary waste resulting from the treatment and disposition of large amount of radioactive liquid waste according to the facility closing. The lagoon waste can be classified into two sorts, such as supernatant and precipitate. The supernatants contain uranium less than 5 ppm and their water content are about 35 percent. Therefore, supernatants are solutions composed of mainly salt components. However, the precipitates have lots of uranium compound contained in the coagulation matrix, and are formed as two kinds of crystalline structures. The most proper method minimizing the secondary waste would be direct drying and solidification of the supernatants and precipitates after separation of them by filtering. (author)

  17. Preliminary data on rheological limits for grouts in the Transportable Grout Facility

    International Nuclear Information System (INIS)

    Gilliam, T.M.; McDaniel, E.W.; Dole, L.R.; West, G.A.

    1987-04-01

    This report describes a method for establishing rheological limits for grouts that can be pumped in the Hanford Transportable Grout Facility (TGF). This method is based on two models that require determining two key parameters - gel strength and density. This work also presents rheological data on grouts prepared with simulated customer phosphate wastes (CPW) and double shell slurry (DSS) from the Hanford complex. These data can be used to make preliminary estimates of operating rheological limits of the TFG grouts. The suggested design limits will include safety factors that will increase these limits significantly. 4 refs

  18. Preliminary geotechnical evaluation of deep borehole facilities for nuclear waste disposal in shales

    International Nuclear Information System (INIS)

    Nataraj, M.S.; New Orleans Univ., LA

    1991-01-01

    This study is concerned with a preliminary engineering evaluation of borehole facilities for nuclear waste disposal in shales. Some of the geotechnical properties of Pierre, Rhinestreet, and typical illite shale have been collected. The influence of a few geotechnical properties on strength and deformation of host material is briefly examined. It appears that Pierre shale is very unstable and requires support to prevent collapse. Typical illite shale is more stable than Rhinestreet shale, although it undergoes relatively more deformation. 16 refs., 5 figs., 3 tabs

  19. Scoping-level Probabilistic Safety Assessment of a complex experimental facility: Challenges and first results from the application to a neutron source facility (MEGAPIE)

    International Nuclear Information System (INIS)

    Podofillini, L.; Dang, V.N.; Thomsen, K.

    2008-01-01

    This paper presents a scoping-level application of Probabilistic Safety Assessment (PSA) to selected systems of a complex experimental facility. In performing a PSA for this type of facility, a number of challenges arise, mainly due to the extensive use of electronic and programmable components and of one-of-a-kind components. The experimental facility is the Megawatt Pilot Target Experiment (MEGAPIE), which was hosted at the Paul Scherrer Institut (PSI). MEGAPIE demonstrated the feasibility of a liquid lead-bismuth target for spallation facilities at a proton beam power level of 1 MW. Given the challenges to estimate initiating event frequencies and failure event probabilities, emphasis is placed on the qualitative results obtainable from the PSA. Even though this does not allow a complete and appropriate characterization of the risk profile, some level of importance/significance evaluation was feasible, and practical and detailed recommendations on potential system improvements were derived. The second part of the work reports on a preliminary quantification of the facility risk. This provides more information on risk significance, which allows prioritizing the insights and recommendations obtained from the PSA. At the present stage, the limited knowledge on initiating and failure events is reflected in the uncertainties in their probabilities as well as in inputs quantified with bounding values. Detailed analyses to improve the quantification of these inputs, many of which turn out to be important contributors, were out of the scope of this study. Consequently, the reported results should be primarily considered as a demonstration of how quantification of the facility risk by a PSA can support risk-informed decisions, rather than precise figures of the facility risk

  20. Performance comparison between the mycobacteria growth indicator tube system and Löwenstein-Jensen medium in the routine detection of Mycobacterium tuberculosis at public health care facilities in Rio de Janeiro, Brazil: preliminary results of a pragmatic clinical trial.

    Science.gov (United States)

    Moreira, Adriana da Silva Rezende; Huf, Gisele; Vieira, Maria Armanda; Fonseca, Leila; Ricks, Monica; Kritski, Afrânio Lineu

    2013-01-01

    In view of the fact that the World Health Organization has recommended the use of the mycobacteria growth indicator tube (MGIT) 960 system for the diagnosis of tuberculosis and that there is as yet no evidence regarding the clinical impact of its use in health care systems, we conducted a pragmatic clinical trial to evaluate the clinical performance and cost-effectiveness of the use of MGIT 960 at two health care facilities in the city of Rio de Janeiro, Brazil, where the incidence of tuberculosis is high. Here, we summarize the methodology and preliminary results of the trial. (ISRCTN.org Identifier: ISRCTN79888843 [http://isrctn.org/]) In view of the fact that the World Health Organization has recommended the use of the mycobacteria growth indicator tube (MGIT) 960 system for the diagnosis of tuberculosis and that there is as yet no evidence regarding the clinical impact of its use in health care systems, we conducted a pragmatic clinical trial to evaluate the clinical performance and cost-effectiveness of the use of MGIT 960 at two health care facilities in the city of Rio de Janeiro, Brazil, where the incidence of tuberculosis is high. Here, we summarize the methodology and preliminary results of the trial. (ISRCTN.org Identifier: ISRCTN79888843 [http://isrctn.org/]).

  1. Preliminary shielding estimates for the proposed Oak Ridge National Laboratory (ORNL) Radioactive Ion Beam Facility (RIBF)

    International Nuclear Information System (INIS)

    Johnson, J.O.; Gabriel, T.A.; Lillie, R.A.

    1996-01-01

    The Oak Ridge National Laboratory (ORNL) has proposed designing and implementing a new target-ion source for production and injection of negative radioactive ion beams into the Hollifield tandem accelerator. This new facility, referred to as the Radioactive Ion Beam Facility (RIBF), will primarily be used to advance the scientific communities' capabilities for performing state-of-the-art cross-section measurements. Beams of protons or other light, stable ions from the Oak Ridge Isochronous Cyclotron (ORIC) will be stopped in the RIBF target ion source and the resulting radioactive atoms will be ionized, charge exchanged, accelerated, and injected into the tandem accelerator. The ORIC currently operates with proton energies up to 60 MeV and beam currents up to 100 microamps with a maximum beam power less than 2.0 kW. The proposed RIBF will require upgrading the ORIC to generate proton energies up to 200 MeV and beam currents up to 200 microamps for optimum performance. This report summarizes the results of a preliminary one-dimensional shielding analysis of the proposed upgrade to the ORIC and design of the RIBF. The principal objective of the shielding analysis was to determine the feasibility of such an upgrade with respect to existing shielding from the facility structure, and additional shielding requirements for the 200 MeV ORIC machine and RIBF target room

  2. Preliminary Feasibility Study on the Construction of Steel Hot Cell Facility for Precise Manipulated Examinations

    International Nuclear Information System (INIS)

    Ahn, Sangbok; Kwon, Hyungmun; Kim, Heemoon; Kim, Dosik; Min, Duckkee; Hong, Kwonpyo

    2006-01-01

    Hot laboratory is essential facility to research and develop in the nuclear industries to examine radioactive materials. The post irradiation examinations for irradiated fuels and materials should be mainly conducted in the hot cell facility to protect radiations to operators. Hot cells are divided into a concrete hot cell and a steel hot cell according to the wall materials. Usually a concrete hot cell is applied to test for high level radioactive materials like as a fuel assembly, rods, and large structure specimens, and a steel hot cell for comparatively lower level activity materials in fuel fragments, and small structural materials. A steel hot cell has many benefits in a specimen manipulation, construction and maintenance costs. In recent the test for the irradiated materials is more frequently required a small and precise manipulating examination for higher degree tests of research and developments. Unfortunately hot laboratory facilities in domestics have mainly constituted of concrete hot cells, and not ready for techniques in steel hot cells. In this paper the construction feasibility of steel hot cell facility is preliminary reviewed in the points of the status of domestic facilities, the test demand prospect and detailed plans

  3. Plans and Preliminary Results of Fundamental Studies of Ice Crystal Icing Physics in the NASA Propulsion Systems Laboratory

    Science.gov (United States)

    Struk, Peter; Tsao, Jen-Ching; Bartkus, Tadas

    2017-01-01

    This paper describes plans and preliminary results for using the NASA Propulsion Systems Lab (PSL) to experimentally study the fundamental physics of ice-crystal ice accretion. NASA is evaluating whether this facility, in addition to full-engine and motor-driven-rig tests, can be used for more fundamental ice-accretion studies that simulate the different mixed-phase icing conditions along the core flow passage of a turbo-fan engine compressor. The data from such fundamental accretion tests will be used to help develop and validate models of the accretion process. This paper presents data from some preliminary testing performed in May 2015 which examined how a mixed-phase cloud could be generated at PSL using evaporative cooling in a warmer-than-freezing environment.

  4. PRTR/309 building nuclear facility preliminary

    International Nuclear Information System (INIS)

    Cornwell, B.C.

    1994-01-01

    The hazard classification of the Plutonium Recycle Test Reactor (PRTR)/309 building as a ''Radiological Facility'' and the office portions as ''Other Industrial Facility'' are documented by this report. This report provides: a synopsis of the history and facility it's uses; describes major area of the facility; and assesses the radiological conditions for the facility segments. The assessment is conducted using the hazard category threshold values, segmentation methodology, and graded approach guidance of DOE-STD-1027-92

  5. Experiments to determine the migration potential for water and contaminants in shallow land burial facilities design, emplacement, and preliminary results

    International Nuclear Information System (INIS)

    DePoorter, G.L.; Abeele, W.V.; Burton, B.W.

    1982-01-01

    Leaching and transport of radionuclides by water has been a primary mode of radioactive contamination from low-level radioactive waste disposal facilities. Similarly, the infiltration of water into nonradioactive hazardous waste disposal facilities has resulted in the movement of contaminants out of these disposal facilities. Although there have been many laboratory studies on water movement and contaminant transport, there is a need for more large scale field experiments. Large scale field experiments are necessary to (1) measure hydraulic conductivities on a scale typical of actual shallow land burial facilities and hazardous waste disposal facilities, (2) allow comparisons to be made between full scale and laboratory measurements, (3) verify the applicability of calculational methods for determining unsaturated hydraulic conductivities from water retention curves, and (4) for model validation. Experiments that will provide the information to do this are described in this paper

  6. Preliminary definition of the remote handling system for the current IFMIF Test Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Queral, V., E-mail: vicentemanuel.queral@ciemat.es [Laboratorio Nacional de Fusion, EURATOM-CIEMAT, 28040 Madrid (Spain); Urbon, J. [Laboratorio Nacional de Fusion, EURATOM-CIEMAT, 28040 Madrid (Spain); Instituto de Fusion Nuclear, Universidad Politecnica de Madrid, 28006 Madrid (Spain); Garcia, A.; Cuarental, I.; Mota, F. [Laboratorio Nacional de Fusion, EURATOM-CIEMAT, 28040 Madrid (Spain); Micciche, G. [CR ENEA Brasimone, I-40035 Camugnano (BO) (Italy); Ibarra, A. [Laboratorio Nacional de Fusion, EURATOM-CIEMAT, 28040 Madrid (Spain); Rapisarda, D. [Laboratorio Nacional de Fusion, EURATOM-CIEMAT, 28040 Madrid (Spain); Instituto de Fusion Nuclear, Universidad Politecnica de Madrid, 28006 Madrid (Spain); Casal, N. [Laboratorio Nacional de Fusion, EURATOM-CIEMAT, 28040 Madrid (Spain)

    2011-10-15

    A coherent design of the remote handling system with the design of the components to be manipulated is vital for reliable, safe and fast maintenance, having a decisive impact on availability, occupational exposures and operational cost of the facility. Highly activated components in the IFMIF facility are found at the Test Cell, a shielded pit where the samples are accurately located. The remote handling system for the Test Cell reference design was outlined in some past IFMIF studies. Currently a new preliminary design of the Test Cell in the IFMIF facility is being developed, introducing important modifications with respect to the reference one. This recent design separates the previous Vertical Test Assemblies in three functional components: Test Modules, shielding plugs and conduits. Therefore, it is necessary to adapt the previous design of the remote handling system to the new maintenance procedures and requirements. This paper summarises such modifications of the remote handling system, in particular the assessment of the feasibility of a modified commercial multirope crane for the handling of the weighty shielding plugs for the new Test Cell and a quasi-commercial grapple for the handling of the new Test Modules.

  7. Preliminary definition of the remote handling system for the current IFMIF Test Facilities

    International Nuclear Information System (INIS)

    Queral, V.; Urbon, J.; Garcia, A.; Cuarental, I.; Mota, F.; Micciche, G.; Ibarra, A.; Rapisarda, D.; Casal, N.

    2011-01-01

    A coherent design of the remote handling system with the design of the components to be manipulated is vital for reliable, safe and fast maintenance, having a decisive impact on availability, occupational exposures and operational cost of the facility. Highly activated components in the IFMIF facility are found at the Test Cell, a shielded pit where the samples are accurately located. The remote handling system for the Test Cell reference design was outlined in some past IFMIF studies. Currently a new preliminary design of the Test Cell in the IFMIF facility is being developed, introducing important modifications with respect to the reference one. This recent design separates the previous Vertical Test Assemblies in three functional components: Test Modules, shielding plugs and conduits. Therefore, it is necessary to adapt the previous design of the remote handling system to the new maintenance procedures and requirements. This paper summarises such modifications of the remote handling system, in particular the assessment of the feasibility of a modified commercial multirope crane for the handling of the weighty shielding plugs for the new Test Cell and a quasi-commercial grapple for the handling of the new Test Modules.

  8. Preliminary conceptual design and cost estimation for Korea Advanced Pyroprocessing Facility Plus (KAPF+)

    Energy Technology Data Exchange (ETDEWEB)

    Ko, Won Il, E-mail: nwiko@kaeri.re.kr [Korea Atomic Energy Research Institute, 989-111, Daedeok-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Lee, Ho Hee, E-mail: nhhlee@kaeri.re.kr [Korea Atomic Energy Research Institute, 989-111, Daedeok-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Choi, Sungyeol, E-mail: csy@kaeri.re.kr [Korea Atomic Energy Research Institute, 989-111, Daedeok-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Kim, Sung-Ki, E-mail: sgkim1@kaeri.re.kr [Korea Atomic Energy Research Institute, 989-111, Daedeok-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Park, Byung Heung, E-mail: b.h.park@ut.ac.kr [Department of Chemical and Biological Engineering, Korea National University of Transportation, 50 Daehak-ro, Chungju-si, Chungbuk, 380-702 (Korea, Republic of); Lee, Hyo Jik, E-mail: hyojik@kaeri.re.kr [Korea Atomic Energy Research Institute, 989-111, Daedeok-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Kim, In Tae, E-mail: nitkim@kaeri.re.kr [Department of Chemical and Biological Engineering, Korea National University of Transportation, 50 Daehak-ro, Chungju-si, Chungbuk, 380-702 (Korea, Republic of); Lee, Han Soo, E-mail: hslee5@kaeri.re.kr [Korea Atomic Energy Research Institute, 989-111, Daedeok-daero, Yuseong-gu, Daejeon 305-353 (Korea, Republic of)

    2014-10-01

    Highlights: • Conceptual design is created for a pilot pyroprocessing plant treating PWR spent fuel. • Pilot-scale design is based on a capacity of 400 tHM/yr with 60 years lifetime. • All individual processes are integrated into a single system from feed to products. • Overall facility design is developed for a pilot pyroprocessing plant. • Unit process cost is estimated for pyroprocessing with uncertainties. - Abstract: Korea has developed pyroprocessing technology as a potential option for recycling spent fuels (SFs) from pressurized water reactors (PWRs). The pyroprocessing consists of various key unit processes and a number of research activities have been focused on each process. However, to realize the whole pyroprocessing concept, there is a critical need for integrating the individual developments and addressing a material flow from feed to final products. In addition, the advancement on overall facility design is an indispensable aspect for demonstration and commercialization of the pyroprocessing. In this study, a facility named as Korea Advanced Pyroprocess Facility Plus (KAPF+) is conceptualized with a capacity of 400 tHM/yr. The process steps are categorized based on their own characteristics while the capacities of process equipment are determined based on the current technical levels. The facility concept with a site layout of 104,000 m{sup 2} is developed by analyzing the operation conditions and materials treated in each process. As an economic approach to the proposed facility, the unit cost (781 $/kgHM denominated in 2009 USD) for KAPF+ is also analyzed with the conceptual design with preliminary sensitivity assessments including decontamination and decommissioning costs, a discount rate, staffing costs, and plant lifetime. While classifying and describing cost details of KAPF+, this study compares the unit cost of KAPF+ treating PWR SF to that of the pyroprocessing facility treating sodium-cooled fast reactor (SFR) SF.

  9. 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

  10. Preliminary results from NOAMP deep drifting floats

    International Nuclear Information System (INIS)

    Ollitrault, M.

    1989-01-01

    This paper is a very brief and preliminary outline of first results obtained with deep SOFAR floats in the NOAMP area. The work is now going toward more precise statistical estimations of mean and variable currents, together with better tracking to resolve submesoscales and estimate diffusivities due to mesoscale and smaller scale motions. However the preliminary results confirm that the NOAMP region (and surroundings) has a deep mesoscale eddy field that is considerably more energetic that the mean field (r.m.s. velocities are of order 5 cm s -1 ), although both values are diminished compared to the western basin. A data report containing trajectories and statistics is scheduled to be published by IFREMER in the near future. The project main task is to especially study the dispersion of radioactive substances

  11. OMEGA Upgrade preliminary design

    International Nuclear Information System (INIS)

    Craxton, R.S.

    1989-10-01

    The OMEGA laser system at the Laboratory for Laser Energetics of the University of Rochester is the only major facility in the United States capable of conducting fully diagnosed, direct-drive, spherical implosion experiments. As such, it serves as the national Laser Users Facility, benefiting scientists throughout the country. The University's participation in the National Inertial Confinement Fusion (ICF) program underwent review by a group of experts under the auspices of the National Academy of Sciences (the Happer Committee) in 1985. The Happer Committee recommended that the OMEGA laser be upgraded in energy to 30 kJ. To this end, Congress appropriated $4,000,000 for the preliminary design of the OMEGA Upgrade, spread across FY88 and FY89. This document describes the preliminary design of the OMEGA Upgrade. The proposed enhancements to the existing OMEGA facility will result in a 30-kHJ, 351-nm, 60-beam direct-drive system, with a versatile pulse-shaping facility and a 1%--2% uniformity of target drive. The Upgrade will allow scientists to explore the ignition-scaling regime, and to study target behavior that is hydrodynamically equivalent to that of targets appropriate for a laboratory microfusion facility (LMF). In addition, it will be possible to perform critical interaction experiments with large-scale-length uniformly irradiated plasmas

  12. Comparison of SBLOCA Test Results with the FESTA Facility for the SMART Design

    Energy Technology Data Exchange (ETDEWEB)

    Ryu, Hyobong; Park, Hyun--Sik; Bae, Hwang; Ryu, Sung-Uk; Ko, Young-Joo; Yi, Sung-Jae [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-10-15

    The FESTA facility is a full height, 1/49-volume scaled test facility with four trains of a secondary system and PRHRS, and can be used to investigate the integral performance of the interconnected components and possible thermal-hydraulic phenomena occurring in the SMART (System-Integrated Modular Advanced Reactor) design, and to validate its safety for various design basis accidents and broad transient scenarios. The role of FESTA can be extended to examine and verify the normal, abnormal, and emergency operating procedures required during the construction phases of SMART. During the design of the FESTA facility, the height is preserved to the full scale, and its area and volume are scaled down to 1/49 compared with the prototype plant, SMART. The scaling ratios adopted in FESTA with respect to SMART are summarized in Table 1. The maximum core power is 2..0 MW, which is about 30% of the scaled full power. The design pressure and temperature of SMART-ITL can simulate the maximum operating conditions, that is, 18.0 MPa and 350 .deg. C. A preliminary analysis of small-break loss of coolant accident (SBLOCA) tests using the MARS/KS code for FESTA was previously conducted. In addition, major test results of SBLOCA scenarios with the VISTA-ITL facility for the SMART design were discussed. In this research, three SBLOCA experimental tests of a safety injection system (SIS) line break, shutdown cooling system (SCS) line break and pressurizer safety valve (PSV) line break for the SMART design were successfully performed and its major results have been compared and discussed. An integral effect test has been performed for the SBLOCA scenario for the SMART design with the FESTA facility.

  13. Basic requirements for a preliminary conceptual design of the Korea advanced pyroprocess facility (KAPF)

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Ho Hee; Ko, Won Il; Chang, Hong Lae; Song, Dae Yong; Kwon, Eun Ha; Lee, Jung Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2008-12-15

    Korea Atomic Energy Research Institute (KAERI) has been developing technologies for pyroprocessing for spent PWR fuels. This study is part of a long term R and D program in Korea to develop an advanced recycle system that has the potential to meet and exceed the proliferation resistance, waste minimization, resource minimization, safety and economic goals of approved Korean Government energy policy, as well as the Generation IV International Forum (GIF) program. To support this R and D program, KAERI requires that an independent estimate be made of the conceptual design and cost for construction and operation of a 'Korea Advanced Pyroprocessing Facility', This document describes the basic requirements for preliminary conceptual design of the Korea Advanced Pyroprocess Facility (KAPF). The presented requirements will be modified to be more effective and feasible on an engineering basis during the subsequent design process.

  14. Basic requirements for a preliminary conceptual design of the Korea advanced pyroprocess facility (KAPF)

    International Nuclear Information System (INIS)

    Lee, Ho Hee; Ko, Won Il; Chang, Hong Lae; Song, Dae Yong; Kwon, Eun Ha; Lee, Jung Won

    2008-12-01

    Korea Atomic Energy Research Institute (KAERI) has been developing technologies for pyroprocessing for spent PWR fuels. This study is part of a long term R and D program in Korea to develop an advanced recycle system that has the potential to meet and exceed the proliferation resistance, waste minimization, resource minimization, safety and economic goals of approved Korean Government energy policy, as well as the Generation IV International Forum (GIF) program. To support this R and D program, KAERI requires that an independent estimate be made of the conceptual design and cost for construction and operation of a 'Korea Advanced Pyroprocessing Facility', This document describes the basic requirements for preliminary conceptual design of the Korea Advanced Pyroprocess Facility (KAPF). The presented requirements will be modified to be more effective and feasible on an engineering basis during the subsequent design process

  15. The preliminary Long Duration Exposure Facility (LDEF) materials data base

    International Nuclear Information System (INIS)

    Funk, J.G.; Strickland, J.W.; Davis, J.M.

    1992-10-01

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

  16. The preliminary Long Duration Exposure Facility (LDEF) materials data base

    Science.gov (United States)

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

    1992-01-01

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

  17. Design aspects of the Alpha Repository. I. Preliminary results of facility layout, room stability, and equipment selection efforts. Summary progress report RSI-0024

    International Nuclear Information System (INIS)

    Gnirk, P.F.; Grams, W.H.; Zeller, T.J.; Ellis, D.B.; Pariseau, W.G.; Fossum, A.F.; Ratigan, J.L.; Hansen, F.D.

    1975-01-01

    Results of preliminary analysis of the stability of mines in salt formations underlying Eddy and Lea Counties in New Mexico are presented. Methods and equipment for drilling canister emplacement holes in these formations were evaluated along with methods for excavating storage areas and transport of the excavated salt. Progress during the period is reported in chapters on geological and rock properties at the repository site, preliminary mine layout, basic requirements for repository usage, excavation geometries, drill selection, excavation systems, and safety requirements

  18. The friction of polymers around Tg,Tm : Preliminary results

    DEFF Research Database (Denmark)

    Sivebæk, Ion Marius; Samoilov, V N; Persson, B N J

    We present Molecular Dynamics calculations involving polymers of different lengths. Polymers with lengths from 20 to 1400 carbon atoms are considered. The systems are able to simulate friction between polymer surfaces and polymer against metal. The results we present are very preliminary and they......We present Molecular Dynamics calculations involving polymers of different lengths. Polymers with lengths from 20 to 1400 carbon atoms are considered. The systems are able to simulate friction between polymer surfaces and polymer against metal. The results we present are very preliminary...

  19. Concerning results of environmental monitoring around the reprocessing facilities of Power Reactor and Nuclear Fuel Development Corporation

    International Nuclear Information System (INIS)

    1989-01-01

    The Central Evaluation Expert Group for Environmental radiation Monitoring has been engaged in examinations of plants for and results of the environmental radiation monitoring performed by Power Reactor and Nuclear Fuel Development Corporation around its reprocessing facilities. The present report outlines an examination of the results of monitoring carried out in 1987 (January to December). It is concluded that the methods used for the monitoring and its technical level are satisfactory in meeting the objectives of the monitoring plans. Expept for tritium in seawater, the level of radiations stays within the normal variation determined based on preliminary measurements of the background radiation. The procedure used for the calculation of exposure dose is also satisfactory in meeting the requirements specified in the monitoring plants. It is confirmed that the exposure dose of the residents around the facilities is well below the permissible exposure dose limite specified in law. (Nogami. K.)

  20. SECONDARY WASTE/ETF (EFFLUENT TREATMENT FACILITY) PRELIMINARY PRE-CONCEPTUAL ENGINEERING STUDY

    International Nuclear Information System (INIS)

    May, T.H.; Gehner, P.D.; Stegen, Gary; Hymas, Jay; Pajunen, A.L.; Sexton, Rich; Ramsey, Amy

    2009-01-01

    This pre-conceptual engineering study is intended to assist in supporting the critical decision (CD) 0 milestone by providing a basis for the justification of mission need (JMN) for the handling and disposal of liquid effluents. The ETF baseline strategy, to accommodate (WTP) requirements, calls for a solidification treatment unit (STU) to be added to the ETF to provide the needed additional processing capability. This STU is to process the ETF evaporator concentrate into a cement-based waste form. The cementitious waste will be cast into blocks for curing, storage, and disposal. Tis pre-conceptual engineering study explores this baseline strategy, in addition to other potential alternatives, for meeting the ETF future mission needs. Within each reviewed case study, a technical and facility description is outlined, along with a preliminary cost analysis and the associated risks and benefits.

  1. French 900 MWe PWR PSA preliminary results

    International Nuclear Information System (INIS)

    Lanore, J.M.; Brisbois, J.

    1988-10-01

    A PSA is performed by the Safety Assessment Department of CEA for a 900 MWe standardized plant. The paper presents the objectives, the scope of the study and the relative preliminary results. Some general insights are drawn, especially the benefit related to the implementation of emergency procedures

  2. Vulnerability Assessments and Resilience Planning at Federal Facilities. Preliminary Synthesis of Project

    Energy Technology Data Exchange (ETDEWEB)

    Moss, R. H. [Pacific Northwest National Lab. (PNNL)/Univ. of Maryland, College Park, MD (United States). Joint Global Change Research Inst.; Blohm, A. J. [Univ. of Maryland, College Park, MD (United States); Delgado, A. [Pacific Northwest National Lab. (PNNL)/Univ. of Maryland, College Park, MD (United States). Joint Global Change Research Inst.; Henriques, J. J. [James Madison Univ., Harrisonburg, VA (United States); Malone, E L. [Pacific Northwest National Lab. (PNNL)/Univ. of Maryland, College Park, MD (United States). Joint Global Change Research Inst.

    2015-08-15

    U.S. government agencies are now directed to assess the vulnerability of their operations and facilities to climate change and to develop adaptation plans to increase their resilience. Specific guidance on methods is still evolving based on the many different available frameworks. Agencies have been experimenting with these frameworks and approaches. This technical paper synthesizes lessons and insights from a series of research case studies conducted by the investigators at facilities of the U.S. Department of Energy and the Department of Defense. The purpose of the paper is to solicit comments and feedback from interested program managers and analysts before final conclusions are published. The paper describes the characteristics of a systematic process for prioritizing needs for adaptation planning at individual facilities and examines requirements and methods needed. It then suggests a framework of steps for vulnerability assessments at Federal facilities and elaborates on three sets of methods required for assessments, regardless of the detailed framework used. In a concluding section, the paper suggests a roadmap to further develop methods to support agencies in preparing for climate change. The case studies point to several preliminary conclusions; (1) Vulnerability assessments are needed to translate potential changes in climate exposure to estimates of impacts and evaluation of their significance for operations and mission attainment, in other words into information that is related to and useful in ongoing planning, management, and decision-making processes; (2) To increase the relevance and utility of vulnerability assessments to site personnel, the assessment process needs to emphasize the characteristics of the site infrastructure, not just climate change; (3) A multi-tiered framework that includes screening, vulnerability assessments at the most vulnerable installations, and adaptation design will efficiently target high-risk sites and infrastructure

  3. Danish Anaesthesia Allergy Centre - preliminary results

    DEFF Research Database (Denmark)

    Garvey, L H; Roed-Petersen, J; Menné, T

    2001-01-01

    BACKGROUND: Anaphylactoid reactions in anaesthesia are rare and should ideally be investigated in specialist centres. At Gentofte University Hospital, we established such a centre in 1998 as a joint venture between the Departments of Anaesthesiology and Dermatology. We present the methodology...... for chlorhexidine. Only one patient has tested positive to a neuromuscular blocking drug (NMBD) so far. DISCUSSION: Our preliminary results appear to differ in two ways from results usually found in this field. Firstly, only one patient has tested positive for a NMBD and secondly, we have had four patients...

  4. A free-piston Stirling engine/linear alternator controls and load interaction test facility

    Science.gov (United States)

    Rauch, Jeffrey S.; Kankam, M. David; Santiago, Walter; Madi, Frank J.

    1992-01-01

    A test facility at LeRC was assembled for evaluating free-piston Stirling engine/linear alternator control options, and interaction with various electrical loads. This facility is based on a 'SPIKE' engine/alternator. The engine/alternator, a multi-purpose load system, a digital computer based load and facility control, and a data acquisition system with both steady-periodic and transient capability are described. Preliminary steady-periodic results are included for several operating modes of a digital AC parasitic load control. Preliminary results on the transient response to switching a resistive AC user load are discussed.

  5. Preliminary hazards analysis -- vitrification process

    Energy Technology Data Exchange (ETDEWEB)

    Coordes, D.; Ruggieri, M.; Russell, J.; TenBrook, W.; Yimbo, P. [Science Applications International Corp., Pleasanton, CA (United States)

    1994-06-01

    This paper presents a Preliminary Hazards Analysis (PHA) for mixed waste vitrification by joule heating. The purpose of performing a PHA is to establish an initial hazard categorization for a DOE nuclear facility and to identify those processes and structures which may have an impact on or be important to safety. The PHA is typically performed during and provides input to project conceptual design. The PHA is then followed by a Preliminary Safety Analysis Report (PSAR) performed during Title 1 and 2 design. The PSAR then leads to performance of the Final Safety Analysis Report performed during the facility`s construction and testing. It should be completed before routine operation of the facility commences. This PHA addresses the first four chapters of the safety analysis process, in accordance with the requirements of DOE Safety Guidelines in SG 830.110. The hazards associated with vitrification processes are evaluated using standard safety analysis methods which include: identification of credible potential hazardous energy sources; identification of preventative features of the facility or system; identification of mitigative features; and analyses of credible hazards. Maximal facility inventories of radioactive and hazardous materials are postulated to evaluate worst case accident consequences. These inventories were based on DOE-STD-1027-92 guidance and the surrogate waste streams defined by Mayberry, et al. Radiological assessments indicate that a facility, depending on the radioactive material inventory, may be an exempt, Category 3, or Category 2 facility. The calculated impacts would result in no significant impact to offsite personnel or the environment. Hazardous materials assessment indicates that a Mixed Waste Vitrification facility will be a Low Hazard facility having minimal impacts to offsite personnel and the environment.

  6. Preliminary test results and CFD analysis for moderator circulation test at Korea

    Energy Technology Data Exchange (ETDEWEB)

    Kim, H.T. [Korea Atomic Energy Research Inst., Daejeon (Korea, Republic of); Im, S.H.; Sung, H.J. [Korea Advanced Inst. of Science and Tech., Daejeon (Korea, Republic of); Seo, H.; Bang, I.C. [Ulsan National Inst. of Science and Tech., Ulsan (Korea, Republic of)

    2014-07-01

    Korea Atomic Energy Research Institute (KAERI) is carrying out a scaled-down moderator test program to simulate the CANDU6 moderator circulation phenomena during steady state operation and accident conditions. This research program includes the construction of the Moderator Circulation Test (MCT) facility, production of the validation data for self-reliant CFD tools, and development of optical measurement system using the Particle Image Velocimetry (PIV). The MCT facility includes a primary circulation loop (pipe lines, a primary side pump, a heat exchanger, valves, flow meters) and a secondary side loop (pipe lines, a secondary side pump, and an external cooling tower). The loop leakage test and non-heating test are performed in the present work. In the present work the PIV technique is used to measure the velocity distributions in the scaled moderator tank of MCT under iso-thermal test conditions. The preliminary PIV measurement data are obtained and compared with CFX code predictions. (author)

  7. Preliminary test results and CFD analysis for moderator circulation test at Korea

    International Nuclear Information System (INIS)

    Kim, H.T.; Im, S.H.; Sung, H.J.; Seo, H.; Bang, I.C.

    2014-01-01

    Korea Atomic Energy Research Institute (KAERI) is carrying out a scaled-down moderator test program to simulate the CANDU6 moderator circulation phenomena during steady state operation and accident conditions. This research program includes the construction of the Moderator Circulation Test (MCT) facility, production of the validation data for self-reliant CFD tools, and development of optical measurement system using the Particle Image Velocimetry (PIV). The MCT facility includes a primary circulation loop (pipe lines, a primary side pump, a heat exchanger, valves, flow meters) and a secondary side loop (pipe lines, a secondary side pump, and an external cooling tower). The loop leakage test and non-heating test are performed in the present work. In the present work the PIV technique is used to measure the velocity distributions in the scaled moderator tank of MCT under iso-thermal test conditions. The preliminary PIV measurement data are obtained and compared with CFX code predictions. (author)

  8. Preliminary physico-chemical results obtained on water using new data acquisition systems for deep wells

    International Nuclear Information System (INIS)

    Vinson, J.M.; Peyrus, J.C.

    1984-02-01

    Data acquisition systems recently developed in the context of research on deep storage facilities have provided with an initial set of interesting observations for the physico-chemical study of boreholes. It is possible to make correlations between the chemical compositions of water, pH and the nature of the substrate. The sampling done at Auriat with a Gerhardt-Owen probe shows the variability in the composition of water as a function of depth. The variation in calcium content, following that of pH, is particularly notable. Examination of pH measurements is of particular interest. A general gradient correlates exactly with the nature of the substrate. Whereas steel piping has a very alkaline pH, distinct pH values correspond to the two types of granite substrate. In this general gradient, series of disturbances can be seen which correspond perfectly to fracturation zones or large fractures. These most promising preliminary results lead to believe that in situ physico-chemical measurements should be continued and developed with a view to improved evaluation of the safety of deep storage facilities

  9. Preliminary Hazard Classification for the 105-B Reactor

    International Nuclear Information System (INIS)

    Kerr, N.R.

    1997-08-01

    This document summarizes the inventories of radioactive and hazardous materials present within the 105-B Reactor and uses the inventory information to determine the preliminary hazard classification for the surveillance and maintenance activities of the facility. The result of this effort was the preliminary hazard classification for the 105-B Building surveillance and maintenance activities. The preliminary hazard classification was determined to be Nuclear Category 3. Additional hazard and accident analysis will be documented in a separate report to define the hazard controls and final hazard classification

  10. Preliminary results from the hierarchical glitch pipeline

    International Nuclear Information System (INIS)

    Mukherjee, Soma

    2007-01-01

    This paper reports on the preliminary results obtained from the hierarchical glitch classification pipeline on LIGO data. The pipeline that has been under construction for the past year is now complete and end-to-end tested. It is ready to generate analysis results on a daily basis. The details of the pipeline, the classification algorithms employed and the results obtained with one days analysis on the gravitational wave and several auxiliary and environmental channels from all three LIGO detectors are discussed

  11. Preliminary hazards analysis -- vitrification process

    International Nuclear Information System (INIS)

    Coordes, D.; Ruggieri, M.; Russell, J.; TenBrook, W.; Yimbo, P.

    1994-06-01

    This paper presents a Preliminary Hazards Analysis (PHA) for mixed waste vitrification by joule heating. The purpose of performing a PHA is to establish an initial hazard categorization for a DOE nuclear facility and to identify those processes and structures which may have an impact on or be important to safety. The PHA is typically performed during and provides input to project conceptual design. The PHA is then followed by a Preliminary Safety Analysis Report (PSAR) performed during Title 1 and 2 design. The PSAR then leads to performance of the Final Safety Analysis Report performed during the facility's construction and testing. It should be completed before routine operation of the facility commences. This PHA addresses the first four chapters of the safety analysis process, in accordance with the requirements of DOE Safety Guidelines in SG 830.110. The hazards associated with vitrification processes are evaluated using standard safety analysis methods which include: identification of credible potential hazardous energy sources; identification of preventative features of the facility or system; identification of mitigative features; and analyses of credible hazards. Maximal facility inventories of radioactive and hazardous materials are postulated to evaluate worst case accident consequences. These inventories were based on DOE-STD-1027-92 guidance and the surrogate waste streams defined by Mayberry, et al. Radiological assessments indicate that a facility, depending on the radioactive material inventory, may be an exempt, Category 3, or Category 2 facility. The calculated impacts would result in no significant impact to offsite personnel or the environment. Hazardous materials assessment indicates that a Mixed Waste Vitrification facility will be a Low Hazard facility having minimal impacts to offsite personnel and the environment

  12. Preliminary design of steam reformer in out-pile demonstration test facility for HTTR heat utilization system

    Energy Technology Data Exchange (ETDEWEB)

    Haga, Katsuhiro; Hino, Ryutaro; Inagaki, Yosiyuki; Hata, Kazuhiko; Aita, Hideki; Sekita, Kenji; Nishihara, Tetsuo; Sudo, Yukio [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment; Yamada, Seiya

    1996-11-01

    One of the key objectives of HTTR is to demonstrate effectiveness of high-temperature nuclear heat utilization system. Prior to connecting a heat utilization system to HTTR, an out-pile demonstration test is indispensable for the development of experimental apparatuses, operational control and safety technology, and verification of the analysis code of safety assessment. For the first heat utilization system of HTTR, design of the hydrogen production system by steam reforming is going on. We have proposed the out-pile demonstration test plan of the heat utilization system and conducted preliminary design of the test facility. In this report, design of the steam reformer, which is the principal component of the test facility, is described. In the course of the design, two types of reformers are considered. The one reformer contains three reactor tubes and the other contains one reactor tube to reduce the construction cost of the test facility. We have selected the steam reformer operational conditions and structural specifications by analyzing the steam reforming characteristics and component structural strength for each type of reformer. (author)

  13. Posiva's application for a decision in principle concerning a disposal facility for spent nuclear fuel. STUK's statement and preliminary safety appraisal

    Energy Technology Data Exchange (ETDEWEB)

    Ruokola, E. [ed.

    2000-03-01

    In May 1999, Posiva Ltd submitted to the Government an application, pursuant to the Nuclear Energy Act, for a Decision in Principle on a disposal facility for spent nuclear fuel from the Finnish nuclear power plants. The Ministry of Trade and Industry requested the Radiation and Nuclear Safety Authority (STUK) to draw up a preliminary safety appraisal concerning the proposed disposal facility. In the beginning of this report, STUK's statement to the Ministry and Industry concerning the proposed disposal facility is given. In that statement, STUK concludes that the Decision in Principle is currently justified from the standpoint of safety. The statement is followed by a safety appraisal, where STUK deems, how the proposed disposal concept, site and facility comply with the safety requirements included in the Government's Decision (478/1999). STUK's preliminary safety appraisal was supported by contributions from a number of outside experts. A collective opinion by an international group of ten distinguished experts is appended to this report. (orig.)

  14. Results of the preliminary radiological survey at the former Diamond Magnesium Company site, Luckey, Ohio (DML001)

    International Nuclear Information System (INIS)

    Foley, R.D.; Crutcher, J.W.

    1990-02-01

    As part of the Formerly Utilized Sites Remedial Action Program, the US Department of Energy (DOE) is implementing a radiological survey program to determine the radiological conditions at sites that were used by the department's predecessor agencies. One such site is the former Diamond Magnesium Company facility in Luckey, Ohio. The preliminary radiological survey discussed in this report was conducted at the request of DOE by members of the Measurement Applications and Development group of Oak Ridge National Laboratory in December 1988. The former Diamond Magnesium Company site in Luckey, Ohio, was used as a magnesium reduction plant during World War 2. It was closed in 1945 and reopened in 1949 as a beryllium production facility, operated by Brush Wellman for the US Atomic Energy Commission. The preliminary radiological survey included: a surface gamma scan of part of the property outdoors, collection of surface and subsurface soil samples, and collection of water samples. Laboratory analysis of soil samples showed concentrations of 226 Ra in excess of applicable DOE guidelines. A follow-up, detailed survey is recommended. 9 refs., 10 figs., 4 tabs

  15. Cognitive Task Analysis of Business Jet Pilots' Weather Flying Behaviors: Preliminary Results

    Science.gov (United States)

    Latorella, Kara; Pliske, Rebecca; Hutton, Robert; Chrenka, Jason

    2001-01-01

    This report presents preliminary findings from a cognitive task analysis (CTA) of business aviation piloting. Results describe challenging weather-related aviation decisions and the information and cues used to support these decisions. Further, these results demonstrate the role of expertise in business aviation decision-making in weather flying, and how weather information is acquired and assessed for reliability. The challenging weather scenarios and novice errors identified in the results provide the basis for experimental scenarios and dependent measures to be used in future flight simulation evaluations of candidate aviation weather information systems. Finally, we analyzed these preliminary results to recommend design and training interventions to improve business aviation decision-making with weather information. The primary objective of this report is to present these preliminary findings and to document the extended CTA methodology used to elicit and represent expert business aviator decision-making with weather information. These preliminary findings will be augmented with results from additional subjects using this methodology. A summary of the complete results, absent the detailed treatment of methodology provided in this report, will be documented in a separate publication.

  16. Preliminary Assessment of Potential Avian Interactions at Four Proposed Wind Energy Facilities on Vandenberg Air Force Base, California

    Energy Technology Data Exchange (ETDEWEB)

    2004-08-01

    The United States Air Force (USAF) is investigating whether to install wind turbines to provide a supplemental source of electricity at Vandenberg Air Force Base (VAFB) near Lompoc, California. As part of that investigation, VAFB sought assistance from the U.S. Department of Energy's National Renewable Energy Laboratory (NREL) to provide a preliminary characterization of the potential risk to wildlife resources (mainly birds and bats) from wind turbine installations. With wind power development expanding throughout North America and Europe, concerns have surfaced over the number of bird fatalities associated with wind turbines. Guidelines developed for the wind industry by the National Wind Coordinating Committee (NWCC) recommend assessing potential impacts to birds, bats, and other potentially sensitive resources before construction. The primary purpose of an assessment is to identify potential conflicts with sensitive resources, to assist developers with identifying their permitting needs, and to develop strategies to avoid impacts or to mitigate their effects. This report provides a preliminary (Phase I) biological assessment of potential impacts to birds and bats that might result from construction and operation of the proposed wind energy facilities on VAFB.

  17. Preliminary results on heavy flavor physics at SLD

    Energy Technology Data Exchange (ETDEWEB)

    Usher, T. [Stanford Univ., CA (United States)

    1994-12-01

    The author reports on preliminary heavy flavor physics results from the SLD detector at the SLAC Linear Collider. Efficient tagging of b{bar b} events is achieved with an impact parameter technique that takes advantage of the small and stable interaction point of the SLC and all charged tracks in Z{sup 0} decays. This technique is applied to samples of Z{sup 0} events collected during the 1992 and 1993 physics runs. Preliminary measurements of the ratio R{sub b} = {Gamma}(Z{sup 0} {yields} b{bar b})/{Gamma}(Z{sup 0} {yields} hadrons) and the average B hadron lifetime <{tau}{sub B}> are reported. In a sample of 27K Z{sup 0} events, values of R{sub b} = 0.235 {+-} 0.006(stat.) {+-} 0.018(syst.) and <{tau}{sub B}> = 1.53 {+-} 0.006(stat.) {+-} 0.018(syst.) are obtained. In addition, the first measurement of the left-right asymmetry A{sub b} is reported. Using a sample of 38K Z{sup 0} events with a luminosity weighted electron polarization of 62%, the author obtains a preliminary value of A{sub b} = 0.94 {+-} 0.006(stat.) {+-} 0.018(syst.).

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

    International Nuclear Information System (INIS)

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

    1988-02-01

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

  19. The neutral beam test facility cryopumping operation: preliminary analysis and design of the cryogenic system

    International Nuclear Information System (INIS)

    Gravil, B.; Henry, D.; Cordier, J.J.; Hemsworth, R.; Van Houtte, D.

    2004-01-01

    The ITER neutral beam heating and current drive system is to be equipped with a cryosorption cryopump made up of 12 panels connected in parallel, refrigerated by 4.5 K 0.4 MPa supercritical helium. The pump is submitted to a non homogeneous flux of H 2 or D 2 molecules, and the absorbed flux varies from 3 Pa.m -3 .s -1 to 35 Pa.m -3 .s -1 . In the frame of the 'ITER first injector and test facility CSU-EFDA task' (TW3-THHN-IITF1), the ITER reference cryo-system and cryo-plant designs have been assessed and compared to optimised designs devoted to the Neutral Beam Test Facility (NBTF). The 4.5 K cryo-panel, which has a mass of about 1000 kg, must be periodically regenerated up to 90 K and occasionally to 470 K. The cool-down time after regeneration depends strongly on the refrigeration capacity. Fast regeneration and cool-down of the cryo-panels are not considered a priority for the test facility operation, and an analysis of the consequences of a limited cold power refrigerator on the cooling down time has been carried out and will be discussed. This paper presents a preliminary evaluation of the NBTF cryo-plant and the associated process flow diagram. (authors)

  20. Preliminary results from film boiling destabilisation experiments

    International Nuclear Information System (INIS)

    Naylor, P.

    1984-05-01

    A series of experiments to investigate the triggered destabilisation of film boiling has been undertaken. Film boiling was established on a polished brass rod immersed in water and the effects of various triggers were investigated. Preliminary results are presented and two thresholds have been observed: an impulse threshold below which triggered destabilisation will not occur and a thermal threshold above which film boiling will re-establish following triggered destabilisation. (author)

  1. Test results with the Transrapid 06. System data from preliminary trials

    Energy Technology Data Exchange (ETDEWEB)

    Heinrich, K; Mnich, P

    1987-10-01

    Following the takeover of the Transrapid maglev facility by MVP, in spite of remaining preparatory work and conversion of the support and guidance system on the basis of a new electronic generation, interesting system data could be obtained experimentally before the planned continuous trials phase. Although the full test track length is not yet available - it is at present only 20.5 km - more than 25,000 km have already been covered in almost 1,200 test runs. Some 200 of these were for the purpose of demonstrating the Transrapid technology to visting German and foreign experts. The system data obtained from the preliminary trails were positive. Any weak points noted were mainly site-specific and not maglev-specific, but in spite of generally satisfactory results there are still many individual aspects calling for improvement and optimation before the technology can be declared ready for service. Proceeding from the positive trend of the system data obtained at up to 355 km/h, it can be said that proof of serviceability of the Transrapid transport system at speeds of up to 400 km/h can be provided in the next two years. (orig.).

  2. Iron in hereditary retinal degeneration: PIXE microanalysis Preliminary results

    International Nuclear Information System (INIS)

    Sergeant, C.; Gouget, B.; Llabador, Y.; Simonoff, M.; Yefimova, M.; Courtois, Y.; Jeanny, J.C.

    1999-01-01

    Several types of hereditary retinal degeneration with progressive alteration of photoreceptors exist in men and animals. Recent immunohistochemical results have shown strong degradation of transferrin, the protein responsible for iron transport, in retinas of rats with hereditary retinal degeneration. Freeze-dried thin sections of rat retinas from different stages of the disease, and respective coeval control sections, have been analyzed using nuclear microprobe. In this first part of the study, the rat retinas at post-natal stages of 35 and 45 days have been analyzed. The sample preparation and the post-irradiation staining to determine precisely the retinal layers involved are described. Preliminary results of element distributions (K, Ca, Fe) in the rat retina layers are discussed. A very high content of calcium in the choriocapillaris of dystrophic rat retinas was observed. Preliminary results on iron distribution in the rat retina layers are presented

  3. Preliminary results of the Adone storage ring FEL experiment, LELA

    International Nuclear Information System (INIS)

    Barbini, R.; Vignola, G.; Trillo, S.

    1983-01-01

    A short description of the LELA (Free Electron Laser on Adone) experiment is given. Results on the spontaneous radiation angle and energy spectra and preliminary results on optical gain measurements are also discussed

  4. Laser heated solenoid proof-of-concept experiment (PCX) facility

    International Nuclear Information System (INIS)

    DeHart, T.E.; Zumdieck, J.F.; Hoffman, A.L.; Lowenthal, D.D.; Crawford, E.A.; Parry, B.

    1977-01-01

    The total facility, including laser, magnet, focusing optics, instrumentation and control, its design problems, and its current performance are discussed. Preliminary results from plasma heating experiments are discussed

  5. Experience base for Radioactive Waste Thermal Processing Systems: A preliminary survey

    International Nuclear Information System (INIS)

    Mayberry, J.; Geimer, R.; Gillins, R.; Steverson, E.M.; Dalton, D.; Anderson, G.L.

    1992-04-01

    In the process of considering thermal technologies for potential treatment of the Idaho National Engineering Laboratory mixed transuranic contaminated wastes, a preliminary survey of the experience base available from Radioactive Waste Thermal Processing Systems is reported. A list of known commercial radioactive waste facilities in the United States and some international thermal treatment facilities are provided. Survey focus is upon the US Department of Energy thermal treatment facilities. A brief facility description and a preliminary summary of facility status, and problems experienced is provided for a selected subset of the DOE facilities

  6. Preliminary results of testing bioassay analytical performance standards

    International Nuclear Information System (INIS)

    Fisher, D.R.; Robinson, A.V.; Hadley, R.T.

    1983-08-01

    The analytical performance of both in vivo and in vitro bioassay laboratories is being studied to determine the capability of these laboratories to meet the minimum criteria for accuracy and precision specified in the draft ANSI Standard N13.30, Performance Criteria for Radiobioassay. This paper presents preliminary results of the first round of testing

  7. Preliminary Analysis of the Transient Reactor Test Facility (TREAT) with PROTEUS

    Energy Technology Data Exchange (ETDEWEB)

    Connaway, H. M. [Argonne National Lab. (ANL), Argonne, IL (United States); Lee, C. H. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2015-11-30

    The neutron transport code PROTEUS has been used to perform preliminary simulations of the Transient Reactor Test Facility (TREAT). TREAT is an experimental reactor designed for the testing of nuclear fuels and other materials under transient conditions. It operated from 1959 to 1994, when it was placed on non-operational standby. The restart of TREAT to support the U.S. Department of Energy’s resumption of transient testing is currently underway. Both single assembly and assembly-homogenized full core models have been evaluated. Simulations were performed using a historic set of WIMS-ANL-generated cross-sections as well as a new set of Serpent-generated cross-sections. To support this work, further analyses were also performed using additional codes in order to investigate particular aspects of TREAT modeling. DIF3D and the Monte-Carlo codes MCNP and Serpent were utilized in these studies. MCNP and Serpent were used to evaluate the effect of geometry homogenization on the simulation results and to support code-to-code comparisons. New meshes for the PROTEUS simulations were created using the CUBIT toolkit, with additional meshes generated via conversion of selected DIF3D models to support code-to-code verifications. All current analyses have focused on code-to-code verifications, with additional verification and validation studies planned. The analysis of TREAT with PROTEUS-SN is an ongoing project. This report documents the studies that have been performed thus far, and highlights key challenges to address in future work.

  8. 33 CFR 127.315 - Preliminary transfer inspection.

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) WATERFRONT FACILITIES WATERFRONT FACILITIES HANDLING LIQUEFIED NATURAL GAS AND LIQUEFIED HAZARDOUS GAS Waterfront Facilities Handling Liquefied Natural Gas Operations § 127.315 Preliminary transfer... parts; (b) For each of the vessel's cargo tanks from which cargo will be transferred, note the pressure...

  9. Scope and purpose of the preliminary planning work

    International Nuclear Information System (INIS)

    Kalas, P.

    1976-01-01

    The results of preliminary planning work are usually expressed in a number of recommendations covering mainly: long-term national policy in the field of energy resources and selection of projects to be further studied at the feasibility level. Moreover, recommendations on further actions are made including: inventory of generation and transmission facilities recommended for the implementation in order to meet the load forecasted for medium-term period, preparation of a preliminary calender of decisions to be taken for the implementation of the projects recommended, preparation of a preliminary construction schedule, preparation of a preliminary investment program, preparation of a program of necessary engineering works, and performance of study on electricity rates which would adjust existing tariffs to proposed development program of the utility. (HP) [de

  10. 33 CFR 127.1315 - Preliminary transfer inspection.

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) WATERFRONT FACILITIES WATERFRONT FACILITIES HANDLING LIQUEFIED NATURAL GAS AND LIQUEFIED HAZARDOUS GAS Waterfront Facilities Handling Liquefied Hazardous Gas Operations § 127.1315 Preliminary... capacity of each storage tank to or from which LHG will be transferred, to ensure that it is safe for...

  11. Preliminary Design of the AEGIS Test Facility

    CERN Document Server

    Dassa, Luca; Cambiaghi, Danilo

    2010-01-01

    The AEGIS experiment is expected to be installed at the CERN Antiproton Decelerator in a very close future, since the main goal of the AEGIS experiment is the measurement of gravity impact on antihydrogen, which will be produced on the purpose. Antihydrogen production implies very challenging environmental conditions: at the heart of the AEGIS facility 50 mK temperature, 1e-12 mbar pressure and a 1 T magnetic field are required. Interfacing extreme cryogenics with ultra high vacuum will affect very strongly the design of the whole facility, requiring a very careful mechanical design. This paper presents an overview of the actual design of the AEGIS experimental facility, paying special care to mechanical aspects. Each subsystem of the facility – ranging from the positron source to the recombination region and the measurement region – will be shortly described. The ultra cold region, which is the most critical with respect to the antihydrogen formation, will be dealt in detail. The assembly procedures will...

  12. East Area Irradiation Test Facility: Preliminary FLUKA calculations

    CERN Document Server

    Lebbos, E; Calviani, M; Gatignon, L; Glaser, M; Moll, M; CERN. Geneva. ATS Department

    2011-01-01

    In the framework of the Radiation to Electronics (R2E) mitigation project, the testing of electronic equipment in a radiation field similar to the one occurring in the LHC tunnel and shielded areas to study its sensitivity to single even upsets (SEU) is one of the main topics. Adequate irradiation test facilities are therefore required, and one installation is under consideration in the framework of the PS East area renovation activity. FLUKA Monte Carlo calculations were performed in order to estimate the radiation field which could be obtained in a mixed field facility using the slowly extracted 24 GeV/c proton beam from the PS. The prompt ambient dose equivalent as well as the equivalent residual dose rate after operation was also studied and results of simulations are presented in this report.

  13. The mixed waste management facility

    International Nuclear Information System (INIS)

    Streit, R.D.

    1995-10-01

    During FY96, the Mixed Waste Management Facility (MWMF) Project has the following major objectives: (1) Complete Project Preliminary Design Review (PDR). (2) Complete final design (Title II) of MWMF major systems. (3) Coordinate all final interfaces with the Decontamination and Waste Treatment Facility (DWTF) for facility utilities and facility integration. (4) Begin long-lead procurements. (5) Issue Project Baseline Revision 2-Preliminary Design (PB2), modifying previous baselines per DOE-requested budget profiles and cost reduction. Delete Mediated Electrochemical Oxidation (MEO) as a treatment process for initial demonstration. (6) Complete submittal of, and ongoing support for, applications for air permit. (7) Begin detailed planning for start-up, activation, and operational interfaces with the Laboratory's Hazardous Waste Management Division (HWM). In achieving these objectives during FY96, the Project will incorporate and implement recent DOE directives to maximize the cost savings associated with the DWTF/MWMF integration (initiated in PB1.2); to reduce FY96 new Budget Authority to ∼$10M (reduced from FY97 Validation of $15.3M); and to keep Project fiscal year funding requirements largely uniform at ∼$10M/yr. A revised Project Baseline (i.e., PB2), to be issued during the second quarter of FY96, will address the implementation and impact of this guidance from an overall Project viewpoint. For FY96, the impact of this guidance is that completion of final design has been delayed relative to previous baselines (resulting from the delay in the completion of preliminary design); ramp-up in staffing has been essentially eliminated; and procurements have been balanced through the Project to help balance budget needs to funding availability

  14. Status of ANSI standards on decommissioning of nuclear reprocessing facilities

    International Nuclear Information System (INIS)

    Graham, H.B.

    1975-01-01

    A definition of decommissioning is given, and the preparation of ANSI Standard, ''General Design Criteria for Nuclear Reprocessing Facilities'' (N101.3) is discussed. A Eurochemic report, entitled ''The Shutdown of Reprocessing Facilities--Results of Preliminary Studies on the Installations Belonging to Eurochemic,'' was used in the preparation of this standard. (U.S.)

  15. Preliminary test results from a telescope of Hughes pixel arrays at FNAL

    International Nuclear Information System (INIS)

    Jernigan, J.G.; Arens, J.; Vezie, D.; Collins, T.; Krider, J.; Skubic, P.

    1992-09-01

    In December of 1991 three silicon hybrid pixel detectors each having 2.56 x 2.56 pixels 30 μm square, made by the Hughes Aircraft Company, were placed in a high energy muon beam at the Fermi National Accelerator Laboratory. Straight tracks were recorded in these detectors at angles to the normal to the plane of the silicon ranging from 0 to 45 degrees. In this note, preliminary results are presented on the straight through tracks, i.e., those passing through the telescope at normal incidence. Pulse height data, signal-to-noise data, and preliminary straight line fits to the data resulting in residual distributions are presented. Preliminary calculations show spatial resolution of less than 5 μm in two dimensions

  16. Preliminary Hazards Analysis Plasma Hearth Process

    International Nuclear Information System (INIS)

    Aycock, M.; Coordes, D.; Russell, J.; TenBrook, W.; Yimbo, P.

    1993-11-01

    This Preliminary Hazards Analysis (PHA) for the Plasma Hearth Process (PHP) follows the requirements of United States Department of Energy (DOE) Order 5480.23 (DOE, 1992a), DOE Order 5480.21 (DOE, 1991d), DOE Order 5480.22 (DOE, 1992c), DOE Order 5481.1B (DOE, 1986), and the guidance provided in DOE Standards DOE-STD-1027-92 (DOE, 1992b). Consideration is given to ft proposed regulations published as 10 CFR 830 (DOE, 1993) and DOE Safety Guide SG 830.110 (DOE, 1992b). The purpose of performing a PRA is to establish an initial hazard categorization for a DOE nuclear facility and to identify those processes and structures which may have an impact on or be important to safety. The PHA is typically performed during and provides input to project conceptual design. The PRA then is followed by a Preliminary Safety Analysis Report (PSAR) performed during Title I and II design. This PSAR then leads to performance of the Final Safety Analysis Report performed during construction, testing, and acceptance and completed before routine operation. Radiological assessments indicate that a PHP facility, depending on the radioactive material inventory, may be an exempt, Category 3, or Category 2 facility. The calculated impacts would result in no significant impact to offsite personnel or the environment. Hazardous material assessments indicate that a PHP facility will be a Low Hazard facility having no significant impacts either onsite or offsite to personnel and the environment

  17. Preliminary design of a Tandem-Mirror-Next-Step facility

    International Nuclear Information System (INIS)

    Damm, C.C.; Doggett, J.N.; Bulmer, R.H.

    1980-01-01

    The Tandem-Mirror-Next-Step (TMNS) facility is designed to demonstrate the engineering feasibility of a tandem-mirror reactor. The facility is based on a deuterium-tritium (D-T) burning, tandem-mirror device with a fusion power output of 245 MW. The fusion power density in the central cell is 2.1 MW/m 3 , with a resultant neutron wall loading of 0.5 MW/m 2 . Overall machine length is 116 m, and the effective central-cell length is 50.9 m. The magnet system includes end cells with yin-yang magnets to provide magnetohydrodynamic (MHD) stability and thermal-barrier cells to help achieve a plasma Q of 4.7 (where Q = fusion power/injected power). Neutral beams at energies up to 200 keV are used for plasma heating, fueling, and barrier pumping. Electron cyclotron resonant heating at 50 and 100 GHz is used to control the electron temperature in the barriers. Based on the resulting engineering design, the overall cost of the facility is estimated to be just under $1 billion. Unresolved physics issues include central-cell β-limits against MHD ballooning modes (the assumed reference value of β exceeds the current theory-derived limit), and the removal of thermalized α-particles from the plasma

  18. Connecticut Transit (CTTRANSIT) Fuel Cell Transit Bus: Preliminary Evaluation Results

    Energy Technology Data Exchange (ETDEWEB)

    Chandler, K.; Eudy, L.

    2008-10-01

    This report provides preliminary results from a National Renewable Energy Laboratory evaluation of a protoptye fuel cell transit bus operating at Connecticut Transit in Hartford. Included are descriptions of the planned fuel cell bus demonstration and equipment; early results and agency experience are also provided.

  19. Preliminary results of a PWA of the centrally produced {phi}{phi} system

    Energy Technology Data Exchange (ETDEWEB)

    Marco A. Reyes et al.

    2001-11-02

    The authors present preliminary results of a Partial Wave Analysis of the centrally produced {phi}{phi} system at 800 GeV/c in the reaction pp {yields} p{sub slow} ({phi}{phi})p{sub fast}. The preliminary results with one and two M = 0 waves, indicate that most of the cross section can be described by two waves, with J{sup PC} LS{sup {eta}} = 2{sup 2}02{sup -1}, 0{sup 2}00{sup -1}.

  20. DRY TRANSFER FACILITY SEISMIC ANALYSIS

    International Nuclear Information System (INIS)

    EARNEST, S.; KO, H.; DOCKERY, W.; PERNISI, R.

    2004-01-01

    The purpose of this calculation is to perform a dynamic and static analysis on the Dry Transfer Facility, and to determine the response spectra seismic forces for the design basis ground motions. The resulting seismic forces and accelerations will be used in a subsequent calculation to complete preliminary design of the concrete shear walls, diaphragms, and basemat

  1. Preliminary Safety Analysis Report for the Tokamak Physics Experiment

    International Nuclear Information System (INIS)

    Motloch, C.G.; Bonney, R.F.; Levine, J.D.; Masson, L.S.; Commander, J.C.

    1995-04-01

    This Preliminary Safety Analysis Report (PSAR), includes an indication of the magnitude of facility hazards, complexity of facility operations, and the stage of the facility life-cycle. It presents the results of safety analyses, safety assurance programs, identified vulnerabilities, compensatory measures, and, in general, the rationale describing why the Tokamak Physics Experiment (TPX) can be safely operated. It discusses application of the graded approach to the TPX safety analysis, including the basis for using Department of Energy (DOE) Order 5480.23 and DOE-STD-3009-94 in the development of the PSAR

  2. Danish Anaesthesia Allergy Centre - preliminary results

    DEFF Research Database (Denmark)

    Garvey, L H; Roed-Petersen, J; Menné, T

    2001-01-01

    BACKGROUND: Anaphylactoid reactions in anaesthesia are rare and should ideally be investigated in specialist centres. At Gentofte University Hospital, we established such a centre in 1998 as a joint venture between the Departments of Anaesthesiology and Dermatology. We present the methodology...... of in vitro testing and skin testing. Blood samples for tryptase analysis are taken at the time of reaction and a control sample is taken together with samples for specific IgE analysis 2-4 weeks after the reaction. Subsequent skin testing comprises both prick tests and intradermal tests in most cases...... for chlorhexidine. Only one patient has tested positive to a neuromuscular blocking drug (NMBD) so far. DISCUSSION: Our preliminary results appear to differ in two ways from results usually found in this field. Firstly, only one patient has tested positive for a NMBD and secondly, we have had four patients...

  3. Safeguardability of a commercial-scaled ACP facility

    Energy Technology Data Exchange (ETDEWEB)

    Ko, Won Il; Lee, S. Y.; Kim, H. D.; Ha, J. H.; Song, D. Y.; Lee, T. H

    2004-07-01

    The Advanced spent fuel Conditioning Process (ACP) is an electro-metallurgical treatment technique to convert oxide-type spent nuclear fuel into a metallic form. This report documents a preliminary study on the safeguardability of ACP. The sub-processes and material flow of the pilot scale ACP facility were designed for this study. Then, their Material Balance Areas (MBA) and Key Measurement Point (KMP) were defined based on diversion scenario analysis. Finally, the limit of error in the MUF value was estimated using international target values for the uncertainty of measurement methods. Based on the results of preliminary study, we concluded that the safeguards goals of International Atomic Energy Agency (IAEA) could be met if the assumptions regarding measurement instruments can be achieved in a safeguards system for the ACP facility.

  4. Safeguardability of a commercial-scaled ACP facility

    International Nuclear Information System (INIS)

    Ko, Won Il; Lee, S. Y.; Kim, H. D.; Ha, J. H.; Song, D. Y.; Lee, T. H.

    2004-07-01

    The Advanced spent fuel Conditioning Process (ACP) is an electro-metallurgical treatment technique to convert oxide-type spent nuclear fuel into a metallic form. This report documents a preliminary study on the safeguardability of ACP. The sub-processes and material flow of the pilot scale ACP facility were designed for this study. Then, their Material Balance Areas (MBA) and Key Measurement Point (KMP) were defined based on diversion scenario analysis. Finally, the limit of error in the MUF value was estimated using international target values for the uncertainty of measurement methods. Based on the results of preliminary study, we concluded that the safeguards goals of International Atomic Energy Agency (IAEA) could be met if the assumptions regarding measurement instruments can be achieved in a safeguards system for the ACP facility

  5. King County Metro Battery Electric Bus Demonstration: Preliminary Project Results

    Energy Technology Data Exchange (ETDEWEB)

    2017-05-22

    The U.S. Federal Transit Administration (FTA) funds a variety of research projects that support the commercialization of zero-emission bus technology. To evaluate projects funded through these programs, FTA has enlisted the help of the National Renewable Energy Laboratory (NREL) to conduct third-party evaluations of the technologies deployed under the FTA programs. NREL works with the selected agencies to evaluate the performance of the zero-emission buses compared to baseline conventional buses in similar service. The evaluation effort will advance the knowledge base of zero-emission technologies in transit bus applications and provide 'lessons learned' to aid other fleets in incrementally introducing next generation zero-emission buses into their operations. This report provides preliminary performance evaluation results from a demonstration of three zero-emission battery electric buses at King County Metro in King County, Washington. NREL developed this preliminary results report to quickly disseminate evaluation results to stakeholders. Detailed evaluation results will be published in future reports.

  6. Structural investigations of biogenic iron oxide samples. Preliminary results

    International Nuclear Information System (INIS)

    Balasoiu, M.; Kuklin, A.I.; Orelovich, O.L.; Kovalev, Yu.S.; Arzumanyan, G.M.; Kurkin, T.S.; Stolyar, S.V.; Iskhakov, R.S.; Rajkher, Yu.L.

    2008-01-01

    Some preliminary results on morphology and structure of iron oxide particles formed inside Klebsiella oxytoca bacteria are presented. In particular, by means of optical microscopy, scanning electron microscopy and small-angle X-ray scattering the effect of the bacteria age (the duration of growth) on the nanoparticles properties is studied

  7. A comparison of goniophotometric measurement facilities

    DEFF Research Database (Denmark)

    Thorseth, Anders; Lindén, Johannes; Dam-Hansen, Carsten

    2016-01-01

    In this paper, we present the preliminary results of a comparison between widely different goniophotometric and goniospectroradiometric measurement facilities. The objective of the comparison is to increase consistency and clarify the capabilities among Danish test laboratories. The study will seek...... to find the degree of equivalence between the various facilities and methods. The collected data is compared by using a three-way variation of principal component analysis, which is well suited for modelling large sets of correlated data. This method drastically decreases the number of numerical values...

  8. The PANDA facility and first test results

    International Nuclear Information System (INIS)

    Dreier, J.; Huggenberger, M.; Aubert, C.; Bandurski, T.; Fischer, O.; Healzer, J.; Lomperski, S.; Strassberger, H.J.; Varadi, G.; Yadigaroglu, G.

    1996-01-01

    The PANDA test facility at the Paul Scherrer Institute is used to study the long-term performance of the Simplified Boiling Water Reactor's passive containment cooling system. The PANDA tests demonstrate performance on a larger scale than previous tests and examine the effects of any non-uniform spatial distributions of steam and non-condensable gases in the system. The facility is in 1:1 vertical scale and 1:25 scale for volume, power etc. Extensive facility characterization tests and steady-state passive containment condenser performance tests are presented. The results of the base case test of a series of transient system behaviour tests are reviewed. The first PANDA tests exhibited reproducibility, and indicated that the Simplified Boiling Water Reactor's containment is likely to be favorably responsive and highly robust to changes in the thermal transport patterns. (orig.) [de

  9. Alternative cask maintenance facility concepts

    International Nuclear Information System (INIS)

    Attaway, C.R.; Pope, R.B.; Wiliamson, A.C.; Medley, L.G.; Shappert, L.B.

    1992-01-01

    In this paper, the results of three trade-off studies of alternative concepts for performing cask maintenance for Civilian Radioactive Waste Management System casks are presented. An earlier study resulted in a recommendation that a submerged pool concept for cask internal component removal be used in the design of a Cask Maintenance Facility. The first trade-off study resulted in confirming the previous recommendation that a submerged pool concept be used rather than an isolation cell; the basis for this continued recommendation is discussed. The second study provides an evaluation of the previously proposed facility for the capability of handling an increased quantity of OCRWM casks. The third study provides a preliminary concept for adding the capability to repaint the exterior cylindrical portions of casks

  10. Preliminary results of statistical dynamic experiments on a heat exchanger

    International Nuclear Information System (INIS)

    Corran, E.R.; Cummins, J.D.

    1962-10-01

    The inherent noise signals present in a heat exchanger have been recorded and analysed in order to determine some of the statistical dynamic characteristics of the heat exchanger. These preliminary results show that the primary side temperature frequency response may be determined by analysing the inherent noise. The secondary side temperature frequency response and cross coupled temperature frequency responses between primary and secondary are poorly determined because of the presence of a non-stationary noise source in the secondary circuit of this heat exchanger. This may be overcome by correlating the dependent variables with an externally applied noise signal. Some preliminary experiments with an externally applied random telegraph type of signal are reported. (author)

  11. Preliminary result and upgrade from WISPDMX Phase II

    Energy Technology Data Exchange (ETDEWEB)

    Nguyen, Le Hoang; Horns, Dieter [Institut fur Experimentalphysik, Universitat Hamburg (Germany); Lobanov, Andrei [Institut fur Experimentalphysik, Universitat Hamburg (Germany); Max-Planck-Institut fur Radioastronomie, Bonn (Germany)

    2016-07-01

    The microwave cavity experiment WISPDMX is the first direct WISP (Weakly interactive slim particles) dark matter search experiment probing the particle masses in the 0.8-2.0 eV range. The first stage of WISPDMX measurements has been completed at nominal resonant frequencies of the cavity. The upgrading of the data acquisition and analysing has been done to increase the sensitivity of the experiment. We report preliminary result from the cavity tuning at second stage of WISPDMX.

  12. Study of fast reactor safety test facilities. Preliminary report

    International Nuclear Information System (INIS)

    Bell, G.I.; Boudreau, J.E.; McLaughlin, T.; Palmer, R.G.; Starkovich, V.; Stein, W.E.; Stevenson, M.G.; Yarnell, Y.L.

    1975-05-01

    Included are sections dealing with the following topics: (1) perspective and philosophy of fast reactor safety analysis; (2) status of accident analysis and experimental needs; (3) experiment and facility definitions; (4) existing in-pile facilities; (5) new facility options; and (6) data acquisition methods

  13. Preliminary results with a strip ionization chamber used as beam monitor for hadrontherapy treatments

    Energy Technology Data Exchange (ETDEWEB)

    Boriano, A. [Dipartimento di Fisica Sperimentale e INFN, Via P.Giuria 1, 1-10125 Turin (Italy); Bourhaleb, F. [Fondazione TERA, Via Puccini 1, 1-28100 Novara (Italy); Cirio, R. [Dipartimento di Fisica Sperimentale e INFN, Via P.Giuria 1, 1-10125 Turin (Italy)] (and others)

    2006-01-15

    Preliminary results are presented from a test of a parallel plate ionization chamber with the anode segmented in strips (MOPI) to be used as a beam monitor for therapeutical treatments on the 62 MeV proton beam line of the INFN-LNS Superconducting Cyclotron. Ocular pathologies have been treated at the Catana facility since March 2002. The detector, placed downstream of the patient collimator, will allow the measurement of the relevant beam diagnostic parameters during treatment such as integrated beam fluence, for dose determination; the beam baricentre, width and asymmetry will be obtained from the fluence profile sampled with a resolution of about 100 Urn at a rate up to 1 kHz with no dead time. In this test, carried out at LNS, the detector has been exposed to different beam shapes and the integrated fluence derived by the measured beam profiles has been compared with that obtained with other dosimeters normally used for treatment. The skewness of the beam profile has been measured and shown to be suitable to on-line check variations of the beam shape.

  14. Preliminary results with a strip ionization chamber used as beam monitor for hadrontherapy treatments

    International Nuclear Information System (INIS)

    Boriano, A.; Bourhaleb, F.; Cirio, R.

    2006-01-01

    Preliminary results are presented from a test of a parallel plate ionization chamber with the anode segmented in strips (MOPI) to be used as a beam monitor for therapeutical treatments on the 62 MeV proton beam line of the INFN-LNS Superconducting Cyclotron. Ocular pathologies have been treated at the Catana facility since March 2002. The detector, placed downstream of the patient collimator, will allow the measurement of the relevant beam diagnostic parameters during treatment such as integrated beam fluence, for dose determination; the beam baricentre, width and asymmetry will be obtained from the fluence profile sampled with a resolution of about 100 Urn at a rate up to 1 kHz with no dead time. In this test, carried out at LNS, the detector has been exposed to different beam shapes and the integrated fluence derived by the measured beam profiles has been compared with that obtained with other dosimeters normally used for treatment. The skewness of the beam profile has been measured and shown to be suitable to on-line check variations of the beam shape

  15. Preliminary results with a strip ionization chamber used as beam monitor for hadrontherapy treatments

    Science.gov (United States)

    Boriano, A.; Bourhaleb, F.; Cirio, R.; Cirrone, G. A. P.; Cuttone, G.; Donetti, M.; Garelli, E.; Giordanengo, S.; Luparia, A.; Marchette, F.; Peroni, C.; Raffaele, L.; Sabini, M. G.; Valastro, L.

    2006-01-01

    Preliminary results are presented from a test of a parallel plate ionization chamber with the anode segmented in strips (MOPI) to be used as a beam monitor for therapeutical treatments on the 62 MeV proton beam line of the INFN-LNS Superconducting Cyclotron. Ocular pathologies have been treated at the Catana facility since March 2002. The detector, placed downstream of the patient collimator, will allow the measurement of the relevant beam diagnostic parameters during treatment such as integrated beam fluence, for dose determination; the beam baricentre, width and asymmetry will be obtained from the fluence profile sampled with a resolution of about 100 Urn at a rate up to 1 kHz with no dead time. In this test, carried out at LNS, the detector has been exposed to different beam shapes and the integrated fluence derived by the measured beam profiles has been compared with that obtained with other dosimeters normally used for treatment. The skewness of the beam profile has been measured and shown to be suitable to on-line check variations of the beam shape.

  16. 1ST-TRIMESTER SCREENING FOR FETAL CHROMOSOMAL-ABNORMALITIES - PRELIMINARY-RESULTS

    NARCIS (Netherlands)

    VANLITH, JMM

    We have started a multicentre trial to study the possibilities of first-trimester maternal serum screening for fetal chromosomal abnormalities. Maternal blood samples were obtained before 13 weeks of gestation. We present the preliminary results of the first 950 patients on alpha-fetoprotein (AFP).

  17. Preliminary results of neutron production in Sahand plasma focus device

    International Nuclear Information System (INIS)

    Siahpoush, V.; Mohammadi, M.A.; Khorram, S.; Shabani, I.; Borhanian, J.; Ashrafi, S.; Naghshara, H.; Moslehi-Fard, M.; Sobhanian, S.

    2004-01-01

    We report in this paper the preliminary results of neutron generation during fusion reaction in deuterium in the Sahand Filipov type plasma focus, recently installed and put in operation at Tabriz University. The special calibration procedure for neutron detection system, using activation method is described

  18. Preliminary Results of the Louisiana Sex Offender Treatment Program

    Directory of Open Access Journals (Sweden)

    Lee A. Underwood

    2015-12-01

    Full Text Available The purpose of this study was to offer preliminary support for the Louisiana Sex Offender Treatment Program (LSOTP in addressing the needs of juvenile sex offenders. Research objectives were (1 to offer statistical evidence for reductions in anxiety, depression, cognitive distortion and negative attitudes towards women comparing a group of 21 adolescents, 12 of whom received services as usual and nine of whom participated in the LSOTP. A controlled experimental evaluation design was utilized. The juvenile sex offenders were randomly assigned to the experimental group for 12 weeks receiving treatment services and a control group receiving care “as usual” in a residential group care program. Participants in the experimental group experienced statistically significant decreases in cognitive distortions related specifically to rape and molestation.The results of this study offer preliminary support of the LSOTP as a best practices alternative to other treatment modalities.

  19. The JCO criticality accident at Tokai-mura, Japan: an overview of the sampling campaign and preliminary results

    International Nuclear Information System (INIS)

    Komura, K.; Yamamoto, M.; Muroyama, T.; Murata, Y.; Nakanishi, T.; Hoshi, M.; Takada, J.; Ishikawa, M.; Takeoka, S.; Kitagawa, K.; Suga, S.; Endo, S.; Tosaki, N.; Mitsugashira, T.; Hara, M.; Hashimoto, T.; Takano, M.; Yanagawa, Y.; Tsuboi, T.; Ichimasa, M.; Ichimasa, Y.; Imura, H.; Sasajima, E.; Seki, R.; Saito, Y.; Kondo, M.; Kojima, S.; Muramatsu, Y.; Yoshida, S.; Shibata, S.; Yonehara, H.; Watanabe, Y.; Kimura, S.; Shiraishi, K.; Ban-nai, T.; Sahoo, S.K.; Igarashi, Y.; Aoyama, M.; Hirose, K.; Uehiro, T.; Doi, T.; Tanaka, A.; Matsuzawa, T.

    2000-01-01

    A criticality accident occurred on September 30, 1999 at the uranium conversion facility of the JCO Company Ltd. in Tokai-mura, Japan. A collaborating scientific investigation team was organized in two groups, the first to carry out research on the environmental impact (the environmental research group) and the second to assess the radiation effects on residents (the biological research group). This report concerns only the activities of the environmental research group. Four investigative teams were sent on different dates to the accident site and its vicinity to collect samples. About 400 samples were collected and subjected to analysis. An outline of the sampling campaign is presented here along with a brief chronology of the accident and the preliminary key results obtained by the independent research group are summarised in this Special Issue of the Journal of Environmental Radioactivity

  20. Trade-off results and preliminary designs of Near-Term Hybrid Vehicles

    Science.gov (United States)

    Sandberg, J. J.

    1980-01-01

    Phase I of the Near-Term Hybrid Vehicle Program involved the development of preliminary designs of electric/heat engine hybrid passenger vehicles. The preliminary designs were developed on the basis of mission analysis, performance specification, and design trade-off studies conducted independently by four contractors. THe resulting designs involve parallel hybrid (heat engine/electric) propulsion systems with significant variation in component selection, power train layout, and control strategy. Each of the four designs is projected by its developer as having the potential to substitute electrical energy for 40% to 70% of the petroleum fuel consumed annually by its conventional counterpart.

  1. A preliminary comprehensive dynamic analysis of the typical FaCT scenarios with JSFR and related fuel cycle facilities

    International Nuclear Information System (INIS)

    Shiotani, Hiroki; Ono, Kiyoshi; Ogawa, Takashi; Koma, Yoshikazu; Kawaguchi, Koichi

    2009-01-01

    A preliminary comprehensive dynamic analysis of the typical Fast Reactor (FR) deployment scenarios with JSFR and related fuel cycle facilities developed in 'FaCT: Fast Reactor Cycle Technology Development Project' was conducted. The scenarios were evaluated from some of the development targets and design goals in the FaCT project. The isotopic compositions of the nuclear fuels and wastes and the quantities of radioactive wastes (HLWs, LLWs) from Japanese nuclear fuel cycle facilities were calculated to grasp the sustainability characteristics. Regarding the long-term economics, the total cash out-flows and the average electricity generation costs to 22nd century were calculated. Cash out-flow peaks and waste generation peaks were found from 2030s to 2050s, 2090s to 2110s, and 2150s to 2170s because of the cost and wastes from decommissioning of the nuclear power plants and reprocessing plants for LWR spent fuel and the construction costs of them. Firstly, the major results of the reference case are explained combined with introduction of the function of the dynamic analysis tool (Supply Chain Management Code). The analysis is related to sustainability and economics in FaCT project development targets since they are important in the sustainability and economics evaluation. Secondly, the comparisons between the reference case and the three other option cases with their own issues of choice are explained. Those options are different breeding ratios, dual-purpose reprocessing plant, and Am-Cm recycling. As the tentative conclusions of the analyses are: the exploration of the optimal breeding ratio between B.R. =1.1 and 1.2 at the start up stage of FR is regarded as reasonable; the cost reduction of the dual purpose reprocessing plant resulted from the facility integration was confirmed though the cost estimation of the facility should be modified, it is a little bit too hasty to decide the manner of MA recycling because many issues to be considered are left at present

  2. Helios, a 20 TW CO2 laser fusion facility

    International Nuclear Information System (INIS)

    Ladish, J.S.

    1979-01-01

    Since June 1978 the Los Alamos Scientific Laboratory's Helios CO 2 laser fusion facility has been committed to an experimental target program to investigate the feasibility of laser produced inertial confinement fusion. This system is briefly described, and preliminary experimental results are reported

  3. Preliminary results of an oilspill risk analysis for the Bombay High Region

    Digital Repository Service at National Institute of Oceanography (India)

    Mascarenhas, A.A.M.Q.; Gouveia, A.D.; Sitaraman, R.

    oil were analysed, covering estimates of the time between spill occurrence and contact with resources. The combined results yielded estimates of the overall risks associated with production within the developmental area. Preliminary results...

  4. Doses in pediatric patients undergoing chest and abdomen CT examinations. Preliminary results

    International Nuclear Information System (INIS)

    Jornada, Tiago S.; Silva, Teogenes A. da

    2011-01-01

    Computed tomography (CT) is a non-invasive method of image production that imparts significant doses to a patient, it is expected that pediatric CT examinations will increase the risk of induced cancer in children. In this study the effective doses in a five year-old child submitted to chest or abdomen CT scans were assessed for comparison purposes. The CTEXPO computed program was used with data from routine protocols of a 0 to 13 year-old children in two public hospitals in Belo Horizonte. Hospital A used a Siemens Dual-Slice unit with 80 kV, 41 mA and pitch 2 for chest or abdomen; hospital B used a Multislice GE unit with 120 kV, 45 mA and pitch 1 for chest and 120 kV, 55 mA. and pitch 1 for abdomen. Results of effective doses in a five year-old child were 1.7 and 1.0 mSv in hospital A and 9.1 and 7.2 mSv in hospital B, for chest and abdomen, respectively. Results were compared to the reference effective doses of 7.2 and 5.0 mSv for chest and abdomen respectively that were derived from the air kerma length product values given in ICRP publication 87. Results of hospital A showed that low dose exposures also can be achieved in CT scans of children. Results showed that even a hospital with a modern facility (hospital B) can provided doses higher than reference values if protocols are not adjusted for children. Preliminary results suggested that there is a room for optimizing children exposure submitted to CT scans. (author)

  5. Preliminary Results on Uncertainty Quantification for Pattern Analytics

    Energy Technology Data Exchange (ETDEWEB)

    Stracuzzi, David John [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Brost, Randolph [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Chen, Maximillian Gene [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Malinas, Rebecca [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Peterson, Matthew Gregor [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Phillips, Cynthia A. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Robinson, David G. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Woodbridge, Diane [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

    2015-09-01

    This report summarizes preliminary research into uncertainty quantification for pattern ana- lytics within the context of the Pattern Analytics to Support High-Performance Exploitation and Reasoning (PANTHER) project. The primary focus of PANTHER was to make large quantities of remote sensing data searchable by analysts. The work described in this re- port adds nuance to both the initial data preparation steps and the search process. Search queries are transformed from does the specified pattern exist in the data? to how certain is the system that the returned results match the query? We show example results for both data processing and search, and discuss a number of possible improvements for each.

  6. Grid-connected ICES: preliminary feasibility analysis and evaluation. Volume 2. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1977-06-30

    The HEAL Complex in New Orleans will serve as a Demonstration Community for which the ICES Demonstration System will be designed. The complex is a group of hospitals, clinics, research facilities, and medical educational facilities. The five tasks reported on are: preliminary energy analysis; preliminary institutional assessment; conceptual design; firming-up of commitments; and detailed work management plan.

  7. Pickering safeguards: a preliminary analysis

    International Nuclear Information System (INIS)

    Todd, J.L.; Hodgkinson, J.G.

    1977-05-01

    A summary is presented of thoughts relative to a systems approach for implementing international safeguards. Included is a preliminary analysis of the Pickering Generating Station followed by a suggested safeguards system for the facility

  8. Preliminary results on time-resolved ion beam induced luminescence applied to the provenance study of lapis lazuli

    Energy Technology Data Exchange (ETDEWEB)

    Czelusniak, C. [Istituto Nazionale di Fisica Nucleare (INFN), Sezione di Firenze, Via Sansone 1, I-50019 Sesto Fiorentino, Firenze (Italy); Dipartimento di Fisica e Astronomia, Università di Firenze, Via Sansone 1, I-50019 Sesto Fiorentino, Firenze (Italy); Palla, L. [Istituto Nazionale di Fisica Nucleare (INFN), Sezione di Pisa and Università di Pisa, Largo B. Pontecorvo 3, I-56127 Pisa (Italy); Massi, M. [Dipartimento di Fisica e Astronomia, Università di Firenze, Via Sansone 1, I-50019 Sesto Fiorentino, Firenze (Italy); Carraresi, L.; Giuntini, L. [Istituto Nazionale di Fisica Nucleare (INFN), Sezione di Firenze, Via Sansone 1, I-50019 Sesto Fiorentino, Firenze (Italy); Dipartimento di Fisica e Astronomia, Università di Firenze, Via Sansone 1, I-50019 Sesto Fiorentino, Firenze (Italy); Re, A.; Lo Giudice, A. [Dipartimento di Fisica, Università di Torino & INFN Sezione di Torino, Via Giuria 1, 10125 Torino (Italy); Pratesi, G. [Museo di Storia Naturale, Università di Firenze, Via G. La Pira 4, 50121 Firenze (Italy); Mazzinghi, A. [Istituto Nazionale di Fisica Nucleare (INFN), Sezione di Firenze, Via Sansone 1, I-50019 Sesto Fiorentino, Firenze (Italy); Dipartimento di Fisica e Astronomia, Università di Firenze, Via Sansone 1, I-50019 Sesto Fiorentino, Firenze (Italy); Ruberto, C. [Istituto Nazionale di Fisica Nucleare (INFN), Sezione di Firenze, Via Sansone 1, I-50019 Sesto Fiorentino, Firenze (Italy); Dipartimento di Chimica, Università di Firenze, Via della Lastruccia 1, 50019 Sesto Fiorentino, Firenze (Italy); Castelli, L. [Istituto Nazionale di Fisica Nucleare (INFN), Sezione di Firenze, Via Sansone 1, I-50019 Sesto Fiorentino, Firenze (Italy); and others

    2016-03-15

    This work will present preliminary results concerning the use of time-resolved ion beam induced luminescence applied to provenance studies of lapis lazuli. Measurements were performed at the pulsed beam facility at LABEC laboratory in Florence. Lapis lazuli is a semi-precious gemstone, used as ornament since the early civilizations that can be found in few places on Earth. The importance of this work lies in understanding the origin of various samples of lapis lazuli, from which it may be possible to gain insight into trade routes from ancient times. The samples studied in this work originated from Chile, Afghanistan, Tajikistan, Myanmar, and Siberia. The stones were irradiated with 3 MeV protons and the resulting luminescence was detected by a photomultiplier tube, whose output was acquired using a sampling digitizer VME module (CAEN/V1720). Wavelength discrimination was performed at 430 nm utilizing a range of beam currents. The results showed that, by changing the beam current intensity, one can study different features of lapis lazuli, and this may aid in distinguishing lapis lazuli from different provenances.

  9. Preliminary results on time-resolved ion beam induced luminescence applied to the provenance study of lapis lazuli

    International Nuclear Information System (INIS)

    Czelusniak, C.; Palla, L.; Massi, M.; Carraresi, L.; Giuntini, L.; Re, A.; Lo Giudice, A.; Pratesi, G.; Mazzinghi, A.; Ruberto, C.; Castelli, L.

    2016-01-01

    This work will present preliminary results concerning the use of time-resolved ion beam induced luminescence applied to provenance studies of lapis lazuli. Measurements were performed at the pulsed beam facility at LABEC laboratory in Florence. Lapis lazuli is a semi-precious gemstone, used as ornament since the early civilizations that can be found in few places on Earth. The importance of this work lies in understanding the origin of various samples of lapis lazuli, from which it may be possible to gain insight into trade routes from ancient times. The samples studied in this work originated from Chile, Afghanistan, Tajikistan, Myanmar, and Siberia. The stones were irradiated with 3 MeV protons and the resulting luminescence was detected by a photomultiplier tube, whose output was acquired using a sampling digitizer VME module (CAEN/V1720). Wavelength discrimination was performed at 430 nm utilizing a range of beam currents. The results showed that, by changing the beam current intensity, one can study different features of lapis lazuli, and this may aid in distinguishing lapis lazuli from different provenances.

  10. Preliminary design and definition of field experiments for welded tuff rock mechanics program

    International Nuclear Information System (INIS)

    Zimmerman, R.M.

    1982-06-01

    The preliminary design contains objectives, typical experiment layouts, definitions of equipment and instrumentation, test matrices, preliminary design predictive modeling results for five experiments, and a definition of the G-Tunnel Underground Facility (GTUF) at the Nevada Test Site where the experiments are to be located. Experiments described for investigations in welded tuff are the Small Diameter Heater, Unit Cell-Canister Scale, Heated Block, Rocha Slot, and Miniature Heater

  11. Preliminary time-phased TWRS process model results

    International Nuclear Information System (INIS)

    Orme, R.M.

    1995-01-01

    This report documents the first phase of efforts to model the retrieval and processing of Hanford tank waste within the constraints of an assumed tank farm configuration. This time-phased approach simulates a first try at a retrieval sequence, the batching of waste through retrieval facilities, the batching of retrieved waste through enhanced sludge washing, the batching of liquids through pretreatment and low-level waste (LLW) vitrification, and the batching of pretreated solids through high-level waste (HLW) vitrification. The results reflect the outcome of an assumed retrieval sequence that has not been tailored with respect to accepted measures of performance. The batch data, composition variability, and final waste volume projects in this report should be regarded as tentative. Nevertheless, the results provide interesting insights into time-phased processing of the tank waste. Inspection of the composition variability, for example, suggests modifications to the retrieval sequence that will further improve the uniformity of feed to the vitrification facilities. This model will be a valuable tool for evaluating suggested retrieval sequences and establishing a time-phased processing baseline. An official recommendation on tank retrieval sequence will be made in September, 1995

  12. Authentication by Keystroke Timing: Some Preliminary Results

    National Research Council Canada - National Science Library

    Gaines, R. S; Lisowski, William; Press, S. J; Shapiro, Norman

    1980-01-01

    ... of an individual seeking access to the computer. This report summarizes preliminary efforts to establish whether an individual can be identified by the statistical characteristics of his or her typing...

  13. Experiments to determine the migration potential for water and contaminants in shallow land-burial facilities: design, emplacement, and preliminary results

    International Nuclear Information System (INIS)

    DePoorter, G.L.; Abeele, W.V.; Burton, B.W.

    1982-01-01

    Although there have been many laboratory studies on water movement and contaminant transport, there is a need for more large scale field experiments. Large scale field experiments are necessary to (1) measure hydraulic conductivities on a scale typical of actual shallow land burial facilities and hazardous waste disposal facilities, (2) allow comparisons to be made between full scale and laboratory measurements, (3) verify the applicability of calculational methods for determining unsaturated hydraulic conductivities from water retention curves, and (4) for model validation. Experiments that will provide the information to do this are described in this paper. The results of these experiments will have applications for both the shallow land burial of low level radioactive wastes and the disposal of hazardous chemical wastes. These experiments will provide results that can be used in model verification for system performance. This type of data on experiments done at this scale has not been available, and are necessary for validating unsaturated transport models and other models used to predict long term system performance. Even though these experiments are done on crushed Bandelier Tuff, most models use physical properties of the backfill material such as density, porosity, and water retention curves. For this reason, once the models are validated in these experiments, they can be applied with confidence to other materials as long as the material properties are well characterized. In addition, from known water movement rates, calculable from the results of these experiments, requirements for other parts of the system such as liners, water diversion systems, and system cap requirements can be determined. Lastly, the results of these experiments and their use in model verification will provide a sound scientific basis on which to base decisions on system requirements and system design

  14. Los Alamos Experimental Engineering Waste Burial Facility: design considerations and preliminary experimental plan

    International Nuclear Information System (INIS)

    DePoorter, G.L.

    1981-01-01

    The Experimental Engineered Waste Burial Facility is a field test site where generic experiments can be performed on several scales to get the basic information necessary to understand the processes occurring in low-level waste disposal facilities. The experiments include hydrological, chemical, mechanical, and biological factors. In order to separate these various factors in the experiments and to extrapolate the experimental results to actual facilities, experiments will be performed on several different scales

  15. Preliminary results of Digital Pulse Shape Acquisition from Chimera

    International Nuclear Information System (INIS)

    Alderighi, D.M.; Sechi, G.; Anzalone, A.; Cavallaro, S.; Giustolisi, F.; Laguidara, E.; Lanzalone, G.; Porto, F.; Bassini, R.; Boiano, C.; Guazzoni, P.; Russo, S.; Sassi, M.; Zetta, L.; Cardella, G.; Defilippo, S.E.; Lanzano, G.; Paganod, A.; Papa, M.; Pirrone, S.; Politi, G.; Geraci, E.

    2003-01-01

    A 100 MS/s 14-bit Sampling Analog-to-Digital converter has been used to perform digital pulse-shape acquisition of signals collected from CHIMERA telescopes. The signals from a typical CHIMERA detection cell have been collected using both a standard CHIMERA electronic chain up to the amplifier, and a very simple analog front end, basically reduced to the preamplifier. The preliminary on-beam results are presented. (authors)

  16. Preliminary results of Digital Pulse Shape Acquisition from Chimera

    Energy Technology Data Exchange (ETDEWEB)

    Alderighi, D.M.; Sechi, G. [INFN Milano and IASF, CNR, Milano (France); Anzalone, A.; Cavallaro, S.; Giustolisi, F.; Laguidara, E.; Lanzalone, G.; Porto, F. [Catania Univ., LNS and Dipartimento di Fisica (France); Bassini, R.; Boiano, C.; Guazzoni, P.; Russo, S.; Sassi, M.; Zetta, L. [Milano Univ., INFN and Dipartimento di Fisica (Italy); Cardella, G.; Defilippo, S.E.; Lanzano, G.; Paganod, A.; Papa, M.; Pirrone, S.; Politi, G. [Catania Univ., INFN and Dipartimento di Fisica (Italy); Geraci, E. [Bologna Univ., INFN and Dipartimento di Fisica (Italy)

    2003-07-01

    A 100 MS/s 14-bit Sampling Analog-to-Digital converter has been used to perform digital pulse-shape acquisition of signals collected from CHIMERA telescopes. The signals from a typical CHIMERA detection cell have been collected using both a standard CHIMERA electronic chain up to the amplifier, and a very simple analog front end, basically reduced to the preamplifier. The preliminary on-beam results are presented. (authors)

  17. Hellenic Amateur Astronomy Association's activities: Preliminary results on Perseids 2010

    Science.gov (United States)

    Maravelias, G.

    2011-01-01

    Preliminary results on the Perseids 2010 are presented. Visual and video observations were obtained by the author and a first reduction of the visual data shows that a maximum of ZHR ~120 was reached during the night 12-13 of August 2010. Moreover, a video setup was tested (DMK camera and UFO Capture v2) and the results show that, under some limitations, valuable data can be obtained.

  18. Functional requirements regarding medical registries--preliminary results.

    Science.gov (United States)

    Oberbichler, Stefan; Hörbst, Alexander

    2013-01-01

    The term medical registry is used to reference tools and processes to support clinical or epidemiologic research or provide a data basis for decisions regarding health care policies. In spite of this wide range of applications the term registry and the functional requirements which a registry should support are not clearly defined. This work presents preliminary results of a literature review to discover functional requirements which form a registry. To extract these requirements a set of peer reviewed articles was collected. These set of articles was screened by using methods from qualitative research. Up to now most discovered functional requirements focus on data quality (e. g. prevent transcription error by conducting automatic domain checks).

  19. Hayabusa Asteroidal Sample Preliminary Examination Team (HASPET) and the Astromaterial Curation Facility at JAXA/ISAS

    Science.gov (United States)

    Yano, H.; Fujiwara, A.

    After the successful launch in May 2003, the Hayabusa (MUSES-C) mission of JAXA/ISAS will collect surface materials (e.g., regolith) of several hundred mg to several g in total from the S-type near Earth asteroid (25143) Itokawa in late 2005 and bring them back to ground laboratories in the summer of 2007. The retrieved samples will be given initial analysis at the JAXA/ISAS astromaterial curation facility, which is currently in the preparation for its construction, by the Hayabusa Asteroidal Sample Preliminary Examination Team (HASPET). HASPET is consisted of the ISAS Hayabusa team, the international partners from NASA and Australia and all-Japan meteoritic scientists to be selected as outsourcing parts of the initial analyses. The initial analysis to characterize general aspects of returned samples can consume only 15 % of its total mass and must complete the whole analyses including the database building before international AO for detailed analyses within the maximum of 1 year. Confident exercise of non-destructive, micro-analyses whenever possible are thus vital for the HASPET analysis. In the purpose to survey what kinds and levels of micro-analysis techniques in respective fields, from major elements and mineralogy to trace and isotopic elements and organics, are available in Japan at present, ISAS has conducted the HASPET open competitions in 2000-01 and 2004. The initial evaluation was made by multiple domestic peer reviews. Applicants were then provided two kinds of unknown asteroid sample analogs in order to conduct proposed analysis with self-claimed amount of samples in self-claimed duration. After the completion of multiple, international peer reviews, the Selection Committee compiled evaluations and recommended the finalists of each round. The final members of the HASPET will be appointed about 2 years prior to the Earth return. Then they will conduct a test-run of the whole initial analysis procedures at the ISAS astromaterial curation facility and

  20. Preliminary volcanic hazards evaluation for Los Alamos National Laboratory Facilities and Operations : current state of knowledge and proposed path forward

    Energy Technology Data Exchange (ETDEWEB)

    Keating, Gordon N.; Schultz-Fellenz, Emily S.; Miller, Elizabeth D.

    2010-09-01

    The integration of available information on the volcanic history of the region surrounding Los Alamos National Laboratory indicates that the Laboratory is at risk from volcanic hazards. Volcanism in the vicinity of the Laboratory is unlikely within the lifetime of the facility (ca. 50–100 years) but cannot be ruled out. This evaluation provides a preliminary estimate of recurrence rates for volcanic activity. If further assessment of the hazard is deemed beneficial to reduce risk uncertainty, the next step would be to convene a formal probabilistic volcanic hazards assessment.

  1. Preliminary results of a test of a longitudinal phase-space monitor

    International Nuclear Information System (INIS)

    Kikutani, Eiji; Funakoshi, Yoshihiro; Kawamoto, Takashi; Mimashi, Toshihiro

    1994-01-01

    A prototype of a longitudinal phase-space monitor has been developed in TRISTAN Main Ring at KEK. The principle of the monitor and its basic components are explained. Also a result of a preliminary beam test is given. (author)

  2. Preliminary Results on Asymptotic Stabilization of Hamiltonian Systems with Nonholonomic Constraints

    NARCIS (Netherlands)

    Khennouf, H.; Canudas de Wit, C.; Schaft, A.J. van der

    1995-01-01

    This paper presents some preliminary results on asymptotic stabilization of nonholonomic mechanical systems using the Hamiltonian formulation proposed previously. Our work seeks to establish a general formulation for designing time-varying controllers for some mechanical system described in the

  3. Study for the selection of a supplementary spent fuel storage facility for KANUPP

    International Nuclear Information System (INIS)

    Ahmed, W.; Iqbal, M.J.; Arshad, M.

    1999-01-01

    Steps taken for construction of the spent fuel facility of Karachi Nuclear Power Plant (KANUPP) are the following: choice of conceptual design and site selection; preliminary design and preparation of Preliminary Safety Analysis Report (PSAR); Construction of the facility and preparation of PSAR; testing/commissioning and loading of the storage facility. Characterisation of the spent fuel is essential for design of the storage facility. After comparison of various storage types, it seems that construction of dry storage facility based on concrete canisters at KANUPP site is a suitable option to enhance the storage capacity

  4. Preliminary Results Of A 600 Joules Small Plasma Focus Device

    International Nuclear Information System (INIS)

    Lee, S. H.; Yap, S. L.; Wong, C. S.

    2009-01-01

    Preliminary results of a 600 J (3.7 μF, 18 kV) Mather type plasma focus device operated at low pressure will be presented. The discharge is formed between a solid anode with length of 6 cm and six symmetrically and coaxially arranged cathode rods of same lengths. The cathode base is profiled in a knife-edge design and a set of coaxial plasma gun are attached to it in order to initiate the breakdown and enhance the current sheath formation. The experiments have been performed in argon gas under a low pressure condition of several microbars. The discharge current and the voltage across the electrodes during the discharge are measured with high voltage probe and current coil. The current and voltage characteristics are used to determine the possible range of operating pressure that gives good focusing action. At a narrow pressure regime of 9.0±0.5 μbar, focusing action is observed with good reproducibility. Preliminary result of ion beam energy is presented. More work will be carried out to investigate the radiation output.

  5. Preliminary analysis of the KAERI RCCS Experiment Using GAMMA+

    Energy Technology Data Exchange (ETDEWEB)

    Khoza, Samukelisiwe; Tak, Nam-il; Lim, Hong-Sik; Lee, Sung-Nam; Cho, Bong-Hyun; Kim, Jong-Hwan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-05-15

    This paper describes the analysis of the KAERI RCCS experiment. GAMMA+ code was used for analysis of the RCCS 1/4-scale natural cooling experimental facility designed and built at KAERI to verify the performance of the natural circulation phenomenon. The results obtained from the GAMMA+ analysis showing the temperature profiles and flow rates at steady state were compared with the results from the preliminary experiments conducted in this facility. GAMMA+ analysis for the KAERI RCCS experimental setup was carried out to understand its natural circulation behavior. The air flow rate at the chimney exit achieved by experiments was from to be almost same as that of GAMMA+.

  6. Results from the CLIC Test Facility

    CERN Document Server

    Braun, H; Bossart, Rudolf; Chautard, F; Corsini, R; Delahaye, J P; Godot, J C; Hutchins, S; Kamber, I; Madsen, J H B; Rinolfi, Louis; Rossat, G; Schreiber, S; Suberlucq, Guy; Thorndahl, L; Wilson, Ian H; Wuensch, Walter

    1996-01-01

    In order to study the principle of the Compact Linear Collider (CLIC) based on the Two Beam Acceleration (TBA) scheme at high frequency, a CLIC Test Facility (CTF) has been set-up at CERN. After four years of successful running, the experimental programme is now fully completed and all its objectives reached, particularly the generation of a high intensity drive beam with short bunches by a photo-injector, the production of 30 GHz RF power and the acceleration of a probe beam by 30 GHz structures. A summary of the CTF results and their impact on linear collider design is given. This covers 30 GHz high power testing, study of intense, short single bunches; as well as RF-Gun, photocathode and beam diagnostic developments. A second phase of the test facility (CTF2) is presently being installed to demonstrate the feasibility of the TBA scheme by constructing a fully engineered, 10 m long, test section very similar to the CLIC drive and main linacs, producing up to 480 MW of peak RF power at 30 GHz and acceleratin...

  7. 77 FR 72817 - Glycine From the People's Republic of China: Preliminary Results of Antidumping Duty...

    Science.gov (United States)

    2012-12-06

    ... Republic of China: Preliminary Results of Antidumping Duty Administrative Review and Preliminary Partial... conducting an administrative review of the antidumping duty order on glycine from the People's Republic of... covers one exporter of subject merchandise, Baoding Mantong Fine Chemistry Co. Ltd. (Baoding Mantong). We...

  8. Safety report content and development for test loop facility on MARIA reactor

    International Nuclear Information System (INIS)

    Konechko, A.; Shumskij, A.M.; Mikul'ahin, V.E.

    1982-01-01

    A 600 kW test loop facility for investigatin.o safety problems is realized on MARIA reactor in Poland together with USSR organizations. Safety reports have been developed in two steps at the designstage. The 1st report being essentially a preliminary safety analysis was developed within the scope of the feasibility study. At the engineering design stage the preliminary test loop facility safety report had been prepared considering measures excluding the possibility of the MARIA reactor damage. The test loop facility safety report is fulfilled for normal, transient and emergency operation regimes. Separate safety basing for each group of experiments will be prepared. The report presents the test loop facility safety criteria coordinated by the nuclear safety comission. They contains the preliminary reports on the test loop facility safety. At the final stage of construction and at thecommitioning stage the start-up safety report will be developed which after required correction and adding up the putting into operation data will turn into operation safety report [ru

  9. Preliminary results of the round-robin testing of F82H

    Energy Technology Data Exchange (ETDEWEB)

    Shiba, K.; Yamanouchi, N.; Tohyama, A.

    1996-10-01

    Preliminary results of metallurgical, physical and mechanical properties of low activation ferritic steel F82H (IEA heat) were obtained in the round-robin test in Japan. The properties of IEA heat F82H were almost the same as the original F82H.

  10. Test facilities for evaluating nuclear thermal propulsion systems

    International Nuclear Information System (INIS)

    Beck, D.F.; Allen, G.C.; Shipers, L.R.; Dobranich, D.; Ottinger, C.A.; Harmon, C.D.; Fan, W.C.; Todosow, M.

    1992-01-01

    Interagency panels evaluating nuclear thermal propulsion (NTP) development options have consistently recognized the need for constructing a major new ground test facility to support fuel element and engine testing. This paper summarizes the requirements, configuration, and baseline performance of some of the major subsystems designed to support a proposed ground test complex for evaluating nuclear thermal propulsion fuel elements and engines being developed for the Space Nuclear Thermal Propulsion (SNTP) program. Some preliminary results of evaluating this facility for use in testing other NTP concepts are also summarized

  11. Radon concentrations in Norwegian kindergartens: survey planning and preliminary results

    International Nuclear Information System (INIS)

    Birovljev, A.; Strand, T.; Heiberg, A.

    1998-01-01

    An extensive radon survey in Norwegian kindergartens and schools was started in early 1997; so far 2481 kindergartens were examined. Preliminary results of the first phase of the survey are presented in tabular and graphic form including, among others, the dependence of average radon concentration on the construction year of the kindergartens and on the age of the buildings. (A.K.)

  12. FUEL HANDLING FACILITY BACKUP CENTRAL COMMUNICATIONS ROOM SPACE REQUIREMENTS CALCULATION

    International Nuclear Information System (INIS)

    SZALEWSKI, B.

    2005-01-01

    The purpose of the Fuel Handling Facility Backup Central Communications Room Space Requirements Calculation is to determine a preliminary estimate of the space required to house the backup central communications room in the Fuel Handling Facility (FHF). This room provides backup communications capability to the primary communication systems located in the Central Control Center Facility. This calculation will help guide FHF designers in allocating adequate space for communications system equipment in the FHF. This is a preliminary calculation determining preliminary estimates based on the assumptions listed in Section 4. As such, there are currently no limitations on the use of this preliminary calculation. The calculations contained in this document were developed by Design and Engineering and are intended solely for the use of Design and Engineering in its work regarding the FHF Backup Central Communications Room Space Requirements. Yucca Mountain Project personnel from Design and Engineering should be consulted before the use of the calculations for purposes other than those stated herein or use by individuals other than authorized personnel in Design and Engineering

  13. 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

  14. SULTAN test facility: Summary of recent results

    International Nuclear Information System (INIS)

    Stepanov, Boris; Bruzzone, Pierluigi; Sedlak, Kamil; Croari, Giancarlo

    2013-01-01

    The test campaigns of the ITER conductors in the SULTAN test facility re-started in December 2011 after three months break. The main focus of the activities is about the qualification tests of the Central Solenoid (CS) conductors, with three different samples for a total six variations of strand suppliers and cable layouts. In 2012, five Toroidal Field (TF) conductor samples have also been tested as part of the supplier and process qualification phase of the European, Korean, Chinese and Russian Federation Agencies. A summary of the test results for all the ITER samples tested in the last period is presented, including an updated statistics of the broad transition, the performance degradation and the impact of layout variations. The role of SULTAN test facility during the ITER construction is reviewed, and the load of work for the next three years is anticipated

  15. Preliminary waste acceptance requirements - Konrad repository project

    International Nuclear Information System (INIS)

    Brennecke, P.W.; Warnecke, E.H.

    1991-01-01

    In Germany, the planned Konrad repository is proposed for the disposal of all types of radioactive wastes whose thermal influence upon the host rock is negligible. The Bundesamt fuer Strahlenschutz has established Preliminary Waste Acceptance Requirements (as of April 1990) for this facility. The respective requirements were developed on the basis of the results of site-specific safety assessments. They include general requirements on the waste packages to be disposed of as well as more specific requirements on the waste forms, the packaging and the radionuclide inventory per waste package. In addition, the delivery of waste packages was regulated. An outline of the structure and the elements of the Preliminary Waste Acceptance Requirements of April 1990 is given including comments on their legal status. (Author)

  16. TCA High Lift Preliminary Assessment

    Science.gov (United States)

    Wyatt, G. H.; Polito, R. C.; Yeh, D. T.; Elzey, M. E.; Tran, J. T.; Meredith, Paul T.

    1999-01-01

    This paper presents a TCA (Technology Concept Airplane) High lift Preliminary Assessment. The topics discussed are: 1) Model Description; 2) Data Repeatability; 3) Effect of Inboard L.E. (Leading Edge) Flap Span; 4) Comparison of 14'x22' TCA-1 With NTF (National Transonic Facility) Modified Ref. H; 5) Comparison of 14'x22' and NTF Ref. H Results; 6) Effect of Outboard Sealed Slat on TCA; 7) TCA Full Scale Build-ups; 8) Full Scale L/D Comparisons; 9) TCA Full Scale; and 10) Touchdown Lift Curves. This paper is in viewgraph form.

  17. Natech accidents at industrial facilities. The case of the Wenchuan earthquake

    OpenAIRE

    Krausmann , Elisabeth; Cruz , Ana Maria; Affeltranger , Bastien

    2009-01-01

    International audience; Natural disasters can trigger chemical accidents (so-called Natech accidents) with severe consequences on man or the environment. This work highlights the main characteristics of earthquake-triggered Natechs by describing our insights from a field trip to chemical facilities in the area affected by the 12 May, 2008, Wenchuan earthquake in China. Our preliminary results indicate that damage was most severe in older facilities with masonry and un- or poorly reinforced co...

  18. Report on the preliminary fact finding mission following the accident at the nuclear fuel processing facility in Tokaimura, Japan

    International Nuclear Information System (INIS)

    1999-01-01

    Following the accident on 30 September 1999 at the nuclear fuel processing facility at Tokaimura, Japan, the IAEA Emergency Response Centre received numerous requests for information about the event's causes and consequences from Contact Points under the Conventions on Early Notification of a Nuclear Accident and on Assistance in the Case of a Nuclear Accident or Radiological Emergency. Although the lack of transboundary consequences of the accident meant that action under the Early Notification Convention was not triggered, the Emergency Response Centre issued several advisories to Member States which drew on official reports received from Japan. After discussions with the Government of Japan, the IAEA dispatched a team of three experts from the Secretariat on a fact finding mission to Tokaimura from 13 to 17 October 1999. The present preliminary report by that team documents key technical information obtained during the mission. At this stage, the report can in no way provide conclusive judgements on the causes and consequences of the accident. Investigations are proceeding in Japan and more information is expected to be made available after access has been gained to the building where the accident occurred. Moreover, much of the information already made available will be revised as more accurate assessments are made, for example of the radiation doses to the three individuals who received the highest exposures. Notwithstanding the preliminary nature of this report, it is clear that the accident was not one involving widespread contamination of the environment as in the 1986 Chernobyl accident. Although there was little risk off the site once the accident had been brought under control, the authorities evacuated the population living within a few hundred metres and advised people within about 10 km of the facility to take shelter for a period of about one day. The event at Tokaimura was nevertheless a serious industrial accident. The results of the detailed

  19. The Southern HII Region Discovery Survey: Preliminary Results

    Science.gov (United States)

    Shea, Jeanine; Wenger, Trey; Balser, Dana S.; Anderson, Loren D.; Armentrout, William P.; Bania, Thomas M.; Dawson, Joanne; Miller Dickey, John; Jordan, Christopher; McClure-Griffiths, Naomi M.

    2017-01-01

    HII regions are some of the brightest sources at radio frequencies in the Milky Way and are the sites of massive O and B-type star formation. They have relatively short (Bank Telescope. Candidate HII regions were selected from mid-infrared emission coincident with radio continuum emission, and confirmed as HII regions by the detection of radio recombination lines. Here we discuss the Southern HII Region Discovery Survey (SHRDS), a continuation of the HRDS using the Australia Telescope Compact Array over the Galactic longitude range 230 to 360 degrees. We have reduced and analyzed a small sub-set of the SHRDS sources and discuss preliminary results, including kinematic distances and metallicities.

  20. Reflooding phenomena of German PWR estimated from CCTF [Cylindrical Core Test Facility], SCTF [Slab Core Test Facility] and UPTF [Upper Plenum Test Facility] results

    International Nuclear Information System (INIS)

    Murao, Y.; Iguchi, T.; Sugimoto, J.

    1988-09-01

    The reflooding behavior in a PWR with a combined injection type ECCS was studied by comparing the test results from Cylindrical Core Test Facility (CCTF), Slab Core Test Facility (SCTF) and Upper Plenum Test Facility (UPTF). Core thermal-hydraulics is discussed mainly based on SCTF test data. In addition, the water accumulation behavior in hot legs and the break-through characteristics at tie plate are discussed

  1. Study on critical heat flux in narrow rectangular channel with repeated-rib roughness. 1. Experimental facility and preliminary experiments

    International Nuclear Information System (INIS)

    Kinoshita, Hidetaka; Terada, Atsuhiko; Kaminaga, Masanori; Hino, Ryutaro

    2001-10-01

    In the design of a spallation target system, the water cooling system, for example a proton beam window and a safety hull, is used with narrow channels, in order to remove high heat flux and prevent lowering of system performance by absorption of neutron. And in narrow channel, heat transfer enhancement using 2-D rib is considered for reduction the cost of cooling component and decrease inventory of water in the cooling system, that is, decrease of the amount of irradiated water. But few studies on CHF with rib have been carried out. Experimental and analytical studies with rib-roughened test section, in 10:1 ratio of pitch to height, are being carried out in order to clarify the CHF in rib-roughened channel. This paper presents the review of previous researches on heat transfer in channel with rib roughness, overview of the test facility and the preliminary experimental and analytical results. As a result, wall friction factors were about 3 times as large as that of smooth channel, and heat transfer coefficients are about 2 times as large as that of smooth channel. The obtained CHF was as same as previous mechanistic model by Sudo. (author)

  2. Preliminary Results of Ancillary Safety Analyses Supporting TREAT LEU Conversion Activities

    Energy Technology Data Exchange (ETDEWEB)

    Brunett, A. J. [Argonne National Lab. (ANL), Argonne, IL (United States); Fei, T. [Argonne National Lab. (ANL), Argonne, IL (United States); Strons, P. S. [Argonne National Lab. (ANL), Argonne, IL (United States); Papadias, D. D. [Argonne National Lab. (ANL), Argonne, IL (United States); Hoffman, E. A. [Argonne National Lab. (ANL), Argonne, IL (United States); Kontogeorgakos, D. C. [Argonne National Lab. (ANL), Argonne, IL (United States); Connaway, H. M. [Argonne National Lab. (ANL), Argonne, IL (United States); Wright, A. E. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2015-10-01

    Report (FSAR) [3]. Depending on the availability of historical data derived from HEU TREAT operation, results calculated for the LEU core are compared to measurements obtained from HEU TREAT operation. While all analyses in this report are largely considered complete and have been reviewed for technical content, it is important to note that all topics will be revisited once the LEU design approaches its final stages of maturity. For most safety significant issues, it is expected that the analyses presented here will be bounding, but additional calculations will be performed as necessary to support safety analyses and safety documentation. It should also be noted that these analyses were completed as the LEU design evolved, and therefore utilized different LEU reference designs. Preliminary shielding, neutronic, and thermal hydraulic analyses have been completed and have generally demonstrated that the various LEU core designs will satisfy existing safety limits and standards also satisfied by the existing HEU core. These analyses include the assessment of the dose rate in the hodoscope room, near a loaded fuel transfer cask, above the fuel storage area, and near the HEPA filters. The potential change in the concentration of tramp uranium and change in neutron flux reaching instrumentation has also been assessed. Safety-significant thermal hydraulic items addressed in this report include thermally-induced mechanical distortion of the grid plate, and heating in the radial reflector.

  3. Preliminary assessment report for National Guard Training Center, Georgia Army National Guard, Fort Stewart, Georgia

    International Nuclear Information System (INIS)

    1993-07-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at the Georgia Army National Guard (GAARNG) facility near Hinesville, Georgia, known as the National Guard Training Center (NGTC). Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a priority basis for completing corrective actions (where necessary) in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining previous site activities, types and quantities of hazardous substances utilized, and potential pathways by which contamination could affect public health and the environment. The scope of this assessment is limited to the facilities and past activities contained within the NGTC. Preliminary assessment site score sheet information is also provided for the NGTC. However, this assessment report is intended to be read in conjunction with a previous IRP assessment of Fort Stewart completed in 1992 (USATHAMA 1992) and to provide comprehensive information on the NGTC area for incorporation with information contained in that previous assessment for the entirety of Fort Stewart

  4. Description and Results: Antenna Measurement Facility Comparisons [Measurements Corner

    DEFF Research Database (Denmark)

    Alberica Saporetti, Maria; Foged, Lars; Sierra Castañer, Manuel

    2017-01-01

    In recent years, formalized facility comparison activities have become important for the documentation and validation of laboratory proficiency and competence and mandatory for achieving accreditation such as that of the International Organization for Standardization (ISO) 17025 or similar...... for Antennas (VISTA) IC1102, including still ongoing campaigns [3]-[5]. Results of these activities have led to improvements in antenna measurement procedures and protocols in facilities and standards [6], [7]. Due to the direct benefits available to the participants, the activities have been very successful...

  5. Preliminary Study on the High Efficiency Supercritical Pressure Water-Cooled Reactor for Electricity Generation

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Yoon Yeong; Park, Jong Kyun; Cho, Bong Hyun and others

    2006-01-15

    This research has been performed to introduce a concept of supercritical pressure water cooled reactor(SCWR) in Korea The area of research includes core conceptual design, evaluation of candidate fuel, fluid systems conceptual design with mechanical consideration, preparation of safety analysis code, and construction of supercritical pressure heat transfer test facility, SPHINX, and preliminary test. As a result of the research, a set of tools for the reactor core design has been developed and the conceptual core design with solid moderator was proposed. The direct thermodynamic cycle has been studied to find a optimum design. The safety analysis code has also been adapted to supercritical pressure condition. A supercritical pressure CO2 heat transfer test facility has been constructed and preliminary test proved the facility works as expected. The result of this project will be good basis for the participation in the international collaboration under GIF GEN-IV program and next 5-year mid and long term nuclear research program of MOST. The heat transfer test loop, SPHINX, completed as a result of this project may be used for the power cycle study as well as further heat transfer study for the various geometries.

  6. Report of the research results with JAERI's facilities in fiscal 1975

    International Nuclear Information System (INIS)

    1976-07-01

    Results of the research works by educational institutions using facilities of the Japan Atomic Energy Research Institute in fiscal 1975 are reported in individual summaries. Facilities utilized are research reactors, Co-60 irradiation facilities, hot laboratory, Linac and electron accelerators. Fields of research are the following: nuclear physics, radiation damage/solid-state physics, positron annihilation, activation analysis/nuclear chemistry, hot atom chemistry, irradiation effects, biology, and neutron diffraction; and, cooperative works to JAERI. (Mori, K.)

  7. Nb/NiCu bilayers in single and stacked superconductive tunnel junctions: preliminary results

    International Nuclear Information System (INIS)

    Pepe, G.P.; Ruotolo, A.; Parlato, L.; Peluso, G.; Ausanio, G.; Carapella, G.; Latempa, R.

    2004-01-01

    We present preliminary experimental results concerning both single and stacked tunnel junctions in which one of the electrodes was formed by a superconductor/ferromagnet (S/F) bi-layer. In particular, in the stacked configuration a Nb/NiCu bi-layer was used as the intermediate electrode, and it was probed by tunneling on both sides. Tunnel junctions have been characterized in terms of current-voltage characteristics (IVC), and differential conductance. Preliminary steady-state injection-detection measurements performed in the stacked devices at T=4.2 K are also presented and discussed

  8. Long range radio tracking of sea turtles and polar bear: Instrumentation and preliminary results

    Science.gov (United States)

    Baldwin, H. A.

    1972-01-01

    Instrumentation developed for studies of path behavior of the green sea turtle and migration movement of polar bear is described. Preliminary results bearing on navigation ability in these species are presented. Both species operate in difficult environments, and the problems faced in the design of electronic instrumentation for these studies are not completely specified at this time. However, the critical factors yet to be understood are primarily related to the behavior of instrumented animals. The data obtained with these experimental techniques are included, first to illustrate the technique and, second to provide initial preliminary results bearing on animal navigation.

  9. Sedimentation on the Valencia Continental Shelf: Preliminary results

    Science.gov (United States)

    Maldonado, Andres; Swift, Donald J. P.; Young, Robert A.; Han, Gregory; Nittrouer, Charles A.; DeMaster, David J.; Rey, Jorge; Palomo, Carlos; Acosta, Juan; Ballester, A.; Castellvi, J.

    1983-10-01

    Preliminary analysis of data collected during the course of a cooperative Spanish-United States investigation of the Valencia Shelf (western Mediterranean) reveals a storm-dominated, mud-accumulating sedimentary regime. Calcareous mud is accumulating seaward of a narrow band of shoreface sand and gravel. On the outer shelf the mud is enriched by a pelagic calcareous component. Preliminary 210Pb data from vertical profiles of box cores yield nominal accumulation rates from 2.6 mm y -1 near the Ebro Delta to 1.3 mm y -1 on the southern portion of the Valencia Shelf. Storm-current winnowing has resulted in the development of a biogenic lag sand over the mid-shelf mud in the northern part of the study area. Piston cores reveal a basal Holocene sand and gravel facies similar to that presently seen on the inner shelf. Upward-fining sequences on the central and outer shelf are inferred to result from the landward shift of lithotopes during the course of the Holocene transgression. These sequences are locally repeated, perhaps as the consequence of brief, local interludes of coastal progradation. Application of a diagnostic circulation model suggests that intense, downwelling coastal flows occur during winter northeastern storms. Storm activity has induced erosional shoreface retreat during the course of the Holocene transgression and has generated by this means the basal coarse facies observed in the piston cores. In the central part of the study area seaward of the Albufera Lagoon, the mud blanket thins to a layer several centimeters thick which is draped over a thickened (10 m) basal sand. The basal sand is molded into northwest trending ridges. The data are not sufficient to determine whether these are overstepped barriers, or submarine sand ridges formed by storm flows during the shoreface retreat process.

  10. Preliminary Beam Irradiation Test for RI Production Targets at KOMAC

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Sang Pil; Kwon, Hyeok Jung; Kim, Han Sung; Cho, Yong Sub; Seol, Kyung Tae; Song, Young Gi; Kim, Dae Il; Jung, Myung Hwan; Kim, Kye Ryung; Min, Yi Sub [KAERI, Daejeon (Korea, Republic of)

    2016-05-15

    The new beamline and target irradiation facility has been constructed for the production of therapeutic radio-isotope. Sr-82 and Cu-67 were selected as the target isotope in this facility, they are promising isotope for the PET imaging and cancer therapy. For the facility commissioning, the irradiation test for the prototype-target was conducted to confirm the feasibility of radio-isotope production, the proto-type targets are made of RbCl pellet and the natural Zn metal for Sr-82 and Cu-67 production respectively, In this paper, an introduction to the RI production targetry system and the results of the preliminary beam irradiation test are discussed. the low-flux beam irradiation tests for proto-type RI target have been conducted. As a result of the beam irradiation tests, we could obtain the evidence of Sr-82 and Cu-67 production, have confirmed the feasibility of Sr-82 and Cu-67 production at KOMAC RI production facility.

  11. Preliminary Beam Irradiation Test for RI Production Targets at KOMAC

    International Nuclear Information System (INIS)

    Yoon, Sang Pil; Kwon, Hyeok Jung; Kim, Han Sung; Cho, Yong Sub; Seol, Kyung Tae; Song, Young Gi; Kim, Dae Il; Jung, Myung Hwan; Kim, Kye Ryung; Min, Yi Sub

    2016-01-01

    The new beamline and target irradiation facility has been constructed for the production of therapeutic radio-isotope. Sr-82 and Cu-67 were selected as the target isotope in this facility, they are promising isotope for the PET imaging and cancer therapy. For the facility commissioning, the irradiation test for the prototype-target was conducted to confirm the feasibility of radio-isotope production, the proto-type targets are made of RbCl pellet and the natural Zn metal for Sr-82 and Cu-67 production respectively, In this paper, an introduction to the RI production targetry system and the results of the preliminary beam irradiation test are discussed. the low-flux beam irradiation tests for proto-type RI target have been conducted. As a result of the beam irradiation tests, we could obtain the evidence of Sr-82 and Cu-67 production, have confirmed the feasibility of Sr-82 and Cu-67 production at KOMAC RI production facility

  12. National Data Center Preparedness Exercise 2015 (NPE 2015): MY-NDC Preliminary Analysis Result

    International Nuclear Information System (INIS)

    Faisal Izwan Abdul Rashid; Muhammed Zulfakar Zolkaffly

    2016-01-01

    Malaysia has established the CTBT National Data Centre (MY-NDC) in December 2005. MY-NDC is tasked to perform Comprehensive Nuclear-Test-Ban-Treaty (CTBT) data management as well as provide information for Treaty related events to Nuclear Malaysia as CTBT National Authority. In 2015, MY-NDC has participated in the National Data Centre Preparedness Exercise 2015 (NPE 2015). This paper aims at presenting MY-NDC preliminary analysis result of NPE 2015. In NPE 2015, MY-NDC has performed five different analyses, namely, radionuclide, atmospheric transport modelling (ATM), data fusion, seismic analysis and site forensics. The preliminary findings show the hypothetical scenario in NPE 2015 most probably is an uncontained event resulted high release of radionuclide to the air. (author)

  13. Spent nuclear fuel project, Cold Vacuum Drying Facility human factors engineering (HFE) analysis: Results and findings

    International Nuclear Information System (INIS)

    Garvin, L.J.

    1998-01-01

    This report presents the background, methodology, and findings of a human factors engineering (HFE) analysis performed in May, 1998, of the Spent Nuclear Fuels (SNF) Project Cold Vacuum Drying Facility (CVDF), to support its Preliminary Safety Analysis Report (PSAR), in responding to the requirements of Department of Energy (DOE) Order 5480.23 (DOE 1992a) and drafted to DOE-STD-3009-94 format. This HFE analysis focused on general environment, physical and computer workstations, and handling devices involved in or directly supporting the technical operations of the facility. This report makes no attempt to interpret or evaluate the safety significance of the HFE analysis findings. The HFE findings presented in this report, along with the results of the CVDF PSAR Chapter 3, Hazards and Accident Analyses, provide the technical basis for preparing the CVDF PSAR Chapter 13, Human Factors Engineering, including interpretation and disposition of findings. The findings presented in this report allow the PSAR Chapter 13 to fully respond to HFE requirements established in DOE Order 5480.23. DOE 5480.23, Nuclear Safety Analysis Reports, Section 8b(3)(n) and Attachment 1, Section-M, require that HFE be analyzed in the PSAR for the adequacy of the current design and planned construction for internal and external communications, operational aids, instrumentation and controls, environmental factors such as heat, light, and noise and that an assessment of human performance under abnormal and emergency conditions be performed (DOE 1992a)

  14. Characteristics, finite element analysis, test description, and preliminary test results of the STM4-120 kinematic Stirling engine

    Science.gov (United States)

    Linker, K. L.; Rawlinson, K. S.; Smith, G.

    1991-10-01

    The Department of Energy's Solar Thermal Program has, as one of its program elements, the development and evaluation of conversion device technologies applicable to dish-electric systems. The primary research and development combines a conversion device (heat engine), solar receiver, and generator mounted at the focus of a parabolic dish concentrator. The Stirling-cycle heat engine was identified as the conversion device for dish-electric with the most potential for meeting the program's goals for efficiency, reliability, and installed cost. To advance the technology toward commercialization, Sandia National Laboratories has acquired a Stirling Thermal Motors, Inc. kinematic Stirling engine, STM4-120, for evaluation. The engine is being bench-tested at Sandia's Engine Test Facility and will be combined later with a solar receiver for on-sun evaluation. This report presents the engine characteristics, finite element analyses of critical engine components, test system layout, instrumentation, and preliminary performance results from the bench test.

  15. Socioeconomic issues and analyses for radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    Ulland, L.

    1988-01-01

    Radioactive Waste facility siting and development can raise major social and economic issues in the host area. Initial site screening and analyses have been conducted for both potential high-level and low-level radioactive waste facilities; more detailed characterization and analyses are being planned. Results of these assessments are key to developing community plans that identify and implement measures to mitigate adverse socioeconomic impacts. Preliminary impact analyses conducted at high-level sites in Texas and Nevada, and site screening activities for low-level facilities in Illinois and California have identified a number of common socioeconomic issues and characteristics as well as issues and characteristics that differ between the sites and the type of facilities. Based on these comparisons, implications for selection of an appropriate methodology for impact assessment and elements of impact mitigation are identified

  16. Preliminary Results Of LOCA Problem For APR1400 Reactor

    International Nuclear Information System (INIS)

    Le Dai Dien; Hoang Minh Giang; Le Thi Thu; Vo Thi Huong; Le Van Hong

    2011-01-01

    Several features of NPP with APR1400 nuclear reactor during a loss of coolant accident (LOCA) are investigated in this study. The report describes some main design characteristics of an engineering safety systems of APR1400 and the thermal hydraulic calculation results for steady-state using MARS and RELAP/SCDAPSIM codes. Large Break LOCA accident has been analyzed and evaluated based on acceptable criteria for ECCS given by US NRC. The results from cold leg break LOCA with broken area of 0.0465 m 2 in case of high pressure safety injection system (HPSI) failed to operate or 2 and 4 HPSI pumps are activated. The preliminary results of this work is a part of collaboration between INST researchers and KAERI experts in using RELAP tool for safety analysis of NPPs. (author)

  17. Radiolabelling of RC-160: preliminary results

    International Nuclear Information System (INIS)

    Verdera, E.S.; Balter Binsky, H.S.; Robles, A.M.; Rodriguez, G.; Souto, B.; Laiz, J.; Oliver, P.; Leon, E.

    1998-01-01

    Vapreotide (RC-160) was labelled with 125 I using Chloramine-T and Iodogen methods and with 99m Tc by a direct method with sodium ditionite as reducing agent in the presence of ascorbic acid. Several methods of purification and quality control were evaluated. Yields of the reactions and of purification steps were calculated. The results obtained for the radioiodination reactions showed higher yields when limiting Chloramine-T method was used. Labelling of RC-160 with 99m Tc indicated better yields when high radioactivity concentration of the radionuclide was used. Stability of the products obtained was assessed at different post-labelling times by selected quality control methods: Sep-Pak cartridge as purification method and chromatography by RP-HPLC and ITLC-SG using saline solution as solvent. It was demonstrated that I-125-RC-160 and Tc-99m-RC-160 were stable during five weeks (at -20 deg. C) and 6 hours (at room temperature) respectively. Preliminary biodistribution of Tc-99m-RC-160 in normal rats and mice were done showing different biological behaviour compared with control animals injected with pertechnetate. In conclusion, RC-160 was successfully labelled with both radionuclides, with radiochemical purity higher than 95%. These results encourage further research work in animal models as well as to investigate the biochemical behaviour of radiolabelled peptide. (author)

  18. Next generation storage facility

    International Nuclear Information System (INIS)

    Schlesser, J.A.

    1994-01-01

    With diminishing requirements for plutonium, a substantial quantity of this material requires special handling and ultimately, long-term storage. To meet this objective, we at Los Alamos, have been involved in the design of a storage facility with the goal of providing storage capabilities for this and other nuclear materials. This paper presents preliminary basic design data, not for the structure and physical plant, but for the container and arrays which might be configured within the facility, with strong emphasis on criticality safety features

  19. Preliminary results from the Arecibo Heating Experiment (HEX): HF to GNSS

    Science.gov (United States)

    Jackson-Booth, N.; Penney, R.; Bernhardt, P. A.; Martin, P. L.; Buckland, R.; Morton-Orr, T.; Nossa, E.; Buckland, R.

    2017-12-01

    The ionosphere is subject to many solar and terrestrial influences that can generate disturbances, causing degradation to modern communication and navigational systems. Whilst the disturbances are normally caused by natural phenomena such as hurricanes, earthquakes and solar storms; they can also be generated by artificially modifying the ionosphere. Artificial Ionospheric Modification (AIM) attempts to alter a small region of the ionosphere in order to perturb the RF propagation environment. This can be achieved through injecting the ionosphere with aerosols, chemicals or radio signals. The effects of any such modification can be detected through the deployment of sensors, including ground based high-frequency (HF) sounders and dual-band Global Navigation Satellite System (GNSS) receivers. HF sounders allow measurements of the bottom-side of the ionosphere. GNSS receivers offer a convenient means of obtaining information about the ionosphere, including ionospheric disturbances through changes in the derived total electron content information. The Heating EXperiment (HEX), which took place in March and May 2017, was designed to further our understanding of the phenomena caused by artificially heating a small region of the ionosphere, using the Arecibo facility in Puerto Rico. This was achieved by utilizing a HF measurement experiment spread between Texas and Trinidad and the deployment of a small scale travelling ionospheric disturbance (TID) network near the heater. The TID network comprised three GNSS receivers along baselines of approximately 4 km, located 20 km north of the heater. This paper presents preliminary results from the HEX campaign, including evidence of heating-induced disturbances enhancing propagation between Virginia and Trinidad. The implications of generated irregularities on GNSS will also be discussed.

  20. Citizens' views about the proposed Hartsville Nuclear Power Plant: a preliminary report of potential social impacts

    International Nuclear Information System (INIS)

    Schuller, C.R.; Fowler, J.R.; Mattingly, T.J. Jr.; Sundstrom, E.; Lounsbury, J.; Passino, E.M.; Dowell, D.A.; Hutton, B.J.

    1975-05-01

    Preliminary results of a survey of public attitudes toward a proposed nuclear power plant facility at Hartsville, Tennessee are summarized. The purpose of the study was to aid in developing better methods for understanding the social consequences of energy facility development. The report is based on data obtained in interviews with 350 randomly selected respondents administered in Trousdale County, Tennessee during February 1975. (U.S.)

  1. The Majorana Demonstrator Status and Preliminary Results

    Science.gov (United States)

    Yu, C.-H.; Alvis, S. I.; Arnquist, I. J.; Avignone, F. T.; Barabash, A. S.; Barton, C. J.; Bertrand, F. E.; Bode, T.; Brudanin, V.; Busch, M.; Buuck, M.; Caldwell, T. S.; Chan, Y.-D.; Christofferson, C. D.; Chu, P.-H.; Cuesta, C.; Detwiler, J. A.; Dunagan, C.; Efremenko, Yu; Ejiri, H.; Elliott, S. R.; Gilliss, T.; Giovanetti, G. K.; Green, M.; Gruszko, J.; Guinn, I. S.; Guiseppe, V. E.; Haufe, C. R.; Hehn, L.; Henning, R.; Hoppe, E. W.; Howe, M. A.; Keeter, K. J.; Kidd, M. F.; Konovalov, S. I.; Kouzes, R. T.; Lopez, A. M.; Martin, R. D.; Massarczyk, R.; Meijer, S. J.; Mertens, S.; Myslik, J.; Othman, G.; Pettus, W.; Poon, A. W. P.; Radford, D. C.; Rager, J.; Reine, A. L.; Rielage, K.; Ruof, N. W.; Shanks, B.; Shirchenko, M.; Suriano, A. M.; Tedeschi, D.; Varner, R. L.; Vasilyev, S.; Vetter, K.; Vorren, K.; White, B. R.; Wilkerson, J. F.; Wiseman, C.; Xu, W.; Yakushev, E.; Yumatov, V.; Zhitnikov, I.; Zhu, B. Z.

    2018-05-01

    The MAJORANA Collaboration is using an array of high-purity Ge detectors to search for neutrinoless double-beta decay in 76Ge. Searches for neutrinoless double-beta decay are understood to be the only viable experimental method for testing the Majorana nature of the neutrino. Observation of this decay would imply violation of lepton number, that neutrinos are Majorana in nature, and provide information on the neutrino mass. The MAJORANA DEMONSTRATOR comprises 44.1 kg of p-type point-contact Ge detectors (29.7 kg enriched in 76Ge) surrounded by a low-background shield system. The experiment achieved a high efficiency of converting raw Ge material to detectors and an unprecedented detector energy resolution of 2.5 keV FWHM at Qββ. The MAJORANA collaboration began taking physics data in 2016. This paper summarizes key construction aspects of the Demonstrator and shows preliminary results from initial data.

  2. Preliminary analysis of the operating characteristics of a generic repository receiving facility: Status report

    International Nuclear Information System (INIS)

    1985-10-01

    The operating characteristics of a repository receiving facility structured around current technology and practices have been reviewed. Cask turnaround times and operator doses were estimated. Large throughout and long-term receiving operations at a nuclear waste repository result in an unprecedented number of casks being handled. While the current generation of material-handling equipment is adequate to process the casks, personnel radiation exposures for the generic facility analyzed are unacceptably high. This emphasizes the need for development of occupational radiation exposure control concepts for application in repository receiving facilities. 3 refs., 22 figs., 6 tabs

  3. Preliminary results for X-ray phase contrast micro-tomography on the biomedical imaging beamline at SSRF

    International Nuclear Information System (INIS)

    Chen Rongchang; Du Guohao; Xie Honglan; Deng Biao; Tong Yajun; Hu Wen; Xue Yanling; Chen Can; Ren Yuqi; Zhou Guangzhao; Wang Yudan; Xiao Tiqiao; Xu Hongjie; Zhu Peiping

    2009-01-01

    With X-ray phase contrast micro-tomography(CT), one is able to obtain edge-enhanced image of internal structure of the samples. This allows visualization of the fine internal features for biology tissues, which is not able to resolve by conventional absorption CT. After preliminary modulation, monochromatic X-rays (8-72.5 keV) are available for experiments on the experimental station of the biomedical imaging beamline at Shanghai Synchrotron Radiation Facility(SSRF). In this paper, we report the in line phase contrast micro-tomography(IL-XPCT) of biology sample (locust) on the beamline. The reconstruct slice images and three dimensional rendering images of the locust were obtained, with clearly visible images of locus's wing, surface texture and internal tissue distribution. (authors)

  4. Barkhausen Effect and Acoustic Emission in a Metallic Glass - Preliminary Results

    International Nuclear Information System (INIS)

    Lopez Sanchez, R.; Lopez Pumarega, M.I.; Armeite, M.; Piotrkowski, R.; Ruzzante, J.E.

    2004-01-01

    Magneto Acoustic Emission, which is Barkhausen Noise (BN) and Acoustic Emission (AE), depends on microstructure and existing residual stresses in magnetic materials. Preliminary results obtained by magnetization along two perpendicular directions on a metal glass foil are presented. Signals were analyzed with Statistic, Fast Fourier and Wavelet methods. Results are part of a Joint Research Project of the Faculty of Science, Cantabria University, Spain, and the Elastic Waves Group of the National Atomic Energy Commission, Argentina

  5. Evaluation methods for hospital facilities

    DEFF Research Database (Denmark)

    Fronczek-Munter, Aneta

    2013-01-01

    according to focus areas and proposes which evaluation methods to use in different building phases of healthcare facilities. Hospital evaluations with experts and users are also considered; their subjective view on space, function, technology, usability and aesthetics. Results & solutions: This paper...... presents the different methods for evaluating buildings in use in a new model, the Evaluation Focus Flower, and proposes which evaluation methods are suitable for various aims and building phases, i.e. which is giving best input for the initial briefing process of new hospital facilities with ambition...... of creating buildings with enhanced usability. Additionally various evaluation methods used in hospital cases in Denmark and Norway are presented. Involvement of users is proposed, not just in defining requirements but also in co-creation/design and evaluation of solutions. The theories and preliminary...

  6. Preliminary Feasibility, Design, and Hazard Analysis of a Boiling Water Test Loop Within the Idaho National Laboratory Advanced Test Reactor National Scientific User Facility

    International Nuclear Information System (INIS)

    Gerstner, Douglas M.

    2009-01-01

    The Advanced Test Reactor (ATR) is a pressurized light-water reactor with a design thermal power of 250 MW. The principal function of the ATR is to provide a high neutron flux for testing reactor fuels and other materials. The ATR and its support facilities are located at the Idaho National Laboratory (INL). A Boiling Water Test Loop (BWTL) is being designed for one of the irradiation test positions within the. The objective of the new loop will be to simulate boiling water reactor (BWR) conditions to support clad corrosion and related reactor material testing. Further it will accommodate power ramping tests of candidate high burn-up fuels and fuel pins/rods for the commercial BWR utilities. The BWTL will be much like the pressurized water loops already in service in 5 of the 9 'flux traps' (region of enhanced neutron flux) in the ATR. The loop coolant will be isolated from the primary coolant system so that the loop's temperature, pressure, flow rate, and water chemistry can be independently controlled. This paper presents the proposed general design of the in-core and auxiliary BWTL systems; the preliminary results of the neutronics and thermal hydraulics analyses; and the preliminary hazard analysis for safe normal and transient BWTL and ATR operation

  7. Modelled and Observed Diurnal SST Signals: "SSTDV:R.EX.-IM.A.M." Project Preliminary Results

    DEFF Research Database (Denmark)

    Karagali, Ioanna; Høyer, Jacob; LeBorgne, Pierre

    2013-01-01

    This study presents some of the preliminary results from the ESA Support To Science Element (STSE) funded project on the Diurnal Variability of the Sea Surface Temperature, regarding its Regional Extend and Implications in Atmospheric Modelling (SSTDV:R.EX.–IM.A.M.). During this phase of the proj......This study presents some of the preliminary results from the ESA Support To Science Element (STSE) funded project on the Diurnal Variability of the Sea Surface Temperature, regarding its Regional Extend and Implications in Atmospheric Modelling (SSTDV:R.EX.–IM.A.M.). During this phase...

  8. Disposition of TA-33-21, a plutonium contaminated experimental facility

    International Nuclear Information System (INIS)

    Cox, E.J.; Garde, R.; Valentine, A.M.

    1975-01-01

    The report discusses the decontamination, demolition and disposal of a plutonium contaminated experimental physics facility which housed physics experiments with plutonium from 1951 until 1960. The results of preliminary decontamination efforts in 1960 are reported along with health physics, waste management, and environmental aspects of final disposition work accomplished during 1974 and 1975. (auth)

  9. Preliminary results of the Spacelab 2 superfluid helium experiment

    International Nuclear Information System (INIS)

    Mason, P.V.; Collins, D.J.; Elleman, D.D.; Jackson, H.W.; Wang, T.

    1986-01-01

    An experiment to investigate the properties of superfluid helium in a microgravity environment flew on the Shuttle on the Spacelab 2 mission in July and August of 1985. This paper summarizes the flight experiment and describes some preliminary results. The experiment comprised an investigation of long-wavelength third-sound waves in micron-thick films, a study of the motions of superfluid helium under milli-g and micro-g accelerations, and measurements of the fluctuations in temperature associated with the small motions of the bulk helium. An additional objective was to qualify and characterize a reflyable, space-compatible cryostat

  10. Initial electron-beam characterizations for the Los Alamos APEX Facility

    Energy Technology Data Exchange (ETDEWEB)

    Lumpkin, A.H.; Feldman, R.B.; Apgar, S.A.; Feldman, D.W.; O' Shea, P.G. (Los Alamos National Lab., NM (United States)); Fiorito, R.B.; Rule, D.W. (Naval Surface Warfare Center, Silver Spring, MD (United States))

    1991-01-01

    The ongoing upgrade of the Los Alamos Free-Electron Laser (FEL) Facility involves the addition of a photoelectric injector (PEI) and acceleration capability to about 40 MeV. The electron-beam and high-speed diagnostics provide key measurements of charge, beam position and profile, divergence emittance, energy (centroid, spread, slew, and extraction efficiency), micropulse duration, and phase stability. Preliminary results on the facility include optical transition radiation interferometer measurements of divergence (1 to 2 mrad), FEL extraction efficiency (0.6 {plus minus} 0.2%), and drive laser phase stability (< 2 ps (rms)). 10 refs.

  11. Initial electron-beam characterizations for the Los Alamos APEX Facility

    Energy Technology Data Exchange (ETDEWEB)

    Lumpkin, A.H.; Feldman, R.B.; Apgar, S.A.; Feldman, D.W.; O`Shea, P.G. [Los Alamos National Lab., NM (United States); Fiorito, R.B.; Rule, D.W. [Naval Surface Warfare Center, Silver Spring, MD (United States)

    1991-12-31

    The ongoing upgrade of the Los Alamos Free-Electron Laser (FEL) Facility involves the addition of a photoelectric injector (PEI) and acceleration capability to about 40 MeV. The electron-beam and high-speed diagnostics provide key measurements of charge, beam position and profile, divergence emittance, energy (centroid, spread, slew, and extraction efficiency), micropulse duration, and phase stability. Preliminary results on the facility include optical transition radiation interferometer measurements of divergence (1 to 2 mrad), FEL extraction efficiency (0.6 {plus_minus} 0.2%), and drive laser phase stability (< 2 ps [rms]). 10 refs.

  12. Hematite nuclear fuel cycle facility decommissioning

    International Nuclear Information System (INIS)

    Hayes, K.

    2004-01-01

    Westinghouse Electric Company LLC ('Westinghouse') acquired a nuclear fuel processing plant at Hematite, Missouri ('Hematite', the 'Facility', or the 'Plant') in April 2000. The plant has subsequently been closed, and its operations have been relocated to a newer, larger facility. Westinghouse has announced plans to complete its clean-up, decommissioning, and license retirement in a safe, socially responsible, and environmentally sound manner as required by internal policies, as well as those of its parent company, British Nuclear Fuels plc. ('BNFL'). Preliminary investigations have revealed the presence of environmental contamination in various areas of the facility and grounds, including both radioactive contamination and various other substances related to the nuclear fuel processing operations. The disparity in regulatory requirements for radiological and nonradiological contaminants, the variety of historic and recent operations, and the number of previous owners working under various contractual arrangements for both governmental and private concerns has resulted in a complex project. This paper discusses Westinghouse's efforts to develop and implement a comprehensive decontamination and decommissioning (D and D) strategy for the facility and grounds. (author)

  13. Beam Characterizations at Femtosecond Electron Beam Facility

    CERN Document Server

    Rimjaem, Sakhorn; Kangrang, Nopadol; Kusoljariyakul, Keerati; Rhodes, Michael W; Saisut, Jatuporn; Thongbai, Chitrlada; Vilaithong, Thiraphat; Wichaisirimongkol, Pathom; Wiedemann, Helmut

    2005-01-01

    The SURIYA project at the Fast Neutron Research Facility (FNRF) has been established and is being commissioning to generate femtosecond electron pulses. Theses short pulses are produced by a system consisting of an S-band thermionic cathode RF-gun, an alpha magnet as a magnetic bunch compressor, and a linear accelerator. The characteristics of its major components and the beam characterizations as well as the preliminary experimental results will be presented and discussed.

  14. Preliminary results of natural radioactivity measurements in the southern part of Ethiopia

    International Nuclear Information System (INIS)

    Wollel Tiruneh, Getachew; Wodaje Kebede, Worku

    2008-01-01

    The paper presents the first results of natural radioactivity measurements in the Southern part of Ethiopia (Bale Zone-Oromiya Regional State). The preliminary results indicate that radiation levels in the mining areas of Kallido Mountain are elevated compared with those in the town of Negele Borena (background area). Both external gamma radiation and alpha surface contamination levels are significantly elevated above local background levels

  15. Preliminary results of natural radioactivity measurements in the southern part of Ethiopia

    Energy Technology Data Exchange (ETDEWEB)

    Wollel Tiruneh, Getachew [Ethiopian Radiation Protection Authority, PO Box 20486 code 1000, Addis-Ababa (Ethiopia)], E-mail: gwollel@yahoo.com; Wodaje Kebede, Worku [Ethiopian Radiation Protection Authority, PO Box 20486 code 1000, Addis-Ababa (Ethiopia)

    2008-11-15

    The paper presents the first results of natural radioactivity measurements in the Southern part of Ethiopia (Bale Zone-Oromiya Regional State). The preliminary results indicate that radiation levels in the mining areas of Kallido Mountain are elevated compared with those in the town of Negele Borena (background area). Both external gamma radiation and alpha surface contamination levels are significantly elevated above local background levels.

  16. Magnetic resonance imaging of the brain in neonates. Preliminary results

    International Nuclear Information System (INIS)

    Dumoulin, M.; Legrand, M.; Gremillet, C.; Lecouffe, P.; Rousseau, J.; Pruvo, J.P.; Marchandise, X.

    1991-01-01

    The place of neonatal cerebral MRI and its specific contribution compared with conventional imaging techniques were evaluated in 36 patients. The difficulties specific to the patient population studied met during this preliminary period are described, with their local solutions. A preliminary evaluation of the diagnostic and prognostic value of MRI according to the disease state and gestational age is presented. The specific contribution of MRI compared with transfontanellar ultrasonography and CT scan is discussed [fr

  17. Conceptual design of an in-space cryogenic fluid management facility, executive summary

    Science.gov (United States)

    Willen, G. S.; Riemer, D. H.; Hustvedt, D. C.

    1981-01-01

    The conceptual design of a Spacelab experiment to develop the technology associated with low gravity propellant management is summarized. The preliminary facility definition, conceptual design and design analysis, and facility development plan, including schedule and cost estimates for the facility, are presented.

  18. Preliminary summary of the ETF conceptual studies

    Science.gov (United States)

    Seikel, G. R.; Bercaw, R. W.; Pearson, C. V.; Owens, W. R.

    1978-01-01

    Power plant studies have shown the attractiveness of MHD topped steam power plants for baseload utility applications. To realize these advantages, a three-phase development program was initiated. In the first phase, the engineering data and experience were developed for the design and construction of a pilot plant, the Engineering Test Facility (ETF). Results of the ETF studies are reviewed. These three parallel independent studies were conducted by industrial teams led by the AVCO Everett Research Laboratory, the General Electric Corporation, and the Westinghouse Corporation. A preliminary analysis and the status of the critical evaluation of these results are presented.

  19. Investigation of polarized-proton target materials by differential calorimetry: preliminary results

    International Nuclear Information System (INIS)

    Hill, D.A.; Hill, J.J.

    1980-01-01

    A simple differential calorimeter was designed and operated for an investigation of the thermodynamic properties of polarized target materials. The calibration and use of the calorimeter are discussed, after a brief exposition of our motivation for this work. The results of a preliminary study of target materials is presented with emphasis on the relevance of the glass state to dynamic polarization in chemically-doped targets

  20. Seismic Hazard Maps for the Maltese Archipelago: Preliminary Results

    Science.gov (United States)

    D'Amico, S.; Panzera, F.; Galea, P. M.

    2013-12-01

    The Maltese islands form an archipelago of three major islands lying in the Sicily channel at about 140 km south of Sicily and 300 km north of Libya. So far very few investigations have been carried out on seismicity around the Maltese islands and no maps of seismic hazard for the archipelago are available. Assessing the seismic hazard for the region is currently of prime interest for the near-future development of industrial and touristic facilities as well as for urban expansion. A culture of seismic risk awareness has never really been developed in the country, and the public perception is that the islands are relatively safe, and that any earthquake phenomena are mild and infrequent. However, the Archipelago has been struck by several moderate/large events. Although recent constructions of a certain structural and strategic importance have been built according to high engineering standards, the same probably cannot be said for all residential buildings, many higher than 3 storeys, which have mushroomed rapidly in recent years. Such buildings are mostly of unreinforced masonry, with heavy concrete floor slabs, which are known to be highly vulnerable to even moderate ground shaking. We can surely state that in this context planning and design should be based on available national hazard maps. Unfortunately, these kinds of maps are not available for the Maltese islands. In this paper we attempt to compute a first and preliminary probabilistic seismic hazard assessment of the Maltese islands in terms of Peak Ground Acceleration (PGA) and Spectral Acceleration (SA) at different periods. Seismic hazard has been computed using the Esteva-Cornell (1968) approach which is the most widely utilized probabilistic method. It is a zone-dependent approach: seismotectonic and geological data are used coupled with earthquake catalogues to identify seismogenic zones within which earthquakes occur at certain rates. Therefore the earthquake catalogues can be reduced to the

  1. Response of lead-acid batteries to chopper-controlled discharge: Preliminary results

    Science.gov (United States)

    Cataldo, R. L.

    1978-01-01

    The preliminary results of simulated electric vehicle, chopper, speed controller discharge of a battery show energy output losses up to 25 percent compared to constant current discharges at the same average discharge current of 100 amperes. These energy losses are manifested as temperature rises during discharge, amounting to a two-fold increase for a 400-ampere pulse compared to the constant current case. Because of the potentially large energy inefficiency, the results suggest that electric vehicle battery/speed controller interaction must be carefully considered in vehicle design.

  2. Recent Results In Nuclear Astrophysics At The n_TOF Facility At CERN

    CERN Document Server

    Tagliente, Giuseppe; Andrzejewski, J; Audouin, L; Bacak, M; Balibrea, J; Barbagallo, M; Bečvář, F; Berthoumieux, E; Billowes, J; Bosnar, D; Brown, A; Caamaño, M; Calviño, F; Calviani, M; Cano-Ott, D; Cardella, R; Casanovas, A; Cerutti, F; Chen, Y H; Chiaveri, E; Colonna, N; Cortés, G; Cortés-Giraldo, M A; Cosentino; Damone, L A; Diakaki, M; Domingo-Pardo, C; Dressler, L R; Dupont, E; Durán, I; Fernández-Domínguez, B; Ferrari, A; Ferreira, P; Finocchiaro, P; Furman, V; Göbel, K; García, A R; Gawlik, A; Gilardoni, S; Glodariu, T; Gonçalves, I F; González, E; Griesmayer, E; Guerrero, C; Gunsing, F; Harada, H; Heinitz, S; Heyse, J; Jenkins, D G; Jericha, E; Käppeler, F; Kadi, Y; Kalamara, A; Kavrigin, P; Kimura, A; Kivel, N; Kokkoris, M; Krtička, M; Kurtulgil, D; Leal-Cidoncha, E; Lederer, C; Lerendegui-Marco, J; Leeb, H; Lo Meo, S; Lonsdale, S J; Macina, D; Marganiec, J; Martínez, T; Masi, A; Massimi, C; Mastinu, P; Mastromarco, M; Maugeri, E A; Mazzone, A; Mendoza, E; Mengoni, A; Mingrone, F; Milazzo, P M; Musumarra, A; Negret, A; Nolte, R; Oprea, A; Patronis, N; Pavlik, A; Perkowski, J; Porras, I; Praena, J; Quesada, J M; Radeck, D; Rauscher, T; Reifarth, R; Rubbia, C; Ryan, J A; Sabaté-Gilarte, M; Saxena, A; Schillebeeckx, P; Schumann, D; Sedyshev, P; Smith, A G; Sosnin, N V; Stamatopoulos, A; Tain, J L; Tarifeño-Saldivia, A; Valenta, S; Vannini, G; Variale, V; Vaz, P; Ventura, A; Vlachoudis, V; Vlastou, R; Wallner, A; Warren, S; Woods, P J; Żugec, P Č

    2017-01-01

    The neutron time of flight (n_TOF) facility at CERN is a spallation source characterized by a white neutron spectrum. The innovative features of the facility, in the two experimental areas, (20 m and 185 m), allow for an accurate determination of the neutron cross section for radioactive samples or for isotopes with small neutron capture cross section, of interest for Nuclear Astrophysics. The recent results obtained at n_TOF facility are presented.

  3. Preliminary results of spatially resolved ECR ion beam profile investigations

    International Nuclear Information System (INIS)

    Panitzsch, L.; Stalder, M.; Wimmer-Schweingruber, R.F.

    2012-01-01

    The profile of an ion beam produced in an Electron Cyclotron Resonance Ion Source (ECRIS) can vary greatly depending on the source settings and the ion-optical tuning. Strongly focussed ion beams form circular structures (hollow beams) as predicted by simulations and observed in experiments. Each of the rings is predicted to be dominated by ions with same or at least similar m/q-ratios due to ion-optical effects. To check this we performed a series of preliminary investigations to test the required tuning capabilities of our ion source. This includes beam focussing (A) and beam steering (B) using a 3D-movable extraction. Having tuned the source to deliver a beam of strongly focussed ions of different ion species and having steered this beam to match the transmittance area of the sector magnet we also recorded the ion charge state distribution of the strongly focussed beam profile at different, spatially limited positions (C). The preliminary results will be introduced within this paper: it appears that our 3D-movable extraction is very efficient to steer and to focus the beam strongly. The paper is followed by the slides of the presentation. (authors)

  4. 75 FR 71072 - Initiation and Preliminary Results of Antidumping Duty Changed Circumstances Review: Certain...

    Science.gov (United States)

    2010-11-22

    ... factors including, but not limited to: (1) Management; (2) production facilities; (3) supplier relationships; and (4) customer base. See Brass Sheet and Strip from Canada: Final Results of Antidumping Duty... y Placa resulted in little or no change in management, production facilities, supplier relationships...

  5. Preliminary Results of the CASCADE Hidden Sector Photon Search

    CERN Document Server

    Woollett, Nathan; Burt, Graeme; Chattopadhyay, Swapan; Dainton, John; Dexter, Amos; Goudket, Phillipe; Jenkins, Michael; Kalliokoski, Matti; Moss, Andrew; Pattalwar, Shrikant; Thakker, Trina; Williams, Peter

    2015-01-01

    Light shining through a wall experiments can be used to make measurements of photon-WISP couplings. The first stage of the CASCADE experiment at the Cockcroft Institute of Accelerator Science and Technology is intended to be a proof-of-principle experiment utilising standard microwave technologies to make a modular, cryogenic HSP detector to take advantage of future high-power superconducting cavity tests. In these proceedings we will be presenting the preliminary results of the CASCADE LSW experiment showing a peak expected exclusion of $1.10 \\times 10^{-8}$ in the mass range from 1.96$\\mu$eV to 5.38$\\mu$eV, exceeding current limits.

  6. V and V Efforts of Auroral Precipitation Models: Preliminary Results

    Science.gov (United States)

    Zheng, Yihua; Kuznetsova, Masha; Rastaetter, Lutz; Hesse, Michael

    2011-01-01

    Auroral precipitation models have been valuable both in terms of space weather applications and space science research. Yet very limited testing has been performed regarding model performance. A variety of auroral models are available, including empirical models that are parameterized by geomagnetic indices or upstream solar wind conditions, now casting models that are based on satellite observations, or those derived from physics-based, coupled global models. In this presentation, we will show our preliminary results regarding V&V efforts of some of the models.

  7. Ambient Assisted Living and ageing: preliminary results of RITA project.

    Science.gov (United States)

    Aquilano, Michela; Cavallo, Filippo; Bonaccorsi, Manuele; Esposito, Raffaele; Rovini, Erika; Filippi, Massimo; Esposito, Dario; Dario, Paolo; Carrozza, Maria Chiara

    2012-01-01

    The ageing of population is a social phenomenon that most of worldwide countries are facing. They are, and will be even more in the future, indeed trying to find solutions for improving quality of life of their elderly citizens. The project RITA wants to demonstrate that an update of the current socio-medical services with an Ambient Assisted Living (AAL) approach could improve the service efficiency and the quality of life of both elderly and caregiver. This paper presents the preliminary results obtained in RITA.

  8. Preliminary mapping of surficial geology of Midway Valley Yucca Mountain Project, Nye County, Nevada

    International Nuclear Information System (INIS)

    Wesling, J.R.; Bullard, T.F.; Swan, F.H.; Perman, R.C.; Angell, M.M.; Gibson, J.D.

    1992-04-01

    The tectonics program for the proposed high-level nuclear waste repository at Yucca Mountain in southwestern Nevada must evaluate the potential for surface faulting beneath the prospective surface facilities. To help meet this goal, Quaternary surficial mapping studies and photolineament analyses were conducted to provide data for evaluating the location, recency, and style of faulting with Midway Valley at the eastern base of Yucca Mountain, the preferred location of these surface facilities. This interim report presents the preliminary results of this work

  9. Preliminary safety analysis report for the Waste Characterization Facility

    International Nuclear Information System (INIS)

    1994-10-01

    This safety analysis report outlines the safety concerns associated with the Waste Characterization Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are to: define and document a safety basis for the Waste Characterization Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume. 142 refs., 38 figs., 39 tabs

  10. An Innovative Approach for Decreasing Fall Trauma Admissions from Geriatric Living Facilities: Preliminary Investigation.

    Science.gov (United States)

    Evans, Tracy; Gross, Brian; Rittenhouse, Katelyn; Harnish, Carissa; Vellucci, Ashley; Bupp, Katherine; Horst, Michael; Miller, Jo Ann; Baier, Ron; Chandler, Roxanne; Rogers, Frederick B

    2015-12-01

    Geriatric living facilities have been associated with a high rate of falls. We sought to develop an innovative intervention approach targeting geriatric living facilities that would reduce geriatric fall admissions to our Level II trauma center. In 2011, a Trauma Prevention Taskforce visited 5 of 28 local geriatric living facilities to present a fall prevention protocol composed of three sections: fall education, risk factor identification, and fall prevention strategies. To determine the impact of the intervention, the trauma registry was queried for all geriatric fall admissions attributed to patients living at local geriatric living facilities. The fall admission rate (total fall admissions/total beds) of the pre-intervention period (2010-2011) was compared with that of the postintervention period (2012-2013) at the 5 intervention and 23 control facilities. A P value fall admissions attributed to local geriatric living facilities (intervention: 179 fall admissions; control: 308 fall admissions). The unadjusted fall rate decreased at intervention facilities from 8.9 fall admissions/bed pre-intervention to 8.1 fall admissions/bed postintervention, whereas fall admission rates increased at control sites from 5.9 to 7.7 fall admissions/bed during the same period [control/intervention odds ratio (OR), 95% confidence interval (CI) = 1.32, 1.05-1.67; period OR, 95%CI = 1.55, 1.18-2.04, P = 0.002; interaction of control/intervention group and period OR 95% CI = 0.68, 0.46-1.00, P = 0.047]. An aggressive intervention program targeting high-risk geriatric living facilities resulted in a statistically significant decrease in geriatric fall admissions to our Level II trauma center.

  11. WEAVE: the next generation wide-field spectroscopy facility for the William Herschel Telescope : The next generation wide-field spectroscopy facility for the William Herschel Telescope

    NARCIS (Netherlands)

    Dalton, Gavin; Trager, Scott C.; Abrams, Don Carlos; Carter, David; Bonifacio, Piercarlo; Aguerri, J. Alfonso L.; MacIntosh, Mike; Evans, Chris; Lewis, Ian; Navarro, Ramon; Agocs, Tibor; Dee, Kevin; Rousset, Sophie; Tosh, Ian; Middleton, Kevin; Pragt, Johannes; Terrett, David; Brock, Matthew; Benn, Chris; Verheijen, Marc; Cano Infantes, Diego; Bevil, Craige; Steele, Iain; Mottram, Chris; Bates, Stuart; Gribbin, Francis J.; Rey, Jürg; Rodriguez, Luis Fernando; Delgado, Jose Miguel; Guinouard, Isabelle; Walton, Nic; Irwin, Michael J.; Jagourel, Pascal; Stuik, Remko; Gerlofsma, Gerrit; Roelfsma, Ronald; Skillen, Ian; Ridings, Andy; Balcells, Marc; Daban, Jean-Baptiste; Gouvret, Carole; Venema, Lars; Girard, Paul

    We present the preliminary design of the WEAVE next generation spectroscopy facility for the William Herschel Telescope (WHT), principally targeting optical ground-based follow up of upcoming ground-based (LOFAR) and spacebased (Gaia) surveys. WEAVE is a multi-object and multi-IFU facility utilizing

  12. Establishment and Operation of User Facilities

    International Nuclear Information System (INIS)

    Kim, Kye Ryung; Park, B. S.; Lim, Y. K.; Lee, S. K.; Jung, J. P.

    2005-08-01

    The final goal of this project is to establish the proton beam user facility which can offer the suitable proton beam for the user's demand. In the first phase we developed the key technologies that were required for the establishment of 20MeV and 100MeV proton user facilities. The user's demand survey was also achieved, and the test user facility was established on the results of the demand survey. Using the test facility, the users performed their pilot studies. Now, we have finished the conceptual design for 20MeV proton user facility. During the first phase we performed the user's demand survey and produced many materials related to the proton beam utilizations in domestic or abroad. The survey results were reflected on the establishment of the test user facility and the conceptual design of 20MeV/100MeV proton beam user facilities. We have developed the key technologies which concern to beam energy control, flux control, uniform irradiation, dose and uniformity measurement, proton energy measurement, SOBP(Spread-out Bragg Peak) system using a rotating range modulator, and carried out the conceptual design of 20MeV proton user facility. The test user facility has been constructed and operated for both verifying the developed key technologies and performing the user's preliminary experiments. 45MeV low flux user facility was constructed in 2003 and has performed a lot of irradiation experiments. The development of 1.8MeV test user facility was completed. Also the low energy user facility that KAERI kept was upgraded and used for many users. Therefore, we provided our users with various beams. On the other hand, the following activities were carried out, such as, inviting the oversea researchers, giving support to users to use the beam in domestic and abroad, discussing the beam utilization technologies by visiting the foreign user facilities, etc

  13. DECOMPOSITION OF TARS IN MICROWAVE PLASMA – PRELIMINARY RESULTS

    Directory of Open Access Journals (Sweden)

    Mateusz Wnukowski

    2014-07-01

    Full Text Available The paper refers to the main problem connected with biomass gasification - a presence of tar in a product gas. This paper presents preliminary results of tar decomposition in a microwave plasma reactor. It gives a basic insight into the construction and work of the plasma reactor. During the experiment, researches were carried out on toluene as a tar surrogate. As a carrier gas for toluene and as a plasma agent, nitrogen was used. Flow rates of the gases and the microwave generator’s power were constant during the whole experiment. Results of the experiment showed that the decomposition process of toluene was effective because the decomposition efficiency attained above 95%. The main products of tar decomposition were light hydrocarbons and soot. The article also gives plans for further research in a matter of tar removal from the product gas.

  14. Rough order of magnitude cost estimate for immobilization of 50 MT of plutonium sharing existing facilities at Hanford with pit disassembly and conversion facility: alternative 11

    International Nuclear Information System (INIS)

    DiSabatino, A.

    1998-01-01

    The purpose of this Cost Estimate Report is to identify preliminary capital and operating costs for a facility to immobilize 50 metric tons (nominal) of plutonium as a ceramic in an existing facility at Hanford, the Fuels and Materials Examination Facility (FMEF). The Pit Disassembly and Conversion Facility (PDCF), which is being costed in a separate report by LANL, will also be located in the FMEF in this co-location option

  15. Preliminary results of the alpha particle registration intercomparison ALRIT

    International Nuclear Information System (INIS)

    Paretzke, H.G.

    1976-01-01

    In view of the widespread interest in alpha particle registration with solid state nuclear track detectors, an international intercomparison of such measurements has been arranged. Sixteen sets of fourteen detectors each were sent to GSF-Neuherberg, there irradiated carefully with different alpha particle fields, and then returned for evaluation. Fourteen irradiation runs were made for each set simulating seven different irradiation situations commonly encountered in practical applications. The preliminary results of this intercomparison reported in this paper are based on the results of eight sets. They show good agreement with respect to the determination of track densities in the case of vertical incident alpha particles. Also the results obtained for determination of particle energies and angle of incidence in most cases were rather accurate. However, apparently it is still rather difficult to determine accurately and precisely the specific activity of alpha emitters on a thick filter positioned at some distance, i.e. for the case of 2π-incidence and a broad energy spectrum. (orig.) [de

  16. The demand factors for cesareans in Portugal – some preliminary results

    OpenAIRE

    Tavares, Aida Isabel; Rocha, Tania

    2012-01-01

    The aim of this work is to determine the demand factors for cesareans in Portugal. This work is exploratory and preliminary. Data is aggregated in NUTSII , for the period 2002-10. The number of cesareans performed is count data which requires the estimation of this panel data by a negative binomial with fixed effects. The main result is the evidence that there may be induced demand for cesareans in Portugal. Further research is needed.

  17. URAM-2 Cryogenic Irradiation Facility

    CERN Document Server

    Shabalin, E P; Kulikov, S A; Kulagin, E N; Melihov, V V; Belyakov, A A; Golovanov, L B; Borzunov, Yu T; Konstantinov, V I; Androsov, A V

    2002-01-01

    The URAM-2 irradiation facility has been built and mounted at the channel No. 3 of the IBR-2 reactor. It was constructed for study of radiolysis effects by fast neutron irradiation in some suitable for effective cold neutron production materials (namely: solid methane, methane hydrate, water ice, etc.). The facility cooling system is based on using liquid helium as a coolant material. The original charging block of the rig allows the samples to be loaded by condensing gas into irradiation cavity or by charging beads of ice prepared before. Preliminary tests for each facility block and assembling them at the working position were carried out. Use of the facility for study accumulation of chemical energy under irradiation at low temperature in materials mentioned above and its spontaneous release was started.

  18. Preliminary results on the Arecibo Pisces-Perseus Supercluster Survey

    Science.gov (United States)

    Cortes, Rosemary; Lebron, Mayra; Jones, Michael G.; Koopmann, Rebecca A.; Haynes, Martha P.; APPSS Team, Undergraduate ALFALFA Team, and the ALFALFA Team

    2018-01-01

    The Arecibo Pisces-Perseus Supercluster Survey (APPSS) aims to exploit the Baryonic Tully-Fisher Relation to derive distances and peculiar velocities of galaxies in and near the main ridge of the Pisces-Perseus Supercluster (PPS), one of the most prominent features of the Cosmic Web in the nearby Universe. The sample of galaxies contains ~ 600 sources in the low-mass range (8 Team institutions in which each group contributes to the analysis of a subset of the HI PPS data. In this poster, we will present the contributions of the U.P.R. team to the APPSS project. We will show the procedure used for the Arecibo HI data analysis, including some examples, and will show our preliminary results.

  19. Preliminary results of MR imaging of lymphoma: Distinguishing active tumor from benign residue

    International Nuclear Information System (INIS)

    Drace, J.; Baker, L.L.; Chang, P.; Castellino, R.A.

    1987-01-01

    Distinguishing tumor from benign posttreatment tissue based on both morphologic and tissue characteristics is critically important. Patients are studied before, during, and after treatment; at the time of recurrence; and on long-term follow-up. Multisection spin-echo sequences in orthogonal planes and a special single-section tissue characterization matrix of 16 different repetition time/echo time combinations are used. These basic images are used for cluster analysis (approximate fuzzy C means), T1-T2 synthetic images, linear combinations, and comparison with internal standards. Preliminary results in 35 patients imaged before treatment and 12 patients with follow-up examinations consistently show lymphoma masses to have complex architecture with high T2-weighted signal and moderate T1-weighted signal, distinct from posttreatment fibrosis. Uncommon components of active tumor with low T2-weighted signal appear distinct from fibrosis on T1-weighted images. Preliminary cluster analysis results show distinct clustering of active lymphoma versus fibrosis and biopsy-proved cystic degeneration

  20. Dissolved air flotation for treating wastewater of the nuclear industry. Preliminary results

    International Nuclear Information System (INIS)

    Ortiz-Oliveros, H.B.; Jimenez-Moleon, M.C.; Cruz-Gonzalez, D.

    2012-01-01

    Preliminary testing of dissolved air flotation (DAF) for wastewater treatment is presented. A combined coagulation-flocculation/DAF column system is used to remove oil and 60 Co from nuclear industry wastewater. In this work, operational conditions and coagulant/flocculant concentrations are optimized by varying pH. Determinations of air-solids ratio (G/S), retention time (θ), pressure (P), volume of depressurized air-water mixture (V), turbidity and 60 Co concentrations are reported. The effect of the treatment on the efficiency of separation of oily residues is also discussed. The results establish that the coagulant/flocculant system, formed by a modified polyamine (25 mgL -1 ) and a slightly cationic polyacrylamide (1.5 mgL -1 ), under specific operational conditions (pH = 7, mixing intensity Im 1 = 300 s -1 and Im 2 = 30 s -1 ), allowed the destabilization of colloidal matter, resulting in resistant flocs. It was concluded that by using G/S = 0.3, θ = 15 min, P = 620 kPa and V = 0.0012 m 3 , the greatest percentage removals of oil, turbidity, total cobalt and 60 Co were obtained. These preliminary results then show that dissolved air flotation represents a good alternative for treatment of nuclear industry wastewater contaminated with radionuclides. (author)

  1. Preliminary identification of contaminating α- and β-emitting radionuclides in nuclear facilities to be decommissioned through Digital Autoradiography

    International Nuclear Information System (INIS)

    Haudebourg, Raphael; Fichet, Pascal

    2016-01-01

    In previous publications, we presented how Digital Autoradiography (DA) could be of the most useful help in a preparation to decommissioning context: with this technique, a radiological mapping of the facility to dismantle can be obtained at a rate of around 2 weeks/100 m 2 . The technique is sensitive to all types of radioactivity (including α and 3 H- or 14 C-emitted β) and to both labile and fixed radioactivity. The method (radiosensitive screens exposure followed by a scanning step at the laboratory in a small-size device) neither involves nuclear material transportation, neither produces wastes, nor requires operators' presence during signal acquisition. The purpose is to accurately locate possible contamination spots, in order to relevantly perform targeted sampling and thus limit destructive analyses runs at the laboratory. In the latest developments, additional methods were implemented to analyze various nuclear samples (wastes, blocks, rubbles, pieces of furniture, drilled cores...) through this technique, to preliminary check for contamination, and to evaluate contamination location, homogeneity, and activity. These methods have proven themselves relevant and useful to build appropriate analyses and optimized decontamination protocols at the LASE (Laboratory of Analyses and Operators' Support). In this paper, we propose a new autoradiographic tool providing the identification of the contaminating radionuclide of a sample or an area, based on the stacking of several screens. The decrease of the signal screen after screen could be considered specific to one radionuclide. Modeling results obtained through Monte Carlo N-Particle transport code (MCNP) were in excellent agreement with experimental results obtained with sealed sources. Moreover, a method was developed to scan all the screens in the stack in only one run (instead of as many runs as screens) to shorten analysis duration. In the case of non-penetrating radiations (α particles, 3 H- or

  2. Do provisions to advance chemical facility safety also advance chemical facility security? An analysis of possible synergies

    DEFF Research Database (Denmark)

    Hedlund, Frank Huess

    2012-01-01

    The European Commission has launched a study on the applicability of existing chemical industry safety provisions to enhancing security of chemical facilities covering the situation in 18 EU Member States. This paper reports some preliminary analytical findings regarding the extent to which exist...

  3. Rough order of magnitude cost estimate for immobilization of 18.2 MT of plutonium sharing existing facilities at Hanford with MOX fuel fabrication facility: alternative 4B

    International Nuclear Information System (INIS)

    DiSabatino, A.

    1998-01-01

    The purpose of this Cost Estimate Report is to identify preliminary capital and operating costs for a facility to immobilize 18.2 metric tons (nominal) of plutonium as a ceramic in an existing facility at Hanford, the Fuels and Materials Examination Facility (FMEF). The MOX Fuel Fabrication Facility (MFFF), which is being costed in a separate report, will also be located in the FMEF in this co-location option

  4. Accumulation chamber as monitoring system for biogas emission from solid waste land filling: preliminary experimental results and elaborations on italian provincial scale

    International Nuclear Information System (INIS)

    Capaccioni, B.; Pirillo, L.; Didero, M.; Lucci, P.; Scartoni, P.; Tatano, F.

    2005-01-01

    On site CO 2 flux measurements with the static, not stationary accumulation chamber system were experimentally carried out in no. 5 MSW (active and closed) landfills located in the territory of the Province of Arezzo (Tuscany Region). Corresponding CO 2 emission flux maps were contoured and analysed, revealing a possible, preliminary geometrical classification of biogas dispersion: diffuse dispersion (internal), lateral/angular dispersion (internal), and external dispersion. Also specific (volume and surface) biogas emission parameters were calculated and graphically compared for the monitored inactive facilities [it

  5. The RPC-based IFR system at BaBar experiment: preliminary results

    International Nuclear Information System (INIS)

    Piccolo, Davide; Palano, A.; Bagnasco, S.; Buzzo, A.; Contri, R.; Crosetti, G.; Lo Vetere, M.; Macri, M.; Monge, R.; Passaggio, S.; Patrignani, C.; Robutti, E.; Santroni, A.; Anulli, F.; Baldini, R.; Calcaterra, A.; De Sangro, R.; Falciai, D.; Finocchiaro, G.; Patteri, P.; Peruzzi, I.; Piccolo, M.; Yu, Z.; Zallo, A.; Cavallo, N.; De Nardo, G.; Fabozzi, F.; Gatto, C.; Lista, L.; Paolucci, P.; Sciacca, C.; Bionta, R.; Wright, D.; Band, H.; Johnson, J.

    2002-01-01

    The IFR system is a RPC-based detector used to identify muons and neutral hadrons in the BaBar experiment at PEP II machine in SLAC. The RPC system can be used to reconstruct the trajectory of muons, pions and neutral hadrons interacting in the iron of the IFR. The different range and hit pattern allow to discriminate different particles crossing the IFR. An overview of the system design and the preliminary results on the IFR performances are reported

  6. The RPC-based IFR system at BaBar experiment preliminary results

    CERN Document Server

    Piccolo, D; Bagnasco, S; Baldini, R; Band, H R; Bionta, R; Buzzo, A; Calcaterra, A; Cavallo, N; Contri, R; Crosetti, G; De Nardo, Gallieno; De Sangro, R; Fabozzi, F; Falciai, D; Finocchiaro, G; Gatto, C; Johnson, J; Lista, L; Lo Vetere, M; Macri, M; Monge, R; Palano, A; Paolucci, P; Passaggio, S; Patrignani, C; Patteri, P; Peruzzi, I; Piccolo, M; Robutti, E; Santroni, A; Sciacca, C; Wright, D; Yu, Z; Zallo, A

    2002-01-01

    The IFR system is a RPC-based detector used to identify muons and neutral hadrons in the BaBar experiment at PEP II machine in SLAC. The RPC system can be used to reconstruct the trajectory of muons, pions and neutral hadrons interacting in the iron of the IFR. The different range and hit pattern allow to discriminate different particles crossing the IFR. An overview of the system design and the preliminary results on the IFR performances are reported.

  7. Evaluation of the CDTN's cementation facility using the results obtained in two different sizes: laboratory and facility

    International Nuclear Information System (INIS)

    Haucz, Maria Judite A.; Calabria, Jaqueline A. Almeida; Tello, Cledola Cassia O.; Candido, Francisco Donizete; Seles, Sandro Rogerio Novaes

    2011-01-01

    At CDTN R and D activities generate low-level radioactive wastes, among them the aqueous liquid ones, which need special attention due to their volumes. The usual treatment for these wastes is the volume reduction process using chemicals in order to change the radionuclides of the waste to an insoluble form. The resultant sludge is incorporated into cement in 200-liter drums using an in-line batch mixing system (CDTN Cementation Facility). The process parameters and solidified product quality are evaluated at the Cementation Laboratory (LABCIM), where tests are carried out to determine the viscosity, set time and density of the paste. In addition of the visual examination, compressive strength test and density are also established in the solidified product. In the cementation facility some pastes are also prepared for the immobilization of non-compactable waste, such as dump, scrap metal, wood, and other ones. This paper aims to present the study comparing the results of tests done in the pastes and products prepared in LABCIM and the ones obtained in CDTN's cementation facility, in order to check the efficiency of the cementation system. (author)

  8. Evaluation of the CDTN cementation facility using the results obtained in two different sizes: laboratory and facility

    International Nuclear Information System (INIS)

    Haucz, Maria Judite A.; Calabria, Jaqueline A. Almeida; Tello, Cledola Cassia O.; Candido, Francisco Donizete; Seles, Sandro Rogerio Novaes

    2011-01-01

    At CDTN R and D activities generate low-level radioactive wastes, among them the aqueous liquid ones, which need special attention due to their volumes. The usual treatment for these wastes is the volume reduction process using chemicals in order to change the radionuclides of the waste to an insoluble form. The resultant sludge is incorporated into cement in 200-liter drums using an in-line batch mixing system (CDTN Cementation Facility). The process parameters and solidified product quality are evaluated at the Cementation Laboratory (LABCIM), where tests are carried out to determine the viscosity, set time and density of the paste. In addition of the visual examination, compressive strength test and density are also established in the solidified product. In the cementation facility some pastes are also prepared for the immobilization of non-compactable waste, such as dump, scrap metal, wood, and other ones. This paper aims to present the study comparing the results of tests done in the pastes and products prepared in LABCIM and the ones obtained in CDTN's cementation facility, in order to check the efficiency of the cementation system. (author)

  9. KEEP Reading Research 1974: Overall Strategy and Preliminary Results. Technical Report No. 23.

    Science.gov (United States)

    Tharp, Roland G.; And Others

    Reading research is an important aspect of the Kamehameha Early Education Program. This report describes the overall strategy of the reading research program, which is based on a conceptual framework that divides lines of inquiry into motivation, linguistics, instructional procedures, and correlational analysis. Preliminary results for each of…

  10. Preliminary hazard analysis for the Brayton Isotope Ground Demonstration System (including vacuum test chamber)

    International Nuclear Information System (INIS)

    Miller, L.G.

    1975-01-01

    The Preliminary Hazard Analysis (PHA) of the BIPS-GDS is a tabular summary of hazards and undesired events which may lead to system damage or failure and/or hazard to personnel. The PHA reviews the GDS as it is envisioned to operate in the Vacuum Test Chamber (VTC) of the GDS Test Facility. The VTC and other equipment which will comprise the test facility are presently in an early stage of preliminary design and will undoubtedly undergo numerous changes before the design is frozen. The PHA and the FMECA to follow are intended to aid the design effort by identifying areas of concern which are critical to the safety and reliability of the BIPS-GDS and test facility

  11. Lead coolant test facility systems design, thermal hydraulic analysis and cost estimate

    Energy Technology Data Exchange (ETDEWEB)

    Khericha, Soli, E-mail: slk2@inel.gov [Battelle Energy Alliance, LLC, Idaho National Laboratory, Idaho Falls, ID 83415 (United States); Harvego, Edwin; Svoboda, John; Evans, Robert [Battelle Energy Alliance, LLC, Idaho National Laboratory, Idaho Falls, ID 83415 (United States); Dalling, Ryan [ExxonMobil Gas and Power Marketing, Houston, TX 77069 (United States)

    2012-01-15

    The Idaho National Laboratory prepared a 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 coolant. Based on review of current world lead or lead-bismuth test facilities and research needs listed in the Generation IV Roadmap, five broad areas of requirements were identified as listed below: Bullet Develop and demonstrate feasibility of submerged heat exchanger. Bullet Develop and demonstrate open-lattice flow in electrically heated core. Bullet Develop and demonstrate chemistry control. Bullet Demonstrate safe operation. Bullet Provision for future testing. This paper discusses the preliminary design of systems, thermal hydraulic analysis, and simplified cost estimated. 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 4200 Degree-Sign 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 (in 2006 $). It is also estimated that the facility will require two years to be constructed and ready for operation.

  12. Escherichia coli O26 IN RAW BUFFALO MILK: PRELIMINARY RESULTS

    Directory of Open Access Journals (Sweden)

    A. Rella

    2013-02-01

    Full Text Available Escherichia coli O26 is considered to be one of the most important food-borne pathogen. In this study, 120 buffalo milk samples collected in Lazio and in Apulia regions were tested for the presence of E. coli O26. One buffalo milk sample (0,8% tested positive for E. coli O26; the isolate was positive at the verocytotoxicity test and it showed resistance properties to different antimicrobial classes. These preliminary results highlight the need to monitor the foods of animal origin used for production and eaten by a wide range of persons, respect VTEC organism.

  13. Preliminary Report of a Pilot Tele-Health Palliative Care and Bioethics Program for Residents in Skilled Nursing Facilities

    Directory of Open Access Journals (Sweden)

    Sean O’Mahony

    2009-12-01

    Full Text Available Currently about 25% of Americans die in nursing homes, many with poorly controlled pain and other symptoms, with minimal provisions for psychosocial support. New models are necessary to lessen structural and process barriers to give effective end-of-life care in nursing homes. Objectives: 1 To extend hospital-based Bioethics Consultation Services (BCS and Palliative Care Services (PCS at Montefiore Medical Center (MMC in the Bronx to two local Skilled Nursing Facilities (SNFs, Morningside House Aging in America (MSH using direct face-to-face consultations and Beth Abraham Health Systems (BAHS via video consultations (VC; 2 Achieve improvements in quality of life and comfort for elderly residents and their families; 2a Improve the level of practice and increase staff satisfaction with palliative care content-related knowledge and bioethical analysis. Methods: We report preliminary findings of this two group quasi experimental project with results of pre- and post- tests rating content-related knowledge in aspects of end-of-life care for staff. Select pre-test and post-test questions were given to physicians and other staff, but were re-configured for, registered and licensed practice nurses, social workers, and certified nursing assistants from the End-of-Life Physician Education Resource Center (EPERC. Patient, family, and staff ratings of the quality of palliative care were measured with a Palliative Outcomes Scale (POS one week prior to and post consultation. Results: 72 staff attended in-services; 53 completed pre-tests and 49 post-tests. Overall knowledge scores increased for 9 of the 16 items that were analyzed. There were improvements in knowledge scores in 12 of 16 items tested for staff content related knowledge which were statistically significant in regard to management of cancer pain from 63.8% to 81.5% (p = 0.03 and a trend to significance for assessment and management of delirium from 31.6% to 61.9% (p = 0.073. Seventy five POS

  14. SmallWorld Behavior of the Worldwide Active Volcanoes Network: Preliminary Results

    Science.gov (United States)

    Spata, A.; Bonforte, A.; Nunnari, G.; Puglisi, G.

    2009-12-01

    We propose a preliminary complex networks based approach in order to model and characterize volcanoes activity correlation observed on a planetary scale over the last two thousand years. Worldwide volcanic activity is in fact related to the general plate tectonics that locally drives the faults activity, that in turn controls the magma upraise beneath the volcanoes. To find correlations among different volcanoes could indicate a common underlying mechanism driving their activity and could help us interpreting the deeper common dynamics controlling their unrest. All the first evidences found testing the procedure, suggest the suitability of this analysis to investigate global volcanism related to plate tectonics. The first correlations found, in fact, indicate that an underlying common large-scale dynamics seems to drive volcanic activity at least around the Pacific plate, where it collides and subduces beneath American, Eurasian and Australian plates. From this still preliminary analysis, also more complex relationships among volcanoes lying on different tectonic margins have been found, suggesting some more complex interrelationships between different plates. The understanding of eventually detected correlations could be also used to further implement warning systems, relating the unrest probabilities of a specific volcano also to the ongoing activity to the correlated ones. Our preliminary results suggest that, as for other many physical and biological systems, an underlying organizing principle of planetary volcanoes activity might exist and it could be a small-world principle. In fact we found that, from a topological perspective, volcanoes correlations are characterized by the typical features of small-world network: a high clustering coefficient and a low characteristic path length. These features confirm that global volcanoes activity is characterized by both short and long-range correlations. We stress here the fact that numerical simulation carried out in

  15. The SNS target station preliminary Title I shielding analyses

    International Nuclear Information System (INIS)

    Johnson, J.O.; Santoro, R.T.; Lillie, R.A.; Barnes, J.M.; McNeilly, G.S.

    2000-01-01

    The Department of Energy (DOE) has given the Spallation Neutron Source (SNS) project approval to begin Title I design of the proposed facility to be built at Oak Ridge National Laboratory (ORNL). During the conceptual design phase of the SNS project, the target station bulk-biological shield was characterized and the activation of the major targets station components was calculated. Shielding requirements were assessed with respect to weight, space, and dose-rate constraints for operating, shut-down, and accident conditions utilizing the SNS shield design criteria, DOE Order 5480.25, and requirements specified in 10 CFR 835. Since completion of the conceptual design phase, there have been major design changes to the target station as a result of the initial shielding and activation analyses, modifications brought about due to engineering concerns, and feedback from numerous external review committees. These design changes have impacted the results of the conceptual design analyses, and consequently, have required a re-investigation of the new design. Furthermore, the conceptual design shielding analysis did not address many of the details associated with the engineering design of the target station. In this paper, some of the proposed SNS target station preliminary Title I shielding design analyses will be presented. The SNS facility (with emphasis on the target station), shielding design requirements, calculational strategy, and source terms used in the analyses will be described. Preliminary results and conclusions, along with recommendations for additional analyses, will also be presented. (author)

  16. Thermal-hydraulically controlled blowdown tests in the experimental facility COSIMA to study PWR fuel behavior: experimental and theoretical results

    International Nuclear Information System (INIS)

    Class, G.; Hain, K.; Meyder, R.

    1978-01-01

    The fuel behavior in the blow-down phase of a LOCA is of importance for fuel rods with high internal pressure and high rod power, because of the effects on clad failure of the small cladding deformations occurring. The operating results of the COSIMA facility show that, on the basis of the new developments for measuring technique and fuel rod simulators performed, reactor relevant blow-down performances can be conducted in a controlled and reproduceable manner. The mechanical and thermal-hydraulic states occurring in the test bed may be subject to computational checking. This permits on one hand to improve the computing models and on the other yields a confirmation of the high state of development of the available computer codes. Therefore it appears that, with the results from COSIMA and the associated theoretical work in the field of the blow-down process, difficult to treat experimentally, an essential contribution to verifying the models for accident calculations is given. The work scheduled for the next about 1 1/2 years will serve to further support the rather preliminary results and to extend the range of then application. (orig.) [de

  17. Preliminary results from the MINERvA experiment

    International Nuclear Information System (INIS)

    Harris, Deborah A.

    2011-01-01

    The MINERvA experiment, operating since 2009 in the NuMI neutrino beam line at Fermilab, has collected neutrino and antineutrino scattering data on a variety of nuclear targets. The detector is designed to identify events originating in plastic scintillator, lead, carbon, iron, water, and liquid helium. The goal of the experiment is to measure inclusive and exclusive cross sections for neutrino and antineutrino with much greater precision than previous experiments. We present preliminary kinematic distributions for charged current quasi-elastic scattering and other processes.

  18. Results from colliding magnetized plasma jet experiments executed at the Trident laser facility

    Science.gov (United States)

    Manuel, M. J.-E.; Rasmus, A. M.; Kurnaz, C. C.; Klein, S. R.; Davis, J. S.; Drake, R. P.; Montgomery, D. S.; Hsu, S. C.; Adams, C. S.; Pollock, B. B.

    2015-11-01

    The interaction of high-velocity plasma flows in a background magnetic field has applications in pulsed-power and fusion schemes, as well as astrophysical environments, such as accretion systems and stellar mass ejections into the magnetosphere. Experiments recently executed at the Trident Laser Facility at the Los Alamos National Laboratory investigated the effects of an expanding aluminum plasma flow into a uniform 4.5-Tesla magnetic field created using a solenoid designed and manufactured at the University of Michigan. Opposing-target experiments demonstrate interesting collisional behavior between the two magnetized flows. Preliminary interferometry and Faraday rotation measurements will be presented and discussed. This work is funded by the U.S Department of Energy, through the NNSA-DS and SC-OFES Joint Program in High-Energy-Density Laboratory Plasmas, grant number DE-NA0001840. Support for this work was provided by NASA through Einstein Postdoctoral Fellowship grant number PF3-140111 awarded by the Chandra X-ray Center, which is operated by the Astrophysical Observatory for NASA under contract NAS8-03060.

  19. Preliminary Hazards Analysis of K-Basin Fuel Encapsulation and Storage

    International Nuclear Information System (INIS)

    Strickland, G.C.

    1994-01-01

    This Preliminary Hazards Analysis (PHA) systematically examines the K-Basin facilities and their supporting systems for hazards created by abnormal operating conditions and external events (e.g., earthquakes) which have the potential for causing undesirable consequences to the facility worker, the onsite individual, or the public. The operational activities examined are fuel encapsulation, fuel storage and cooling. Encapsulation of sludges in the basins is not examined. A team of individuals from Westinghouse produced a set of Hazards and Operability (HAZOP) tables documenting their examination of abnormal process conditions in the systems and activities examined in K-Basins. The purpose of this report is to reevaluate and update the HAZOP in the original Preliminary Hazard Analysis of K-Basin Fuel Encapsulation and Storage originally developed in 1991

  20. Modern methods of material accounting for mixed oxide fuel fabrication facility

    International Nuclear Information System (INIS)

    Eggers, R.F.; Pindak, J.L.; Brouns, R.J.; Williams, R.C.; Brite, D.W.; Kinnison, R.R.; Fager, J.E.

    1981-01-01

    The generic requirements loss detection, and response to alarms of a contemporary material control and accounting (MCandA) philosophy have been applied to a mixed oxide fuel fabrication plant to produce a detailed preliminary MCandA system design that is generally applicable to facilities of this type. This paper summarizes and discusses detailed results of the mixed oxide fuel fabrication plant study

  1. Development of an integrated assay facility

    International Nuclear Information System (INIS)

    Molesworth, T.V.; Bailey, M.; Findlay, D.J.S.; Parsons, T.V.; Sene, M.R.; Swinhoe, M.T.

    1990-01-01

    The I.R.I.S. concept proposed the use of passive examination and active interrogation techniques in an integrated assay facility. A linac would generate the interrogating gamma and neutron beams. Insufficiently detailed knowledge about active neutron and gamma interrogation of 500 litre drums of cement immobilised intermediate level waste led to a research programme which is now in its main experimental stage. Measurements of interrogation responses are being made using simulated waste drums containing actinide samples and calibration sources, in an experimental assay assembly. Results show that responses are generally consistent with theory, but that improvements are needed in some areas. A preliminary appraisal of the engineering and economic aspects of integrated assay shows that correct operational sequencing is required to achieve the short cycle time needed for high throughput. The main engineering features of a facility have been identified

  2. Testing optimization sequence for the beam port facility of PSBR

    International Nuclear Information System (INIS)

    Bekar, K.B.; Azmy, Y.Y.; Unlu, K.

    2005-01-01

    We present preliminary testing results of the modular code package prepared for the size and shape optimization of the beam tube device of the beam port facility at the Penn State Breazeale Reactor (PSBR). In the test cases, using the Min-max algorithm as an optimizer and multidimensional, neutral particle transport code TORT as a transport solver in the physics calculation, we optimize the shape of the D 2 O moderator of the beam tube device. We illustrate the modular nature of the optimization package, validation tests of the physics model, and preliminary optimization calculation via the whole code package. Results obtained so far indicate the drum-shaped D 2 O moderator tank is over-designed in size and does not possess the almost hemi-spherical optimal shape computed by our new package. (authors)

  3. Lunar landing and launch facilities and operations

    Science.gov (United States)

    1988-01-01

    A preliminary design of a lunar landing and launch facility for a Phase 3 lunar base is formulated. A single multipurpose vehicle for the lunar module is assumed. Three traffic levels are envisioned: 6, 12, and 24 landings/launches per year. The facility is broken down into nine major design items. A conceptual description of each of these items is included. Preliminary sizes, capacities, and/or other relevant design data for some of these items are obtained. A quonset hut tent-like structure constructed of aluminum rods and aluminized mylar panels is proposed. This structure is used to provide a constant thermal environment for the lunar modules. A structural design and thermal analysis is presented. Two independent designs for a bridge crane to unload/load heavy cargo from the lunar module are included. Preliminary investigations into cryogenic propellant storage and handling, landing/launch guidance and control, and lunar module maintenance requirements are performed. Also, an initial study into advanced concepts for application to Phase 4 or 5 lunar bases has been completed in a report on capturing, condensing, and recycling the exhaust plume from a lunar launch.

  4. Vivo dosimetry using TLD detectors in prostate seed implants of I-125: preliminary results

    International Nuclear Information System (INIS)

    Sanchez-Reyes, A.; Pedro, A.; Bassas, P.; Duch, M. A.; Cros, M.; Mane, S.

    2011-01-01

    We present preliminary results of a new in vivo dosimetry technique that could allow to know immediately after implantation of the prostate if the dose distribution determined by the scheduler is similar to the actual dose measured with TLD detectors.

  5. 77 FR 66580 - Certain Preserved Mushrooms From India: Preliminary Results of Antidumping Duty Administrative...

    Science.gov (United States)

    2012-11-06

    ... DEPARTMENT OF COMMERCE International Trade Administration [A-533-813] Certain Preserved Mushrooms... preserved mushrooms (mushrooms) from India. The period of review (POR) is February 1, 2011, through January... Preliminary Results of Antidumping Duty Administrative Review: Certain Preserved Mushrooms from India...

  6. Chemical Analysis of the Moon at the Surveyor VII Landing Site: Preliminary Results.

    Science.gov (United States)

    Turkevich, A L; Franzgrote, E J; Patterson, J H

    1968-10-04

    The alpha-scattering experiment aboard Surveyor VII has provided a chemical analysis of the moon in the area of the crater Tycho. The preliminary results indicate a chemical composition similar to that already found at two mare sites, but with a lower concentration of elements of the iron group (titanium through copper).

  7. 78 FR 36744 - Diamond Sawblades and Parts Thereof From the People's Republic of China: Preliminary Results of...

    Science.gov (United States)

    2013-06-19

    ... management, production facilities, supplier relationships, and customer base.\\5\\ While no single factor or... significant changes to management, production facilities, supplier relationships, and customers. As a result..., production facilities, and customer/ supplier relationships have not changed as a result of the name change...

  8. US Army facility for the consolidation of low-level radioactive waste

    International Nuclear Information System (INIS)

    Stein, S.L.; Tanner, J.E.; Murphy, B.L.; Gillings, J.C.; Hadley, R.T.; Lyso, O.M.; Gilchrist, R.L.; Murphy, D.W.

    1983-12-01

    A preliminary study of a waste consolidation facility for the Department of the Army's low-level radioactive waste was carried out to determine a possible site and perform a cost-benefit analysis. Four sites were assessed as possible locations for such a facility, using predetermined site selection criteria. To assist in the selection of a site, an evaluation of environmental issues was included as part of each site review. In addition, a preliminary design for a waste consolidation facility was developed, and facilities at each site were reviewed for their availability and suitability for this purpose. Currently available processes for volume reduction, as well as processes still under development, were then investigated, and the support and handling equipment and the staff needed for the safe operation of a waste consolidation facility were studied. Using current costs for the transportation and burial of low-level waste, a cost comparison was then made between waste disposal with and without the utilization of volume reduction. Finally, regulations that could affect the operation of a waste consolidation facility were identified and their impact was assessed. 11 references, 5 figures, 16 tables

  9. Aerosol composition in a stagnant air mass impacted by dense fogs: preliminary results

    Energy Technology Data Exchange (ETDEWEB)

    Jacob, D.J.; Munger, J.W.; Waldman, J.M.; Hoffman, M.R.

    1984-01-01

    Over the last two winters, our research group has been investigating the chemical composition of fogwater and haze aerosol during wintertime stagnation episodes in the San Joaquin Valley of California. The valley is encompassed by mountain ranges. During the winter a strong subsidence inversion based below the natural boundaries of the valley restricts the ventilation of the air masses below the inversion. The residence time of an air parcel in the valley under these stagnation conditions is on the order of 8 days. Because the trapped air is very humid, stagnation episodes are associated with a persistent thick haze and frequent widespread nighttime fogs. During the winter 1982-1983 the authors sampled fog and haze at one site (Bakersfield); results from this preliminary study have been discussed in detail in a previous report. In the winter 1983-1984 the scale of the program was expanded in order to test hypotheses formulated as a result of first year data. The present paper first reports briefly on the 1982-1983 results and outlines the essential conclusions. They then describe the large-scale experiment conducted during the winter of 1983-1984, and discuss some preliminary fogwater data.

  10. In-cell facility for performing mechanical-property tests on irradiated cladding

    International Nuclear Information System (INIS)

    Yaggee, F.L.; Haglund, R.C.; Mattas, R.F.

    1978-11-01

    A new facility was developed for testing cladding sections of LWR fuel rods. This facility and the accompanying test procedures have improved the level of in-cell mechanical-testing capabilities, making them comparable to existing capabilities for unirradiated cladding. The new facility is currently being used to study the susceptibility of irradiated Zircaloy cladding from LWR fuel rods to iodine stress-corrosion cracking. Preliminary testing results indicate a systematic effect of temperature, stress and irradiation on the susceptibility of annealed and stress-relieved Zircaloy-2. Experimental data obtained to date are being used to develop a stress-corrosion cracking model for LWR fuel rod failure. SEM examination of the undisturbed fracture surface of specimens that failed by pinhole leakage provides useful information on crack propagation and morphology

  11. Vapour explosions (fuel-coolant interactions) resulting from the sub-surface injection of water into molten metals: preliminary results

    International Nuclear Information System (INIS)

    Asher, R.C.; Bullen, D.; Davies, D.

    1976-03-01

    Preliminary experiments are reported on the relationship between the injection mode of contact and the occurrence and magnitude of vapour explosions. Water was injected beneath the surface of molten metals, chiefly tin at 250 to 900 0 C. Vapour explosions occurred in many, but not all, cases. The results are compared with Dullforce's observations (Culham Report (CLM-P424) on the dropping mode of contact and it appears that rather different behaviour is found; in particular, the present results suggest that the Temperature Interaction Zone is different for the two modes of contact. (author)

  12. RCRA Facilities Assessment (RFA)---Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    1987-03-01

    US Department of Energy (DOE) facilities are required to be in full compliance with all federal and state regulations. In response to this requirement, the Oak Ridge National Laboratory (ORNL) has established a Remedial Action Program (RAP) to provide comprehensive management of areas where past and current research, development, and waste management activities have resulted in residual contamination of facilities or the environment. This report presents the RCRA Facility Assessment (RFA) required to meet the requirements of RCRA Section 3004(u). Included in the RFA are (1) a listing of all sites identified at ORNL that could be considered sources of releases or potential releases; (2) background information on each of these sites, including location, type, size, period of operation, current operational status, and information on observed or potential releases (as required in Section II.A.1 of the RCRA permit); (3) analytical results obtained from preliminary surveys conducted to verify the presence or absence of releases from some of the sites; and (4) ORNL's assessment of the need for further remedial attention

  13. RCRA Facilities Assessment (RFA)---Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    1987-03-01

    US Department of Energy (DOE) facilities are required to be in full compliance with all federal and state regulations. In response to this requirement, the Oak Ridge National Laboratory (ORNL) has established a Remedial Action Program (RAP) to provide comprehensive management of areas where past and current research, development, and waste management activities have resulted in residual contamination of facilities or the environment. This report presents the RCRA Facility Assessment (RFA) required to meet the requirements of RCRA Section 3004(u). Included in the RFA are (1) a listing of all sites identified at ORNL that could be considered sources of releases or potential releases; (2) background information on each of these sites, including location, type, size, period of operation, current operational status, and information on observed or potential releases (as required in Section II.A.1 of the RCRA permit); (3) analytical results obtained from preliminary surveys conducted to verify the presence or absence of releases from some of the sites; and (4) ORNL`s assessment of the need for further remedial attention.

  14. RCRA Facilities Assessment (RFA)---Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    1987-03-01

    US Department of Energy (DOE) facilities are required to be in full compliance with all federal and state regulations. In response to this requirement, the Oak Ridge National Laboratory (ORNL) has established a Remedial Action Program (RAP) to provide comprehensive management of areas where past and current research, development, and waste management activities have resulted in residual contamination of facilities or the environment. This report presents the RCRA Facility Assessment (RFA) required to meet the requirements of RCRA Section 3004(u). Included in the RFA are (1) a listing of all sites identified at ORNL that could be considered sources of releases or potential releases; (2) background information on each of these sites, including location, type, size, period of operation, current operational status, and information on observed or potential releases (as required in Section II.A.1 of the RCRA permit); (3) analytical results obtained from preliminary surveys conducted to verify the presence or absence of releases from some of the sites; and (4) ORNL's assessment of the need for further remedial attention.

  15. High temperature combustion facility: present capabilities and future prospects

    International Nuclear Information System (INIS)

    Boccio, J.L.; Ginsberg, T.; Ciccarelli, G.

    1995-01-01

    The high-temperature combustion facility constructed and operated by the Department of Advanced Technology of Brookhaven National Laboratory to support and promote research in the area of hydrogen combustion phenomena in mixtures prototypical to light-water reactor containment atmospheres under potential severe accident conditions is reported. The facility can accommodate combustion research activities encompassing the fields of detonation physics, flame acceleration, and low-speed deflagration in a wide range of combustible gas mixtures at initial temperatures up to 700 K and post-combustion pressures up to 100 atmospheres. Some preliminary test results are presented that provide further evidence that the effect of temperature is to increase the sensitivity of hydrogen-air-steam mixtures to undergo detonation [ru

  16. A Qualitative Study of Factors Influencing Racial Diversity in Environmental Education: Preliminary Results

    Science.gov (United States)

    Kathy James; Leo H. McAvoy

    1992-01-01

    This study presents preliminary result interviews with people of color working in environmental education and interpretation throughout the United States. The three primary questions asked were these? (1) What path led each individual to a career in environmental education; (2) How does each individual define environmentalism? and (3) What are the primary issues this...

  17. Radiation Testing on State-of-the-Art CMOS: Challenges, Plans, and Preliminary Results

    Science.gov (United States)

    LaBel, Kenneth A.; Cohn, Lewis M.

    2009-01-01

    At GOMAC 2007 and 2008, we discussed a variety of challenges for radiation testing of modern semiconductor devices and technologies [1, 2]. In this presentation, we provide more specific details in this on-going investigation focusing on out-of-the-box lessons observed for providing radiation effects assurances as well as preliminary test results.

  18. OSU TOMF Program Site Selection and Preliminary Concept Design Report

    Energy Technology Data Exchange (ETDEWEB)

    Spadling, Steve [Oklahoma State Univ., Stillwater, OK (United States)

    2012-05-10

    The purpose of this report is to confirm the programmatic requirements for the new facilities, identify the most appropriate project site, and develop preliminary site and building concepts that successfully address the overall project goals and site issues. These new facilities will be designed to accommodate the staff, drivers and maintenance requirements for the future mixed fleet of passenger vehicles, Transit Style Buses and School Buses.

  19. Managing LLRW from decommissioning of nuclear facilities - a Canadian perspective

    Energy Technology Data Exchange (ETDEWEB)

    Donders, R E [Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs.; Hardy, D G [Frontenac Consulting Services, Deep River, ON (Canada); De, P L [Low-Level Radioactive Waste Management Office, Gloucester, ON (Canada)

    1994-03-01

    In Canada, considerable experience has been gained recently in decommissioning nuclear facilities and managing the resulting waste. This experience has raised important issues from both the decommissioning and waste management perspectives. This paper focuses on the waste management aspects of decommissioning. Past experience is reviewed, preliminary estimates of waste volumes and characteristics are provided, and the major technical and regulatory issues are discussed. (author). 5 refs., 1 tab., 2 figs.

  20. Preliminary siting characterization Salt Disposition Facility - Site B

    International Nuclear Information System (INIS)

    Wyatt, D.

    2000-01-01

    A siting and reconnaissance geotechnical program has been completed in S-Area at the Savannah River Site in South Carolina. This program investigated the subsurface conditions for the area known as ''Salt Disposition Facility (SDF), Site B'' located northeast of H-Area and within the S-Area. Data acquired from the Site B investigation includes both field exploration and laboratory test data

  1. The Inter Facility Testing of a Standard Oscillating Water Column (OWC) Type Wave Energy Converter (WEC)

    DEFF Research Database (Denmark)

    Andersen, Morten Thøtt; Thomsen, Jonas Bjerg

    This report describes the behavior and preliminary performance of a simplified standard oscillating water column (OWC) wave energy converter (WEC). The same tests will be conducted at different scales at 6 different test facilities and the results obtained will be used for comparison. This project...

  2. Chemical Analysis of the Moon at the Surveyor VI Landing Site: Preliminary Results.

    Science.gov (United States)

    Turkevich, A L; Patterson, J H; Franzgrote, E J

    1968-06-07

    The alpha-scattering experiment aboard soft-landing Surveyor VI has provided a chemical analysis of the surface of the moon in Sinus Medii. The preliminary results indicate that, within experimental errors, the composition is the same as that found by Surveyor V in Mare Tranquillitatis. This finding suggests that large portions of the lunar maria resemble basalt in composition.

  3. Small-angle neutron scattering investigations of Co-doped iron oxide nanoparticles. Preliminary results

    Science.gov (United States)

    Creanga, Dorina; Balasoiu, Maria; Soloviov, Dmitro; Balasoiu-Gaina, Alexandra-Maria; Puscasu, Emil; Lupu, Nicoleta; Stan, Cristina

    2018-03-01

    Preliminary small-angle neutron scattering investigations on aqueous suspensions of several cobalt doped ferrites (CoxFe3-xO4, x=0; 0.5; 1) nanoparticles prepared by chemical co-precipitation method, are reported. The measurements were accomplished at the YuMO instrument in function at the IBR-2 reactor. Results of intermediary data treatment are presented and discussed.

  4. Preliminary results of a battery-based, multi megawatt 200 kA pulsed power supply.

    NARCIS (Netherlands)

    Karthaus, W.; Kolkert, W.J.; Nowee, J.

    1989-01-01

    A pulsed power supply consisting of a fast discharge battery, a switch based on silicon-controlled-rectifier SCR technology, and an energy storage/pulse transformer is discussed. Preliminary results indicate that the battery is capable of discharging current pulses with reproducible peak values of

  5. 78 FR 28192 - Polyethylene Retail Carrier Bags From Thailand: Preliminary Results of Antidumping Duty...

    Science.gov (United States)

    2013-05-14

    ... Bags From Thailand: Preliminary Results of Antidumping Duty Administrative Review; 2011-2012 AGENCY... on polyethylene retail carrier bags (PRCBs) from Thailand. The review covers 11 respondents. The... merchandise has been sold at less than normal value by the companies subject to this review. DATES: Effective...

  6. Comparison the Results of Numerical Simulation And Experimental Results for Amirkabir Plasma Focus Facility

    Science.gov (United States)

    Goudarzi, Shervin; Amrollahi, R.; Niknam Sharak, M.

    2014-06-01

    In this paper the results of the numerical simulation for Amirkabir Mather-type Plasma Focus Facility (16 kV, 36μF and 115 nH) in several experiments with Argon as working gas at different working conditions (different discharge voltages and gas pressures) have been presented and compared with the experimental results. Two different models have been used for simulation: five-phase model of Lee and lumped parameter model of Gonzalez. It is seen that the results (optimum pressures and current signals) of the Lee model at different working conditions show better agreement than lumped parameter model with experimental values.

  7. Comparison the results of numerical simulation and experimental results for Amirkabir plasma focus facility

    International Nuclear Information System (INIS)

    Goudarzi, Shervin; Amrollahi, R; Sharak, M Niknam

    2014-01-01

    In this paper the results of the numerical simulation for Amirkabir Mather-type Plasma Focus Facility (16 kV, 36μF and 115 nH) in several experiments with Argon as working gas at different working conditions (different discharge voltages and gas pressures) have been presented and compared with the experimental results. Two different models have been used for simulation: five-phase model of Lee and lumped parameter model of Gonzalez. It is seen that the results (optimum pressures and current signals) of the Lee model at different working conditions show better agreement than lumped parameter model with experimental values.

  8. Preliminary results on tests of a Cerenkov ring imaging device employing a photoionizing PWC

    Energy Technology Data Exchange (ETDEWEB)

    Durkin, S.; Honma, A.; Leith, D.W.G.S.

    1978-08-01

    A brief description of techniques and problems of ring imaging Cerenkov detectors employing photoionizing PWC's is discussed. Preliminary results on a one dimensional ring imaging device tested at SLAC in May and June of 1978 are then presented. These results include rough measurements of the Cerenkov ring in nitrogen, argon, neon, and helium produced by a collimated positron beam.

  9. Preliminary Concept of Operations for a Global Cylinder Identification and Monitoring System

    Energy Technology Data Exchange (ETDEWEB)

    Whitaker, J. M. [ORNL; White-Horton, J. L. [ORNL; Morgan, J. B. [InSolves Associates

    2013-08-01

    This report describes a preliminary concept of operations for a Global Cylinder Identification and Monitoring System that could improve the efficiency of the International Atomic Energy Agency (IAEA) in conducting its current inspection activities and could provide a capability to substantially increase its ability to detect credible diversion scenarios and undeclared production pathways involving UF6 cylinders. There exist concerns that a proliferant State with access to enrichment technology could obtain a cylinder containing natural or low-enriched uranium hexafluoride (UF6) and produce a significant quantity (SQ)1 of highly enriched uranium in as little as 30 days. The National Nuclear Security Administration (NNSA) through the Next Generation Safeguards Initiative sponsored a multi-laboratory team to develop an integrated system that provides for detecting scenarios involving 1) diverting an entire declared cylinder for enrichment at a clandestine facility, 2) misusing a declared cylinder at a safeguarded facility, and 3) using an undeclared cylinder at a safeguarded facility. An important objective in developing this integrated system was to improve the timeliness for detecting the cylinder diversion and undeclared production scenarios. Developing this preliminary concept required in-depth analyses of current operational and safeguards practices at conversion, enrichment, and fuel fabrication facilities. The analyses evaluated the processing, movement, and storage of cylinders at the facilities; the movement of cylinders between facilities (including cylinder fabrication); and the misuse of safeguarded facilities.

  10. FMIT - the fusion materials irradiation test facility

    International Nuclear Information System (INIS)

    Liska, D.J.

    1980-01-01

    A joint effort by the Hanford Engineering Development Laboratory (HEDL) and Los Alamos Scientific Laboratory (LASL) has produced a preliminary design for a Fusion Materials Irradiation Test Facility (FMIT) that uses a high-power linear accelerator to fire a deuteron beam into a high-speed jet of molten lithium. The result is a continuous energy spectrum of neutrons with a 14-MeV average energy which can irradiate material samples to projected end-of-life levels in about 3 years, with a total accumulated fluence of 10 21 to 10 22 n/cm 2

  11. Assessment of the proposed decontamination and waste treatment facility at LLNL

    International Nuclear Information System (INIS)

    Cohen, J.J.

    1987-01-01

    To provide a centralized decontamination and waste treatment facility (DWTF) at LLNL, the construction of a new installation has been planned. Objectives for this new facility were to replace obsolete, structurally and environmentally sub-marginal liquid and solid waste process facilities and decontamination facility and to bring these facilities into compliance with existing federal, state and local regulations as well as DOE orders. In a previous study, SAIC conducted a preliminary review and evaluation of existing facilities at LLNL and cost effectiveness of the proposed DWTF. This document reports on a detailed review of specific aspects of the proposed DWTF

  12. Preliminary evaluation of 30 potential granitic rock sites for a radioactive waste storage facility in southern Nevada

    International Nuclear Information System (INIS)

    Boardman, C.R.; Knutson, C.F.

    1978-01-01

    Results of preliminary study are presented which was performed under subtask 2.7 of the NTS Terminal Waste Storage Program Plan for 1978. Subtask 2.7 examines the feasibility of locating a nuclear waste repository in a granitic stock or pluton in southern Nevada near the Nevada Test Site (NTS). It is assumed for the purposes of this study that such a repository cannot be located at NTS. This assumption may or may not be correct. This preliminary report does not identify a particular site as being a suitable location for a repository. Nor does it absolutely eliminate a particular site from further consideration. It does, however, answer the basic question of probable suitability of some of the sites and present a systematic method for site evaluation. Since the findings of this initial study have been favorable, it will be followed by more exhaustive and detailed studies of the original 30 sites and perhaps others. In future studies some of the evaluation criteria used in the preliminary study may be modified or eliminated, and new criteria may be introduced

  13. Preliminary evaluation of 30 potential granitic rock sites for a radioactive waste storage facility in southern Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Boardman, C.R.; Knutson, C.F.

    1978-02-15

    Results of preliminary study are presented which was performed under subtask 2.7 of the NTS Terminal Waste Storage Program Plan for 1978. Subtask 2.7 examines the feasibility of locating a nuclear waste repository in a granitic stock or pluton in southern Nevada near the Nevada Test Site (NTS). It is assumed for the purposes of this study that such a repository cannot be located at NTS. This assumption may or may not be correct. This preliminary report does not identify a particular site as being a suitable location for a repository. Nor does it absolutely eliminate a particular site from further consideration. It does, however, answer the basic question of probable suitability of some of the sites and present a systematic method for site evaluation. Since the findings of this initial study have been favorable, it will be followed by more exhaustive and detailed studies of the original 30 sites and perhaps others. In future studies some of the evaluation criteria used in the preliminary study may be modified or eliminated, and new criteria may be introduced.

  14. Engineering test facility

    International Nuclear Information System (INIS)

    Steiner, D.; Becraft, W.R.; Sager, P.H.

    1981-01-01

    The vehicle by which the fusion program would move into the engineering testing phase of fusion power development is designated the Engineering Test Facility (ETF). The ETF would provide a test-bed for reactor components in the fusion environment. In order to initiate preliminary planning for the ETF decision, the Office of Fusion Energy established the ETF Design Center activity to prepare the design of the ETF. This paper described the design status of the ETF

  15. Safety overview of the National Ignition Facility

    International Nuclear Information System (INIS)

    Brereton, S.J.; McLouth, L.; Odell, B.; Singh, M.; Tobin, M.; Trent, M.

    1996-01-01

    The National Ignition Facility (NIF) is a proposed US Department of Energy inertial confinement laser fusion facility. The candidate sites for locating the NIF are: Los Alamos National Laboratory, Sandia National Laboratory, the Nevada Test Site, and Lawrence Livermore National Laboratory (LLNL), the preferred site. The NIF will operate by focusing 192 laser beams onto a tiny deuterium- tritium target located at the center of a spherical target chamber. The NIF mission is to achieve inertial confinement fusion (ICF) ignition, access physical conditions in matter of interest to nuclear weapons physics, provide an above ground simulation capability for nuclear weapons effects testing, and contribute to the development of inertial fusion for electrical power production. The NIF has been classified as a radiological, low hazard facility on the basis of a preliminary hazards analysis and according to the DOE methodology for facility classification. This requires that a safety analysis be prepared under DOE Order 5481.1B, Safety Analysis and Review System. A draft Preliminary Safety Analysis Report (PSAR) has been written, and this will be finalized later in 1996. This paper summarizes the safety issues associated with the operation of the NIF. It provides an overview of the hazards, estimates maximum routine and accidental exposures for the preferred site of LLNL, and concludes that the risks from NIF operations are low

  16. Determining Plutonium Mass in Spent Fuel with Nondestructive Assay Techniques -- Preliminary Modeling Results Emphasizing Integration among Techniques

    International Nuclear Information System (INIS)

    Tobin, S.J.; Fensin, M.L.; Ludewigt, B.A.; Menlove, H.O.; Quiter, B.J.; Sandoval, N.P.; Swinhoe, M.T.; Thompson, S.J.

    2009-01-01

    There are a variety of motivations for quantifying Pu in spent (used) fuel assemblies by means of nondestructive assay (NDA) including the following: strengthen the capabilities of the International Atomic Energy Agencies to safeguards nuclear facilities, quantifying shipper/receiver difference, determining the input accountability value at reprocessing facilities and providing quantitative input to burnup credit determination for repositories. For the purpose of determining the Pu mass in spent fuel assemblies, twelve NDA techniques were identified that provide information about the composition of an assembly. A key point motivating the present research path is the realization that none of these techniques, in isolation, is capable of both (1) quantifying the elemental Pu mass of an assembly and (2) detecting the diversion of a significant number of pins. As such, the focus of this work is determining how to best integrate 2 or 3 techniques into a system that can quantify elemental Pu and to assess how well this system can detect material diversion. Furthermore, it is important economically to down-select among the various techniques before advancing to the experimental phase. In order to achieve this dual goal of integration and down-selection, a Monte Carlo library of PWR assemblies was created and is described in another paper at Global 2009 (Fensin et al.). The research presented here emphasizes integration among techniques. An overview of a five year research plan starting in 2009 is given. Preliminary modeling results for the Monte Carlo assembly library are presented for 3 NDA techniques: Delayed Neutrons, Differential Die-Away, and Nuclear Resonance Fluorescence. As part of the focus on integration, the concept of 'Pu isotopic correlation' is discussed and the role of cooling time determination.

  17. Presentation of preliminary studies relative to the long duration disposal of medium level and long lived (MLLL) wastes

    International Nuclear Information System (INIS)

    Leroy, C.; Moreau, A.; Fayette, L.; Bellon, M.; Templier, J.C.; Macias, R.M.; Porcher, J.B.; Rey, F.; Hollender, F.; Girard, J.P.

    2002-01-01

    In the contract of objectives signed in 2001 with the government, the French atomic energy commission (CEA) committed itself to supply reports of preliminary studies about long duration disposal concepts for medium level and long lived radioactive wastes. This document makes the synthesis of the preliminary studies carried out in 2001 and 2002 by exploring simultaneously the surface and subsurface disposal concepts. The studies deal with the design of a facility with a long service life. Four hypotheses have been retained for the preliminary studies: a secular lifetime (typically 100 to 300 years), a single and new site for all waste packages (no existing facility available), two confinement barriers, an envelope-type site with specific characteristics (seismicity, climate conditions, airplane crash..). These preliminary studies show the existence of solutions for each option: with and without storage containers in both type (surface and subsurface) of facilities. They outline the necessity of studying more thoroughly some technical points. This instruction will be performed for the concepts retained after a multi-criteria analysis. (J.S.)

  18. A study on the establishment of severe accident experimental facility

    International Nuclear Information System (INIS)

    Yoo, Kun Joong; Kim, Sang Baek; Kim, In Sik; Nho, Ki Man; Bark, Rae Joon; Park, Chun Kyeong; Sim, Seok Koo; Lee, Seong Jae; Chung, Moon Ki; Cho, Yeong Ro; Chun, Shee Yeong

    1994-07-01

    Significant progress has been achieved during this year of the project. Planned DCH experiments on the sensitivity of the cavity geometry factors and the cavity capture volume effects were performed using the HPME facility for Kori-1/2 and YGN-3/4 cavity scale models. The Crust Formation Test Facility has been completed. Preliminary calculations were performed to predict test results. The experiments of the crust formation on the simulant and its heat transfer characteristic were performed to investigate the effects of coolant injection methods, bottom heating boundary surface temperatures, coolant temperatures and coolant flow rates. The design of the FCI Test Facility has been completed and the procurement of the materials is in progress. Also, the steam condensation experiment on the vertical containment walls and the research on the development of measuring techniques of the particle sizes and velocities are in progress as planned. Through international research collaboration with USNRC and CEA Cadarache, information of the experimental research on the severe fuel damage has been gathered and analyzed. Preliminary planning of the second phase tests has been launched this year. This study proposes the scope of the second phase and the strategy to implement the proposed second phase experimental program. This study also proposes a strategy to establish building blocks and infrastructure for the severe accident research in Korea. (Author)

  19. Human factors engineering report for the cold vacuum drying facility

    Energy Technology Data Exchange (ETDEWEB)

    IMKER, F.W.

    1999-06-30

    The purpose of this report is to present the results and findings of the final Human Factors Engineering (HFE) technical analysis and evaluation of the Cold Vacuum Drying Facility (CVDF). Ergonomics issues are also addressed in this report, as appropriate. This report follows up and completes the preliminary work accomplished and reported by the Preliminary HFE Analysis report (SNF-2825, Spent Nuclear Fuel Project Cold Vacuum Drying Facility Human Factors Engineering Analysis: Results and Findings). This analysis avoids redundancy of effort except for ensuring that previously recommended HFE design changes have not affected other parts of the system. Changes in one part of the system may affect other parts of the system where those changes were not applied. The final HFE analysis and evaluation of the CVDF human-machine interactions (HMI) was expanded to include: the physical work environment, human-computer interface (HCI) including workstation and software, operator tasks, tools, maintainability, communications, staffing, training, and the overall ability of humans to accomplish their responsibilities, as appropriate. Key focal areas for this report are the process bay operations, process water conditioning (PWC) skid, tank room, and Central Control Room operations. These key areas contain the system safety-class components and are the foundation for the human factors design basis of the CVDF.

  20. Human factors engineering report for the cold vacuum drying facility

    International Nuclear Information System (INIS)

    IMKER, F.W.

    1999-01-01

    The purpose of this report is to present the results and findings of the final Human Factors Engineering (HFE) technical analysis and evaluation of the Cold Vacuum Drying Facility (CVDF). Ergonomics issues are also addressed in this report, as appropriate. This report follows up and completes the preliminary work accomplished and reported by the Preliminary HFE Analysis report (SNF-2825, Spent Nuclear Fuel Project Cold Vacuum Drying Facility Human Factors Engineering Analysis: Results and Findings). This analysis avoids redundancy of effort except for ensuring that previously recommended HFE design changes have not affected other parts of the system. Changes in one part of the system may affect other parts of the system where those changes were not applied. The final HFE analysis and evaluation of the CVDF human-machine interactions (HMI) was expanded to include: the physical work environment, human-computer interface (HCI) including workstation and software, operator tasks, tools, maintainability, communications, staffing, training, and the overall ability of humans to accomplish their responsibilities, as appropriate. Key focal areas for this report are the process bay operations, process water conditioning (PWC) skid, tank room, and Central Control Room operations. These key areas contain the system safety-class components and are the foundation for the human factors design basis of the CVDF

  1. IFMIF (International Fusion Materials Irradiation Facility) conceptual design activity reduced cost report

    International Nuclear Information System (INIS)

    2000-02-01

    This report describes the results of a preliminary reevaluation of the design and cost of the International Fusion Materials Irradiation Facility (IFMIF) Project in response to the request from the 28th FPCC meeting in January 1999. Two major ideas have been considered: 1) reduction of the total construction cost through elimination of the previously planned facility upgrade and 2) a facility deployment in 3 stages with capabilities for limited experiments in the first stage. As a result, the size and complexity of the facility could be significantly reduced, leading to substantial cost savings. In addition to these two ideas, this study also included a critical review of the original CDA specification with the objective of elimination of nonessential items. For example, the number of lithium targets was reduced from two to one. As a result of these changes in addition to the elimination of the upgrade, the total cost estimate was very substantially reduced from 797.2 MICF to 487.8 MICF, where 1 MICF = 1 Million of the IFMIF Conversion Units (approximately $1M US January, 1996). (author)

  2. Development of post-irradiation test facility for domestic production of 99Mo

    International Nuclear Information System (INIS)

    Taguchi, Taketoshi; Yonekawa, Minoru; Kato, Yoshiaki; Kurosawa, Makoto; Nishikata, Kaori; Ishida, Takuya; Kawamata, Kazuo

    2013-01-01

    JMTR focus on the activation method. By carrying out the preliminary tests using irradiation facilities existing, and verification tests using the irradiation facility that has developed in the cutting-edge research and development strategic strengthening business, as irradiation tests towards the production of 99 Mo, we have been conducting research and development that can contribute to supply about 25% for 99 Mo demand in Japan and the stable supply of radiopharmaceutical. This report describes a summary of the status of the preliminary tests for the production of 99 Mo: Maintenance of test equipment in the facility in JMTR hot laboratory in preparation for research and development for the production of 99 Mo in JMTR and using MoO 3 pellet irradiated at Kyoto University Research Reactor Institute (KUR). (author)

  3. Hybrid Spectral Micro-CT: System Design, Implementation, and Preliminary Results

    CERN Document Server

    Bennett, James R; Xu, Qiong; Yu, Hengyong; Walsh, Michael; Butler, Anthony; Butler, Phillip; Cao, Guohua; Mohs, Aaron; Wang, Ge

    2014-01-01

    Spectral CT has proven an important development in biomedical imaging, and there have been several publications in the past years demonstrating its merits in pre-clinical and clinical applications. In 2012, Xu et al. reported that near-term implementation of spectral micro-CT could be enhanced by a hybrid architecture: a narrow-beam spectral "interior" imaging chain integrated with a traditional wide-beam "global" imaging chain. This hybrid integration coupled with compressive sensing (CS)-based interior tomography demonstrated promising results for improved contrast resolution, and decreased system cost and radiation dose. The motivation for the current study is implementation and evaluation of the hybrid architecture with a first-of-its-kind hybrid spectral micro-CT system. Preliminary results confirm improvements in both contrast and spatial resolution. This technology is shown to merit further investigation and potential application in future spectral CT scanner design.

  4. Hazard analysis in uranium hexafluoride production facility

    International Nuclear Information System (INIS)

    Marin, Maristhela Passoni de Araujo

    1999-01-01

    The present work provides a method for preliminary hazard analysis of nuclear fuel cycle facilities. The proposed method identify both chemical and radiological hazards, as well as the consequences associated with accident scenarios. To illustrate the application of the method, a uranium hexafluoride production facility was selected. The main hazards are identified and the potential consequences are quantified. It was found that, although the facility handles radioactive material, the main hazards as associated with releases of toxic chemical substances such as hydrogen fluoride, anhydrous ammonia and nitric acid. It was shown that a contention bung can effectively reduce the consequences of atmospheric release of toxic materials. (author)

  5. Initial characterization of the ATR [Advanced Test Reactor] Large Gamma Facility

    International Nuclear Information System (INIS)

    Schnitzler, B.G.; Rogers, J.W.

    1986-05-01

    Radiation fields in the ATR Large Gamma Facility test volume are characterized. The preliminary characterization efforts described in this report include total dose rate measurements in the facility, development of a simple methodology for calculating radiation fields from the ATR fuel element power histories, and a comparison of the measured and calculated values

  6. Preliminary safety evaluation of a commercial-scale krypton-85 encapsulation facility

    International Nuclear Information System (INIS)

    Christensen, A.B.; Tanner, J.E.; Knecht, D.A.

    1980-01-01

    This paper demonstrates that a commercial-scale facility for encapsulating krypton-85 in zeolite-5A or glass at a 2000 MTHM per year nuclear fuel reprocessing plant can be designed to contain fragments and the 340 to 850 kCi krypton-85 inventory from an assumed catastrophic failure of the high pressure vessel. The vessel failure was assumed as a worst case and was not based on a detailed design evaluation or operating experience. The process design is based on existing commercial hot isostatic pressing technology operated at up to 40 times the scale required for krypton encapsulation. From the calculated process gas inventory in the pressure vessel and vessel design, the maximum explosive energy of 8.4 kg TNT and resulting vessel plug and fragment velocities were calculated. The facility Containment Cell housing the high pressure vessel was designed to contain the gases, fragments, and the shock wave energy calculated for a hypothetical vessel failure. The Access Cell located directly above the Containment Cell was designed to be a tertiary confinement of krypton-85, should the access hatch be breached. 3 figures, 2 tables

  7. Approach to the fracture hydrology at Stripa: preliminary results

    International Nuclear Information System (INIS)

    Gale, J.E.; Witherspoon, P.A.

    1979-05-01

    There are two main problems associated with the concept of geologic storage of radioactive waste in fractured crystalline rock: (1) the thermo-mechanical effects of the heat generated by the waste, and (2) the potential for transport of radioactive materials by the groundwater system. In both problems, fractures play a dominant role. An assessment of the hydraulic and mechanical characteristics of fractued rock requires a careful series of laboratory and field investigations. The complexity of the problem is illustrated by the field studies in a fractured granite that are currently underway in an abandoned iron-ore mine at Stripa, Sweden. Much information is being gathered from an extensive series of boreholes and fracture maps. The approach being taken to integrate these data into an analysis of the fracture hydrology is reviewed and preliminary results from the hydrology program are presented. 13 figures

  8. Salt Repository Project transportation system interface requirements: Transportation system/repository receiving facility interface requirements

    International Nuclear Information System (INIS)

    Smith, L.A.; Insalaco, J.W.; Trainer, T.A.

    1988-01-01

    This report is a preliminary review of the interface between the transportation system and the repository receiving facility for a nuclear waste mined geologic disposal system in salt. Criteria for generic cask and facility designs are developed. These criteria are derived by examining the interfaces that occur as a result of the operations needed to receive nuclear waste at a repository. These criteria provide the basis for design of a safe, operable, practical nuclear waste receiving facility. The processing functions required to move the shipping unit from the gate into the unloading area and back to the gate for dispatch are described. Criteria for a generic receiving facility are discussed but no specific facility design is presented or evaluated. The criteria are stated in general terms to allow application to a wide variety of cask and facility designs. 9 refs., 6 figs., 4 tabs

  9. National Plutonium Workers' Study: considerations and preliminary results

    International Nuclear Information System (INIS)

    Acquavella, J.F.; Wilkinson, G.S.

    1983-03-01

    The National Plutonium Workers' Study developed from the clinical follow-up of workers with body burdens in excess of 10 nCi. The importance of plutonium to energy and weapons development and the uncertainty about its biological effects motivated the formation of an epidemiologic study of more than 125,000 workers at six Department of Energy facilities. This report reviews recent results from The National Plutonium Workers' Study, including an analysis of cancer mortality among workers at the Rocky Flats Plant and a study of malignant melanoma among employees at Los Alamos National Laboratory. The problems inherent in large-scale epidemiologic studies, as well as the future directions for the study, are discussed

  10. Preliminary Results Of PCA On MRO CRISM Multispectral Images

    Science.gov (United States)

    Klassen, David R.; Smith, M. D.

    2008-09-01

    Mars Reconnaissance Orbiter arrived at Mars in March 2006 and by September had achieved its science-phase orbit with the Compact Reconnaissance Imaging Spectrometer for Mars (CRISM) beginning its visible to near-infrared (VIS/NIR) spectral imaging shortly thereafter. One of the goals of CRISM is to fill in the spatial gaps between the various targeted observations, eventually mapping the entire surface. Due to the large volume of data this would create, the instrument works in a reduced spectral sampling mode creating "multispectral” images. From this data we can create image cubes using 70 wavelengths from 0.410 to 3.504 µm. We present here a preliminary analysis of these multispectral mode data products using the technique of Principal Components Analysis. Previous work with ground-based images has shown that over an entire visible hemisphere, there are only three to four meaningful components out of 32-105 wavelengths over 1.5-4.1 µm. The first two of these components are fairly consistent over all time intervals from day-to-day and season-to-season. [1-4] The preliminary work on the CRISM images cubes implies similar results_three to four significant principal components that are fairly consistent over time. We will show these components and a rough linear mixture modeling based on in-data spectral endmembers derived from the extrema of the principal components [5]. References: [1] Klassen, D. R. and Bell III, J. F. (2001) BAAS 33, 1069. [2] Klassen, D. R. and Bell III, J. F. (2003) BAAS, 35, 936. [3] Klassen, D. R., Wark, T. J., Cugliotta, C. G. (2005) BAAS, 37, 693. [4] Klassen, D. R. and Bell III, J. F. (2007) in preparation. [5] Klassen, D. R. and Bell III, J. F. (2000) BAAS, 32, 1105.

  11. Can facility management contribute to study success?

    NARCIS (Netherlands)

    Kok, H.B; Mobach, Mark P.; Omta, S.W.F.; Alexander, K.

    2013-01-01

    Purpose– The present paper aims to explore to what extent the quality of facility services can be related to the differences in educational achievements in higher education. Design/methodology/approach - This paper is based on the first preliminary analyses of a national online survey among 1,752

  12. Preliminary results of a feasibility study for a hard x-ray Kirkpatrick-Baez telescope

    DEFF Research Database (Denmark)

    Joensen, Karsten D.; Gorenstein, Paul; Wood, James L.

    1994-01-01

    the preliminary results of a feasibility study of a multifocus Kirkpatrick-Baez telescope. We conclude that high quality multilayers can be performed on relevant thin large flat substrate with adequate uniformity, and that existing deposition chambers can produce the multilayers at a rate of 0.42 m2 per day, so...

  13. Sludge treatment facility preliminary siting study for the sludge treatment project (A-13B)

    International Nuclear Information System (INIS)

    WESTRA, A.G.

    1999-01-01

    This study evaluates various sites in the 100 K area and 200 areas of Hanford for locating a treatment facility for sludge from the K Basins. Both existing facilities and a new standalone facility were evaluated. A standalone facility adjacent to the AW Tank Farm in the 200 East area of Hanford is recommended as the best location for a sludge treatment facility

  14. Report of questionnaire result concerning the radiation control in medicare facilities

    International Nuclear Information System (INIS)

    Nakamura, Yutaka

    2009-01-01

    Radiation control in Japanese medicare facilities is regulated generally by multiple laws of radiation and the Committee has investigated their actual radiation control practice through questionnaire, of which result and its analysis are described here. The questionnaire on web (Committee's homepage) was conducted in the period Apr., 13-May, 1, 2009, by asking to medical radiology personnel (MRP) with 20 items, mainly about personnel working for radiation medicare (RM), monitoring of their external dose, notice of exposure dose to individual person, archiving of the dose record, and questions about the Law Concerning Prevention from Radiation Hazard due to Radioisotopes, Etc.; was answered by 378 facilities where 15,281 persons in total worked for RM (41/facility in average); and the facilities were under regulation by 1 (Medical, 39%) and 2 (Medical and for Prevention, 61%) laws. Major findings were: 71% of facilities had no clear rule to select MRP; 98% trusted dosimetry outside; in 76%, personnel participating in RM had pocket dosimeter as well; 70% investigated the exposure history at personnel employment; to personnel whose dose could exceed or exceeded 20 mSv/y, 45% transferred the person to other work site, 34% issued warning and 21% had no such personnel; 73% felt the necessity of qualified expert for radiation control; 81% conducted education and training to MRP; 54% used radiation-generating equipments, 27%, unsealed radioisotopes and 19%, sealed ones; and 77% felt the radiation control should be unified in the Medical Law. Based on the findings, the Committee discussed and commented about definition and selection of MRP, dosimetry and its record of MRP having multiple, increasing works, uncertainty of the exact number of MRP in Japan, and desirable unification of radiation control practice in the medicare facility into the Medical Law if amended in future. (K.T.)

  15. Jovian seismology: preliminary results of the SYMPA instrument

    Science.gov (United States)

    Gaulme, P.; Schmider, F. X.; Gay, J.; Jacob, C.; Jeanneaux, F.; Alvarez, M.; Reyes, M.; Valtier, J. C.; Fossat, E.; Palle, P. L.; Belmonte, J. C.; Gelly, B.

    2006-06-01

    Jupiter's internal structure is poorly known (Guillot et al. 2004). Seismology is a powerful tool to investigate the internal structure of planets and stars, by analyzing how acoustic waves propagate. Mosser (1997) and Gudkova & Zarkhov (1999) showed that the detection and the identification of non-radial modes up to degree ℓ=25 can constrain strongly the internal structure. SYMPA is a ground-based network project dedicated to the Jovian oscillations (Schmider et al. 2002). The instrument is composed of a Mach-Zehnder interferometer producing four interferograms of the planetary spectrum. The combination of the four images in phase quadrature allows the reconstruction of the incident light phase, which is related to the Doppler shift generated by the oscillations. Two SYMPA instruments were built at the Nice university and were used simultaneously during two observation campaigns, in 2004 and 2005, at the San Pedro Martir observatory (Mexico) and the Teide observatory (Las Canarias). We will present for the first time the data processing and the preliminary results of the experiment.

  16. Mortality among workers at the Mound Facility: A preliminary report

    International Nuclear Information System (INIS)

    Reyes, M.; Wilkinson, G.S.; Tietjen, G.L.; Wiggs, L.D.; Galke, W.A.

    1991-04-01

    Mortality among 4,697 white males who were employed at the Mound Facility between 1943 and 1979 was compared with expected mortality based on US white male death rates. Standardized mortality ratios (SMRs) of 96 were observed for both all causes and all cancers. SMRs for digestive cancers and unintentional injuries were significantly less than 100. No SMR was significantly greater than 100 for these workers. A significantly elevated lung cancer SMR was observed for the subcohort of workers employed from 1943--1959, a period during which polonium-210 was processed at the plant. To determine the potential impact of wartime selection factors, this time period was further divided into two periods, 1943--1945 and 1946--1959. In the 1943--1945 period, the SMR for lung cancer was 204 (90% CI = 140, 290), while in the later period the lung cancer SMR was 105 (90% CI = 77, 140). Similar results were observed for all causes, all cancers, cancers of the rectum, nonmalignant respiratory diseases, and all injuries for which the SMRs were elevated during the wartime period but were not elevated after the war. Additional analyses considering workers hired in the period 1960--1979, during which plutonium-238 was processed at the facility, yielded little information. Generally, a strong healthy worker effect was observed and was attributed to the limited follow-up time and small numbers of deaths among this subcohort. 22 refs., 9 tabs

  17. Preliminary design of a biological treatment facility for trench water from a low-level radioactive waste disposal area at West Valley, New York

    Energy Technology Data Exchange (ETDEWEB)

    Rosten, R.; Malkumus, D. [Pacific Nuclear, Inc. (United States); Sonntag, T. [New York State Energy Research and Development Authority, NY (United States); Sundquist, J. [Ecology and Environment, Inc. (United States)

    1993-03-01

    The New York State Energy Research and Development Authority (NYSERDA) owns and manages a State-Licensed Low-Level Radioactive Waste Disposal Area (SDA) at West Valley, New York. Water has migrated into the burial trenches at the SDA and collected there, becoming contaminated with radionuclides and organic compounds. The US Environmental Protection Agency issued an order to NYSERDA to reduce the levels of water in the trenches. A treatability study of the contaminated trench water (leachate) was performed and determined the best available technology to treat the leachate and discharge the effluent. This paper describes the preliminary design of the treatment facility that incorporates the bases developed in the leachate treatability study.

  18. Nuclear Reactor Component Code CUPID-I: Numerical Scheme and Preliminary Assessment Results

    International Nuclear Information System (INIS)

    Cho, Hyoung Kyu; Jeong, Jae Jun; Park, Ik Kyu; Kim, Jong Tae; Yoon, Han Young

    2007-12-01

    A component scale thermal hydraulic analysis code, CUPID (Component Unstructured Program for Interfacial Dynamics), is being developed for the analysis of components of a nuclear reactor, such as reactor vessel, steam generator, containment, etc. It adopted three-dimensional, transient, two phase and three-field model. In order to develop the numerical schemes for the three-field model, various numerical schemes have been examined including the SMAC, semi-implicit ICE, SIMPLE, Row Scheme and so on. Among them, the ICE scheme for the three-field model was presented in the present report. The CUPID code is utilizing unstructured mesh for the simulation of complicated geometries of the nuclear reactor components. The conventional ICE scheme that was applied to RELAP5 and COBRA-TF, therefore, were modified for the application to the unstructured mesh. Preliminary calculations for the unstructured semi-implicit ICE scheme have been conducted for a verification of the numerical method from a qualitative point of view. The preliminary calculation results showed that the present numerical scheme is robust and efficient for the prediction of phase changes and flow transitions due to a boiling and a flashing. These calculation results also showed the strong coupling between the pressure and void fraction changes. Thus, it is believed that the semi-implicit ICE scheme can be utilized for transient two-phase flows in a component of a nuclear reactor

  19. Nuclear Reactor Component Code CUPID-I: Numerical Scheme and Preliminary Assessment Results

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Hyoung Kyu; Jeong, Jae Jun; Park, Ik Kyu; Kim, Jong Tae; Yoon, Han Young

    2007-12-15

    A component scale thermal hydraulic analysis code, CUPID (Component Unstructured Program for Interfacial Dynamics), is being developed for the analysis of components of a nuclear reactor, such as reactor vessel, steam generator, containment, etc. It adopted three-dimensional, transient, two phase and three-field model. In order to develop the numerical schemes for the three-field model, various numerical schemes have been examined including the SMAC, semi-implicit ICE, SIMPLE, Row Scheme and so on. Among them, the ICE scheme for the three-field model was presented in the present report. The CUPID code is utilizing unstructured mesh for the simulation of complicated geometries of the nuclear reactor components. The conventional ICE scheme that was applied to RELAP5 and COBRA-TF, therefore, were modified for the application to the unstructured mesh. Preliminary calculations for the unstructured semi-implicit ICE scheme have been conducted for a verification of the numerical method from a qualitative point of view. The preliminary calculation results showed that the present numerical scheme is robust and efficient for the prediction of phase changes and flow transitions due to a boiling and a flashing. These calculation results also showed the strong coupling between the pressure and void fraction changes. Thus, it is believed that the semi-implicit ICE scheme can be utilized for transient two-phase flows in a component of a nuclear reactor.

  20. SPANISH MULTICENTRIC STUDY ABOUT NUTRITION-INFLAMATIONhn WITH MID DILUTION (ENIMID STUDY: PRELIMINARY RESULTS

    Directory of Open Access Journals (Sweden)

    Barril G

    2012-06-01

    CONCLUSIONS: 1-The preliminary results show that MidDilution provides a good removal of small and middle molecules, increases appetite by providing a proper balance of cytokines through stimulation of antiinflamatory ones and neuropeptide Y. 2-It provides an improvement of body composition. Finally MidDilution improves nutritional parameters which leads to a better quality of life, as well as physical and mental status.

  1. Preliminary results from the Orbiting Solar Observatory 8 - Observations of optically thin lines

    Science.gov (United States)

    Shine, R. A.; Roussel-Dupre, D.; Bruner, E. C., Jr.; Chipman, E. G.; Lites, B. W.; Rottman, G. J.; Athay, R. G.; White, O. R.

    1976-01-01

    The University of Colorado spectrometer aboard OSO 8 has measured the high temperature C IV resonance lines (at 1548 and 1551 A) and the Si IV resonance lines (at 1393 and 1402 A) formed in the solar chromosphere-corona transition region. Preliminary results include studies of mean profiles, a comparison of cell and network profiles, and the behavior of the lines at the extreme solar limb.

  2. Preliminary studies of tunnel interface response modeling using test data from underground storage facilities.

    Energy Technology Data Exchange (ETDEWEB)

    Sobolik, Steven Ronald; Bartel, Lewis Clark

    2010-11-01

    correctly image the tunnel. This report represents a preliminary step in the development of a methodology to convert numerical predictions of rock properties to an estimation of the extent of rock damage around an underground facility and its corresponding seismic velocity, and the corresponding application to design a testing methodology for tunnel detection.

  3. 76 FR 26247 - Magnesium Metal From the Russian Federation: Preliminary Results of Antidumping Duty...

    Science.gov (United States)

    2011-05-06

    ... to represent the total net realizable value (NRV) of raw magnesium, it used this value as the offset... AVISMA did not make sales to the United States at less than normal value. If these preliminary results... Than Fair Value: Pure Magnesium in Granular Form From the People's Republic of China, 66 FR 49345...

  4. 78 FR 61987 - Corbett Water District; Notice of Preliminary Determination of a Qualifying Conduit Hydropower...

    Science.gov (United States)

    2013-10-09

    ... District; Notice of Preliminary Determination of a Qualifying Conduit Hydropower Facility and Soliciting... construct a qualifying conduit hydropower facility, pursuant to section 30 of the Federal Power Act, as amended by section 4 of the Hydropower Regulatory Efficiency Act of 2013 (HREA). The Corbett Hydroelectric...

  5. Physics issues related to the confinement of ICF experiments in the US National Ignition Facility

    International Nuclear Information System (INIS)

    Tobin, M.; Anderson, A.; Latkowski, J.

    1995-04-01

    ICF experiments planned for the proposed US National Ignition Facility (NIF) will produce emissions of neutrons, x rays, debris, and shrapnel. The NIF Target Area (TA) must acceptably confine these emissions and respond to their effects to allow an efficient rate of experiments, from 600 to possibly 1500 per year, and minimal down time for maintenance. Detailed computer code predictions of emissions are necessary to study their effects and impacts on Target Area operations. Preliminary results show that the rate of debris shield transmission loss (and subsequent periodicity of change-out) due to ablated material deposition is acceptable, neutron effects on optics are manageable, and preliminary safety analyses show a facility rating of low hazard, non-nuclear. Therefore, NIF Target Area design features such as fused silica debris shields, refractory first wall coating, and concrete shielding are effective solutions to confinement of ICF experiment emissions

  6. Preliminary study of magnet design for an SSC

    International Nuclear Information System (INIS)

    Taylor, C.E.; Meuser, R.B.

    1983-08-01

    The overriding design consideration for the SSC magnets is that cost of the facility be minimized; at 8 T, approximately 40 km of bending magnets is required for each ring of a 20 TeV collider. We present some results of a parametric study of two-in-one, iron-core magnets for an SSC. These results are necessarily preliminary in nature, and are intended only to show some of the trade-offs for a wide range of the variables. We show also some results for a reference design that produces 6.5 T in the aperture at 4.4 K for a coil inside diameter of 40 mm. It is not to be inferred that we have established this to be an optimum in any sense

  7. Environmental Survey preliminary report, Idaho National Engineering Laboratory, Idaho Falls, Idaho and Component Development and Integration Facility, Butte, Montana

    International Nuclear Information System (INIS)

    1988-09-01

    This report presents the preliminary findings of the first phase of the Environmental Survey of the United States Department of Energy's (DOE) Idaho National Engineering Laboratory (INEL) and Component Development and Integration Facility (CDIF), conducted September 14 through October 2, 1987. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. The team includes outside experts supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the INEL and CDIF. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations' carried on at the INEL and the CDIF, and interviews with site personnel. The Survey team developed a Sampling and Analysis (S ampersand A) Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The S ampersand A Plan will be executed by the Oak Ridge National Laboratory. When completed, the S ampersand A results will be incorporated into the INEL/CDIF Survey findings for inclusion into the Environmental Survey Summary Report. 90 refs., 95 figs., 77 tabs

  8. Environmental Survey preliminary report, Idaho National Engineering Laboratory, Idaho Falls, Idaho and Component Development and Integration Facility, Butte, Montana

    Energy Technology Data Exchange (ETDEWEB)

    1988-09-01

    This report presents the preliminary findings of the first phase of the Environmental Survey of the United States Department of Energy's (DOE) Idaho National Engineering Laboratory (INEL) and Component Development and Integration Facility (CDIF), conducted September 14 through October 2, 1987. The Survey is being conducted by an interdisciplinary team of environmental specialists, led and managed by the Office of Environment, Safety and Health's Office of Environmental Audit. The team includes outside experts supplied by a private contractor. The objective of the Survey is to identify environmental problems and areas of environmental risk associated with the INEL and CDIF. The Survey covers all environmental media and all areas of environmental regulation. It is being performed in accordance with the DOE Environmental Survey Manual. The on-site phase of the Survey involves the review of existing site environmental data, observations of the operations' carried on at the INEL and the CDIF, and interviews with site personnel. The Survey team developed a Sampling and Analysis (S A) Plan to assist in further assessing certain of the environmental problems identified during its on-site activities. The S A Plan will be executed by the Oak Ridge National Laboratory. When completed, the S A results will be incorporated into the INEL/CDIF Survey findings for inclusion into the Environmental Survey Summary Report. 90 refs., 95 figs., 77 tabs.

  9. Finite-element model evaluation of barrier configurations to reduce infiltration into waste-disposal structures: preliminary results and design considerations

    International Nuclear Information System (INIS)

    Lu, A.H.; Phillips, S.J.; Adams, M.R.

    1982-09-01

    Barriers to reduce infiltration into waste burial disposal structures (trenches, pits, etc.) may be required to provide adequate waste confinement. The preliminary engineering design of these barriers should consider interrelated barrier performance factors. This paper summarizes preliminary computer simulation activities to further engineering barrier design efforts. Several barrier configurations were conceived and evaluated. Models were simulated for each barrier configuration using a finite element computer code. Results of this preliminary evaluation indicate that barrier configurations, depending on their morphology and materials, may significantly influence infiltration, flux, drainage, and storage of water through and within waste disposal structures. 9 figures

  10. Republic of Korea. Closure concept development for LILW disposal facility in Republic of Korea

    International Nuclear Information System (INIS)

    2001-01-01

    Nuclear Environment Technology Institute (NETEC) of Korea Electric Power Corporation (KEPCO) is developing near surface disposal concepts for both a rock cavern type disposal facility, and a vault type facility; two types of facility are being considered to provide more options for LILW repository siting. The conceptual design for the vault type facility will be completed in 1999. As a part of conceptual design effort, a preliminary concept for the disposal facility closure has been identified

  11. NSLS-II Preliminary Design Report

    International Nuclear Information System (INIS)

    Dierker, S.

    2007-01-01

    Following the CD0 approval of the National Synchrotron Light Source II (NSLS-II) during August 2005, Brookhaven National Laboratory prepared a conceptual design for a worldclass user facility for scientific research using synchrotron radiation. DOE SC review of the preliminary baseline in December 2006 led to the subsequent CD1 approval (approval of alternative selection and cost range). This report is the documentation of the preliminary design work for the NSLS-II facility. The preliminary design of the Accelerator Systems (Part 1) was developed mostly based of the Conceptual Design Report, except for the Booster design, which was changed from in-storage-ring tunnel configuration to in external- tunnel configuration. The design of beamlines (Part 2) is based on designs developed by engineering firms in accordance with the specification provided by the Project. The conventional facility design (Part 3) is the Title 1 preliminary design by the AE firm that met the NSLS-II requirements. Last and very important, Part 4 documents the ES and H design and considerations related to this preliminary design. The NSLS-II performance goals are motivated by the recognition that major advances in many important technology problems will require scientific breakthroughs in developing new materials with advanced properties. Achieving this will require the development of new tools that will enable the characterization of the atomic and electronic structure, chemical composition, and magnetic properties of materials, at nanoscale resolution. These tools must be nondestructive, to image and characterize buried structures and interfaces, and they must operate in a wide range of temperatures and harsh environments. The NSLS-II facility will provide ultra high brightness and flux and exceptional beam stability. It will also provide advanced insertion devices, optics, detectors, and robotics, and a suite of scientific instruments designed to maximize the scientific output of the

  12. NSLS-II Preliminary Design Report

    Energy Technology Data Exchange (ETDEWEB)

    Dierker, S.

    2007-11-01

    Following the CD0 approval of the National Synchrotron Light Source II (NSLS-II) during August 2005, Brookhaven National Laboratory prepared a conceptual design for a worldclass user facility for scientific research using synchrotron radiation. DOE SC review of the preliminary baseline in December 2006 led to the subsequent CD1 approval (approval of alternative selection and cost range). This report is the documentation of the preliminary design work for the NSLS-II facility. The preliminary design of the Accelerator Systems (Part 1) was developed mostly based of the Conceptual Design Report, except for the Booster design, which was changed from in-storage-ring tunnel configuration to in external- tunnel configuration. The design of beamlines (Part 2) is based on designs developed by engineering firms in accordance with the specification provided by the Project. The conventional facility design (Part 3) is the Title 1 preliminary design by the AE firm that met the NSLS-II requirements. Last and very important, Part 4 documents the ES&H design and considerations related to this preliminary design. The NSLS-II performance goals are motivated by the recognition that major advances in many important technology problems will require scientific breakthroughs in developing new materials with advanced properties. Achieving this will require the development of new tools that will enable the characterization of the atomic and electronic structure, chemical composition, and magnetic properties of materials, at nanoscale resolution. These tools must be nondestructive, to image and characterize buried structures and interfaces, and they must operate in a wide range of temperatures and harsh environments. The NSLS-II facility will provide ultra high brightness and flux and exceptional beam stability. It will also provide advanced insertion devices, optics, detectors, and robotics, and a suite of scientific instruments designed to maximize the scientific output of the facility

  13. The evaluation of GL impact in Physical sciences using bibliometric indicators : preliminary results

    OpenAIRE

    Di Cesare, Rosa (CNR); GreyNet, Grey Literature Network Service

    1994-01-01

    A bibliometric study of the Italian grey literature in SIGLE database. Preliminary results. Given the increasing importance of Grey Literature (GL) for the information and documentation field, it is essential to apply a bibliometric analysis similar to the one widely used for the conventional literature. Study objectives: 1) impact evalutation of grey literature in physical sciences; and 2) differentiation between scientific and non scientific grey literature documents in the same discipline,...

  14. 78 FR 7395 - Stainless Steel Bar From India: Preliminary Results of Antidumping Duty Administrative Review...

    Science.gov (United States)

    2013-02-01

    ... DEPARTMENT OF COMMERCE International Trade Administration [A-533-810] Stainless Steel Bar From... steel bar (SSB) from India. The period of review (POR) is February 1, 2011, through January 31, 2012... Preliminary Results of Antidumping Duty Administrative Review: Stainless Steel Bar from India'' dated...

  15. Tissue characterization using magnetic resonance elastography: preliminary results

    International Nuclear Information System (INIS)

    Kruse, S.A.; Smith, J.A.; Lawrence, A.J.; Dresner, M.A.; Manduca, A.; Greenleaf, J.F.; Ehman, R.L.

    2000-01-01

    The well-documented effectiveness of palpation as a diagnostic technique for detecting cancer and other diseases has provided motivation for developing imaging techniques for non-invasively evaluating the mechanical properties of tissue. A recently described approach for elasticity imaging, using propagating acoustic shear waves and phase-contrast MRI, has been called magnetic resonance elastography (MRE). The purpose of this work was to conduct preliminary studies to define methods for using MRE as a tool for addressing the paucity of quantitative tissue mechanical property data in the literature. Fresh animal liver and kidney tissue specimens were evaluated with MRE at multiple shear wave frequencies. The influence of specimen temperature and orientation on measurements of stiffness was studied in skeletal muscle. The results demonstrated that all of the materials tested (liver, kidney, muscle and tissue-simulating gel) exhibit systematic dependence of shear stiffness on shear rate. These data are consistent with a viscoelastic model of tissue mechanical properties, allowing calculation of two independent tissue properties from multiple-frequency MRE data: shear modulus and shear viscosity. The shear stiffness of tissue can be substantially affected by specimen temperature. The results also demonstrated evidence of shear anisotropy in skeletal muscle but not liver tissue. The measured shear stiffness in skeletal muscle was found to depend on both the direction of propagation and polarization of the shear waves. (author)

  16. Preliminary definition of the DOE/OCRWM transportation operating system: Final report

    International Nuclear Information System (INIS)

    Rawl, R.R.; Kline, S.C.

    1988-01-01

    This paper is based on the report ''Preliminary Definition of the Transportation Operations System'' and presents a summary of the preliminary definition of transportation operations activities for the cask shipment cycle, commencing with the dispatch of an empty cask, to loading and unloading of cask contents, and preparation of the empty cask for redispatch. It first presents a high-level description of the transportation cycle and then further describes each of the major activities in greater detail. For simplicity of presentation, the highway mode of transport is most often used to describe activities. The reader should keep in mind that the use of other modes will slightly alter the activities and possibly the sequences. Major activities and functions of the system are organized into a first cut of how they could be allocated to specific facilities. The reader should keep in mind that the assignment of functions and the aggregation of these into specific facilities are tasks which have yet to be performed. This paper simply presents a first look at possible groupings of the functions on a facility basis. 12 figs

  17. 76 FR 66271 - Stainless Steel Plate in Coils From Belgium: Notice of Preliminary Results of Antidumping Duty...

    Science.gov (United States)

    2011-10-26

    ... production facilities, supplier relationships, management, and customer base of Aperam are substantially... facilities; (3) supplier relationships; and (4) customer base. See, e.g., Carbon and Certain Alloy Steel Wire... Belgium N.V. resulted in little or no change in management, production facility, supplier relationships...

  18. Current status of collaborative relationships between dialysis facilities and dental facilities in Japan: results of a nationwide survey.

    Science.gov (United States)

    Yoshioka, Masami; Shirayama, Yasuhiko; Imoto, Issei; Hinode, Daisuke; Yanagisawa, Shizuko; Takeuchi, Yuko

    2015-02-12

    Recent studies have reported an association between periodontal disease and mortality among dialysis patients. Therefore, preventive dental care should be considered very important for this population. In Japan, no systematic education has been undertaken regarding the importance of preventive dental care for hemodialysis patients--even though these individuals tend to have oral and dental problems. The aim of this study was to investigate the current state of collaborative relationships between hemodialysis facilities and dental services in Japan and also to identify strategies to encourage preventive dental visits among hemodialysis outpatients. A nationwide questionnaire on the collaborative relationship between dialysis facilities and dental facilities was sent by mail to all medical facilities in Japan offering outpatient hemodialysis treatment. Responses were obtained from 1414 of 4014 facilities (35.2%). Among the 1414 facilities, 272 (19.2%) had a dental service department. Approximately 100,000 dialysis outpatients were receiving treatment at these participating facilities, which amounts to one-third of all dialysis patients in Japan. Of those patients, 82.9% received hemodialysis at medical facilities without dental departments. Only 87 of 454 small clinics without in-house dental departments (19.2%) had collaborative registered dental clinics. Medical facilities with registered dental clinics demonstrated a significantly more proactive attitude to routine collaboration on dental matters than facilities lacking such clinics. Our nationwide survey revealed that most dialysis facilities in Japan have neither an in-house dental department nor a collaborative relationship with a registered dental clinic. Registration of dental clinics appears to promote collaboration with dental facilities on a routine basis, which would be beneficial for oral health management in hemodialysis patients.

  19. 340 Facility secondary containment and leak detection

    International Nuclear Information System (INIS)

    Bendixsen, R.B.

    1995-01-01

    This document presents a preliminary safety evaluation for the 340 Facility Secondary Containment and Leak Containment system, Project W-302. Project W-302 will construct Building 340-C which has been designed to replace the current 340 Building and vault tank system for collection of liquid wastes from the Pacific Northwest Laboratory buildings in the 300 Area. This new nuclear facility is Hazard Category 3. The vault tank and related monitoring and control equipment are Safety Class 2 with the remainder of the structure, systems and components as Safety Class 3 or 4

  20. Preliminary assessment report for Fort William Henry Harrison, Montana Army National Guard, Helena, Montana

    International Nuclear Information System (INIS)

    DuWaldt, J.; Meyer, T.

    1993-07-01

    This report presents the results of the preliminary assessment (PA) conducted by Argonne National Laboratory at a Montana Army National Guard (MTARNG) property near Helena, Montana. Preliminary assessments of federal facilities are being conducted to compile the information necessary for completing preremedial activities and to provide a basis for establishing corrective actions in response to releases of hazardous substances. The principal objective of the PA is to characterize the site accurately and determine the need for further action by examining site activities, quantities of hazardous substances present, and potential pathways by which contamination could affect public health and the environment. This PA satisfies, for the Fort William Henry Harrison property, requirements of the Department of Defense Installation Restoration Program

  1. Preliminary experimental results from a linear reciprocating magnetic refrigerator prototype

    International Nuclear Information System (INIS)

    Tagliafico, Luca Antonio; Scarpa, Federico; Valsuani, Federico; Tagliafico, Giulio

    2013-01-01

    A linear reciprocating magnetic refrigerator prototype was designed and built with the aid of an industrial partner. The refrigerator is based on the Active Magnetic Regenerative cycle, and exploits two regenerators working in parallel. The active material is Gadolinium in plates, 0.8 mm thick, for a total mass of 0.36 kg. The device is described and results about magnetic field and temperature span measurements are presented. The designed permanent magnet structure, based on an improved cross-type arrangement, generates a maximum magnetic field intensity of 1.55 T in air, over a gap of (13 × 50 × 100) mm 3 . The maximum temperature span achieved is 5.0 K, in a free run condition. -- Highlights: ► We give preliminary results from a linear reciprocating magnetic refrigerator prototype. ► The design is intended to process visualization and investigation. ► The prototype behavior gives us various suggestions to improve its general performance

  2. A facility for liquid-phase radiation experiments on heavy ion beams

    Energy Technology Data Exchange (ETDEWEB)

    Stuglik, Z; Zvara, I; Yakushev, A B; Timokhin, S N [Flerov Lab. of Nuclear Reactions, Dubna (Russian Federation). Joint Inst. for Nuclear Research

    1994-05-01

    The facility for liquid-phase radiation experiments installed on the beam line of the U-400 cyclotron in the Flerov Laboratory of Nuclear Reactions, JINR, Dubna, is described. The accelerator provides intermediate energy (some 10 MeV/nucleon) beams of ions ranging from Li to Xe. Preliminary results on the radiolysis of the Fricke solution and malachite green in ethanol by {sup 11}B, {sup 24}Mg and {sup 40}Ca ions are presented. (author).

  3. Hardware availability calculations and results of the IFMIF accelerator facility

    International Nuclear Information System (INIS)

    Bargalló, Enric; Arroyo, Jose Manuel; Abal, Javier; Beauvais, Pierre-Yves; Gobin, Raphael; Orsini, Fabienne; Weber, Moisés; Podadera, Ivan; Grespan, Francesco; Fagotti, Enrico; De Blas, Alfredo; Dies, Javier; Tapia, Carlos; Mollá, Joaquín; Ibarra, Ángel

    2014-01-01

    Highlights: • IFMIF accelerator facility hardware availability analyses methodology is described. • Results of the individual hardware availability analyses are shown for the reference design. • Accelerator design improvements are proposed for each system. • Availability results are evaluated and compared with the requirements. - Abstract: Hardware availability calculations have been done individually for each system of the deuteron accelerators of the International Fusion Materials Irradiation Facility (IFMIF). The principal goal of these analyses is to estimate the availability of the systems, compare it with the challenging IFMIF requirements and find new paths to improve availability performances. Major unavailability contributors are highlighted and possible design changes are proposed in order to achieve the hardware availability requirements established for each system. In this paper, such possible improvements are implemented in fault tree models and the availability results are evaluated. The parallel activity on the design and construction of the linear IFMIF prototype accelerator (LIPAc) provides detailed design information for the RAMI (reliability, availability, maintainability and inspectability) analyses and allows finding out the improvements that the final accelerator could have. Because of the R and D behavior of the LIPAc, RAMI improvements could be the major differences between the prototype and the IFMIF accelerator design

  4. Hardware availability calculations and results of the IFMIF accelerator facility

    Energy Technology Data Exchange (ETDEWEB)

    Bargalló, Enric, E-mail: enric.bargallo-font@upc.edu [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia (UPC), Barcelona (Spain); Arroyo, Jose Manuel [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, Madrid (Spain); Abal, Javier [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia (UPC), Barcelona (Spain); Beauvais, Pierre-Yves; Gobin, Raphael; Orsini, Fabienne [Commissariat à l’Energie Atomique, Saclay (France); Weber, Moisés; Podadera, Ivan [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, Madrid (Spain); Grespan, Francesco; Fagotti, Enrico [Istituto Nazionale di Fisica Nucleare, Legnaro (Italy); De Blas, Alfredo; Dies, Javier; Tapia, Carlos [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia (UPC), Barcelona (Spain); Mollá, Joaquín; Ibarra, Ángel [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, Madrid (Spain)

    2014-10-15

    Highlights: • IFMIF accelerator facility hardware availability analyses methodology is described. • Results of the individual hardware availability analyses are shown for the reference design. • Accelerator design improvements are proposed for each system. • Availability results are evaluated and compared with the requirements. - Abstract: Hardware availability calculations have been done individually for each system of the deuteron accelerators of the International Fusion Materials Irradiation Facility (IFMIF). The principal goal of these analyses is to estimate the availability of the systems, compare it with the challenging IFMIF requirements and find new paths to improve availability performances. Major unavailability contributors are highlighted and possible design changes are proposed in order to achieve the hardware availability requirements established for each system. In this paper, such possible improvements are implemented in fault tree models and the availability results are evaluated. The parallel activity on the design and construction of the linear IFMIF prototype accelerator (LIPAc) provides detailed design information for the RAMI (reliability, availability, maintainability and inspectability) analyses and allows finding out the improvements that the final accelerator could have. Because of the R and D behavior of the LIPAc, RAMI improvements could be the major differences between the prototype and the IFMIF accelerator design.

  5. Archaeogeophysical investigations in Tiwanaku: preliminary results

    Science.gov (United States)

    Masini, Nicola; Sileo, Maria; Lasaponara, Rosa; Leucci, Giovanni; Orefici, Giuseppe; Rizzo, Enzo

    2017-04-01

    -1450) Tiwanaku was characterized by the resurgence of regional identities and polities In spite of the rich archaeological record numerous issues, related to the function and the extension of Tiwanaku, need to be investigated especially in the monumental core which includes the pyramid of Akapana, and other ceremonial places such Kalasasaya, Putuni and Kantatallita. To this aims some geophysical investigations were performed in 2009 and 2014 in the context of multidisciplinary research including the use of satellite remote sensing [8]. This paper deals with the discussion of preliminary results of geomagnetic and GPR investigations, some of which have been verified by trial archaeological excavations which have unearthed some buried structures, improving the knowledge of the ceremonial areas of Tiwanaku. References [1] Lasaponara R., Leucci G., Masini N., Persico R., Scardozzi G., Towards an operative use of remote sensing for exploring the past using satellite data: The case study of Hierapolis (Turkey), Remote sensing of Environment, 174 (2016) : 148-164, doi:10.1016/j.rse.2015.12.016 [2] Masini N., Lasaponara R., Rizzo E., Orefici G. 2012. Integrated Remote Sensing Approach in Cahuachi (Peru): Studies and Results of the ITACA Mission (2007-2010), In: Lasaponara R., Masini N. (Eds) 2012, Satellite Remote Sensing: a new tool for Archaeology, Springer, Verlag Berlin Heidelberg, ISBN 978-90-481-8800-0, doi: 10.1007/978-90-481-8801-7_14; pp. 307-344 [3] Rizzo E., Masini N., Lasaponara R., Orefici G. 2010, ArchaeoGeophysical methods in the Templo del Escalonado (Cahuachi, Nasca, Perù), Near Surface Geophysics 8 (5), 433-439, doi:10.3997/1873-0604.2010030 [4] Masini N., Rizzo E., Lasaponara R., and Orefici G. 2008, Integrated remote sensing techniques for the detection of buried archaeological adobe structures: preliminary results in Cahuachi (Peru), Advances in Geosciences, 19, 75-82 [5] Lasaponara R., Leucci G., Masini N., Persico R. 2014. Investigating archaeological looting

  6. Preliminary Overview of a Helium Cooling System for the Secondary Helium Loop in VHTR-based SI Hydrogen Production Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Youngjoon; Cho, Mintaek; Kim, Dahee; Lee, Taehoon; Lee, Kiyoung; Kim, Yongwan [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    Nuclear hydrogen production facilities consist of a very high temperature gas-cooled nuclear reactor (VHTR) system, intermediate heat exchanger (IHX) system, and a sulfur-iodine (SI) thermochemical process. This study focuses on the coupling system between the IHX system and SI thermochemical process. To prevent the propagation of the thermal disturbance owing to the abnormal operation of the SI process components from the IHX system to the VHTR system, a helium cooling system for the secondary helium of the IHX is required. In this paper, the helium cooling system has been studied. The temperature fluctuation of the secondary helium owing to the abnormal operation of the SI process was then calculated based on the proposed coupling system model. Finally, the preliminary conceptual design of the helium cooling system with a steam generator and forced-draft air-cooled heat exchanger to mitigate the thermal disturbance has been carried out. A conceptual flow diagram of a helium cooling system between the IHX and SI thermochemical processes in VHTR-based SI hydrogen production facilities has been proposed. A helium cooling system for the secondary helium of the IHX in this flow diagram prevents the propagation of the thermal disturbance from the IHX system to the VHTR system, owing to the abnormal operation of the SI process components. As a result of a dynamic simulation to anticipate the fluctuations of the secondary helium temperature owing to the abnormal operation of the SI process components with a hydrogen production rate of 60 mol·H{sub 2}/s, it is recommended that the maximum helium cooling capacity to recover the normal operation temperature of 450 .deg. C is 31,933.4 kJ/s. To satisfy this helium cooling capacity, a U-type steam generator, which has a heat transfer area of 12 m{sup 2}, and a forced-draft air-cooled condenser, which has a heat transfer area of 12,388.67 m{sup 2}, are required for the secondary helium cooling system.

  7. Fuel Coolant Interaction Results in the Fuel Pins Melting Facility (PMF)

    International Nuclear Information System (INIS)

    Urunashi, H.; Hirabayashi, T.; Mizuta, H.

    1976-01-01

    The experimental work related to FCI at PNC has been concentrated into the molten UO 2 dropping test. After the completion of molten UO 2 drop experiments, emphasis is directed toward the FCI phenomena of the initiating conditions of the accident under the more realistic geometry. The experiments are conducted within the Pin Melt Facility (PMF) in which UO 2 pellets clad in stainless steel are melted by direct electric heating under the stagnant or flowing sodium. The primary objectives of the PMF test are to: - obtain detail experimental results (heat-input, clad temperature, sodium temperature, etc.) on the FCI under TOP and LOF conditions; - observe the movement of the fuel before and after the pin failure by the X-ray cinematography; - observe the degree of coherence of the pin failures; - accumulate the experience of the FCI experiment which is applicable to the subassembly or more larger scale; - simulate the fuel behavior of the in-pile test (GETR, CABRI). The preliminary conclusions can be drawn from the foregoing observations are as follows: - Although the fuel motion and FCI of the closed test section appeared to be different from those of the open test section, the conclusion of the effect of the inside pressure on FCI needs more experimental data. - The best heating condition of the UO 2 pellet for the FCI study with PMF is established as 40 w/cm at the steady state and 1680 J/g of UO 2 during the additional transient state. The total energy deposition of the UO 2 pellet is thus estimated in the range of 2400 J/g of UO 2 -2600 J/g of UO 2 . The analytical model of the fuel pin failure and the subsequent FCI are suggested to count the following parameters: - The fuel pin failure due to the fuel vaporization due to the rapid energy deposition; - Molten fuel, clad and sodium interaction in the fuel pin after the pin failure; - The upward flow of molten fuel with molten clad or vapor sodium, as well as the slumping of molten fuel

  8. Preliminary results on the cryogenic target for FIREX project

    International Nuclear Information System (INIS)

    Iwamoto, A.; Maekawa, R.; Mito, T.; Okamoto, M.; Motojima, O.; Nakai, M.; Norimatsu, T.; Nagai, K.

    2006-01-01

    Preliminary tests on the cryogenic target for the fast ignition realization experiment (FIREX) project has been conducted. A foam shell method is proposed to realize its target design. A foam target consists of three parts: a foam shell, a conical laser guide and a liquid or gas feeder made of glass. The shell is a hollow sphere (500 μm in diameter) with a uniform and thin foam layer (about 20 μm in thickness). Epoxy resin is utilized to assemble the parts into the target. Liquid fuel is fed into the shell by the feeder and is soaked up by the foam material through capillarity. The fuel is then solidified. Regarding target fabrication, one of the concerns is the influence on various thermal contractions from the different materials when it is cooled down to cryogenic environment. This paper describes the result on the validity check at cryogenic environment and the demonstration of H 2 liquefaction using a dummy target instead of the foam target. Judging from these results, the target assembled in the same process as the dummy target is sure to be practicable for the FIREX project. (authors)

  9. Preliminary plan for decommissioning - repository for spent nuclear fuel

    International Nuclear Information System (INIS)

    Hallberg, Bengt; Tiberg, Liselotte

    2010-06-01

    The final disposal facility for spent nuclear fuel is part of the KBS-3 system, which also consists of a central facility for interim storage and encapsulation of the spent nuclear fuel and a transport system. The nuclear fuel repository will be a nuclear facility. Regulation SSMFS 2008:1 (Swedish Radiation Safety Authority's regulations on safety of nuclear facilities) requires that the licensee must have a current decommissioning plan throughout the facility lifecycle. Before the facility is constructed, a preliminary decommissioning plan should be reported to the Swedish Radiation Safety Authority. This document is a preliminary decommissioning plan, and submitted as an attachment to SKB's application for a license under the Nuclear Activities Act to construct, own and operate the facility. The final disposal facility for spent nuclear fuel consists of an above ground part and a below ground part and will be built near Forsmark and the final repository for radioactive operational waste, SFR. The parts above and below ground are connected by a ramp and several shafts, e.g. for ventilation. The below ground part consists of a central area, and several landfill sites. The latter form the repository area. The sealed below ground part constitutes the final repository. The decommissioning is taking place after the main operation has ended, that is, when all spent nuclear fuel has been deposited and the deposition tunnels have been backfilled and plugged. The decommissioning involves sealing of the remaining parts of the below ground part and demolition of above ground part. When decommissioning begins, there will be no contamination in the facility. The demolition is therefore performed as for a conventional plant. Demolition waste is sorted and recycled whenever possible or placed in landfill. Hazardous waste is managed in accordance with current regulations. A ground investigation is performed and is the basis for after-treatment of the site. The timetable for the

  10. WISE/NEOWISE OBSERVATIONS OF THE JOVIAN TROJANS: PRELIMINARY RESULTS

    International Nuclear Information System (INIS)

    Grav, T.; Mainzer, A. K.; Bauer, J.; Masiero, J.; Eisenhardt, P. R. M.; Blauvelt, E.; DeBaun, E.; Elsbury, D.; Gautier, T. IV; Gomillion, S.; Hand, E.; Wilkins, A.; Spahr, T.; McMillan, R. S.; Walker, R.; Cutri, R.; Wright, E.

    2011-01-01

    We present the preliminary analysis of over 1739 known and 349 candidate Jovian Trojans observed by the NEOWISE component of the Wide-field Infrared Survey Explorer (WISE). With this survey the available diameters, albedos, and beaming parameters for the Jovian Trojans have been increased by more than an order of magnitude compared to previous surveys. We find that the Jovian Trojan population is very homogenous for sizes larger than ∼10 km (close to the detection limit of WISE for these objects). The observed sample consists almost exclusively of low albedo objects, having a mean albedo value of 0.07 ± 0.03. The beaming parameter was also derived for a large fraction of the observed sample, and it is also very homogenous with an observed mean value of 0.88 ± 0.13. Preliminary debiasing of the survey shows that our observed sample is consistent with the leading cloud containing more objects than the trailing cloud. We estimate the fraction to be N(leading)/N(trailing) ∼ 1.4 ± 0.2, lower than the 1.6 ± 0.1 value derived by Szabó et al.

  11. The engineering test facility

    International Nuclear Information System (INIS)

    Steiner, D.; Becraft, W.R.; Sager, P.H.

    1981-01-01

    The vehicle by which the fusion program would move into the engineering testing phase of fusion power development is designated the Engineering Test Facility (ETF). The ETF would provide a test-bed for reactor components in the fusion environment. In order to initiate preliminary planning for the ETF decision, the Office of Fusion Energy established the ETF Design Center activity to prepare the design of the ETF. This paper describes the design status of the ETF. (orig.)

  12. Assessment and mitigation of electromagnetic pulse (EMP) impacts at short-pulse laser facilities

    International Nuclear Information System (INIS)

    Brown, C G Jr; Bond, E; Clancy, T; Dangi, S; Eder, D C; Ferguson, W; Kimbrough, J; Throop, A

    2010-01-01

    The National Ignition Facility (NIF) will be impacted by electromagnetic pulse (EMP) during normal long-pulse operation, but the largest impacts are expected during short-pulse operation utilizing the Advanced Radiographic Capability (ARC). Without mitigation these impacts could range from data corruption to hardware damage. We describe our EMP measurement systems on Titan and NIF and present some preliminary results and thoughts on mitigation.

  13. Dry Transfer Facility No.1 - Ventilation Confinement Zoning Analysis

    International Nuclear Information System (INIS)

    K.D. Draper

    2005-01-01

    The purpose of this analysis is to establish the preliminary Ventilation Confinement Zone (VCZ) for the Dry Transfer Facility (DTF). The results of this document is used to determine the air quantities for each VCZ that will eventually be reflected in the development of the Ventilation Flow Diagrams. The calculations contained in this document were developed by D and E/Mechanical-HVAC and are intended solely for the use of the D and E/Mechanical-HVAC department in its work regarding the HVAC system for the Dry Transfer Facility. Yucca Mountain Project personnel from the D and E/Mechanical-HVAC department should be consulted before use of the calculation for purposes other than those stated herein or used by individuals other than authorized personnel in D and E/Mechanical-HVAC department

  14. Preliminary results on ocean dynamics from Skylab and their implications for future spacecraft

    Science.gov (United States)

    Hayes, J.; Pierson, W. J.; Cardone, V. J.

    1975-01-01

    The instrument aboard Skylab designated S193 - a combined passive and active microwave radar system acting as a radiometer, scatterometer, and altimeter - is used to measure the surface vector wind speeds in the planetary boundary layer over the oceans. Preliminary results corroborate the hypothesis that sea surface winds in the planetary boundary layer can be determined from satellite data. Future spacecraft plans for measuring a geoid with an accuracy up to 10 cm are discussed.

  15. 78 FR 32367 - Multilayered Wood Flooring From the People's Republic of China; Preliminary Results of...

    Science.gov (United States)

    2013-05-30

    ... From the People's Republic of China; Preliminary Results of Antidumping Duty New Shipper Review; 2011... duty order on multilayered wood flooring (``MLWF'') from the People's Republic of China (``PRC''). The period of review (``POR'') is May 26, 2011 through May 31, 2012. The review covers one exporter of...

  16. Preliminary assessment of safeguardability on the concepture design of advanced spent fuel conditioning process

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sang Yoon; Ha, Jang Ho; Ko, Won Il; Song, Dae Yong; Kim, Ho Dong

    2003-04-01

    In this report, a preliminary study on the safeguardability of ACP (Advanced spent fuel Conditioning Process) was conducted with Los Alamos National Laboratory. The proposed ACP concept is an electrometallurgical treatment technique to convert oxide-type spent nuclear fuels into metal forms, which can achieve significant reduction of the volume and heat load of spent fuel to be stored and disposed of. For the safeguardability analysis of the ACP facility, sub-processes and their KMPs (Key Measurement Points) were defined first, and then their material flows were analyzed. Finally, the standard deviation of the Inventory Difference (ID) value of the facility was estimated with assumption by assuming international target values for the uncertainty of measurement methods and their uncertainty. From the preliminary calculation, we concluded that if the assumptions regarding measurement instruments can be achieved in a safeguards system for the ACP facility, the safeguards goals of International Atomic Energy Agency (IAEA) could be met. In the second phase of this study, further study on sensitivity analyses considering various factors such as measurement errors, facility capacities, MBA periods etc. may be needed.

  17. Preliminary assessment of safeguardability on the concepture design of advanced spent fuel conditioning process

    International Nuclear Information System (INIS)

    Lee, Sang Yoon; Ha, Jang Ho; Ko, Won Il; Song, Dae Yong; Kim, Ho Dong

    2003-04-01

    In this report, a preliminary study on the safeguardability of ACP (Advanced spent fuel Conditioning Process) was conducted with Los Alamos National Laboratory. The proposed ACP concept is an electrometallurgical treatment technique to convert oxide-type spent nuclear fuels into metal forms, which can achieve significant reduction of the volume and heat load of spent fuel to be stored and disposed of. For the safeguardability analysis of the ACP facility, sub-processes and their KMPs (Key Measurement Points) were defined first, and then their material flows were analyzed. Finally, the standard deviation of the Inventory Difference (ID) value of the facility was estimated with assumption by assuming international target values for the uncertainty of measurement methods and their uncertainty. From the preliminary calculation, we concluded that if the assumptions regarding measurement instruments can be achieved in a safeguards system for the ACP facility, the safeguards goals of International Atomic Energy Agency (IAEA) could be met. In the second phase of this study, further study on sensitivity analyses considering various factors such as measurement errors, facility capacities, MBA periods etc. may be needed

  18. National Ignition Facility frequency converter development

    International Nuclear Information System (INIS)

    Barker, C.E.; Auerbach, J.M.; Adams, C.H.

    1996-01-01

    A preliminary error budget for the third harmonic converter for the National Ignition Facility (NIF) laser driver has been developed using a root-sum-square-accumulation of error sources. Such a budget sets an upper bound on the allowable magnitude of the various effects that reduce conversion efficiency. Development efforts on crystal mounting technology and crystal quality studies are discussed

  19. Report of the research results with joint-use facilities in fiscal year 1977

    International Nuclear Information System (INIS)

    1978-01-01

    In the Nuclear Engineering Research Laboratory, the University of Tokyo, fast neutron source reactor 'Yayoi', linac and fusion-reactor blanket facility are jointly used by educational institutions. Research results from the joint uses of the facilities in fiscal 1977 are presented in individual summaries: (on-pile) irradiation, reactor physics and engineering, etc., (off-pile) equipment and component techniques, etc., (linac) operation, etc., with these joint uses, unique works are intended in resonable way. (Mori, K.)

  20. Survey of active and inactive mines for possible use as in situ test facilities

    International Nuclear Information System (INIS)

    1976-09-01

    A survey of active and inactive mines which might be useful for radioactive waste storage in situ test experiments was conducted. It was performed for Union Carbide Corporation, Nuclear Division, Office of Waste Isolation. The report covers available information gathered from literature, U.S. Bureau of Mines, the Mining Enforcement and Safety Agency, and a limited number of personal contacts with constructors or operators of facilities. This survey is preliminary in nature and the objective is to develop potential candidate facilities for in situ experiments which warrant further investigation. Included are descriptions of 244 facilities, with all the data about each one which was available within the time restraint of the study. These facility descriptions are additionally indexed by depth of mine, nature of the country rock, mineral mined, and type of entry. A total of 14 inactive mines and 34 active mines has been selected as those most worthy of further investigation for possible service as nuclear waste isolation test facilities. This investigation, being preliminary and having been performed in a very short time period, must be qualified, and the description of the qualification is presented in the body of this report. Qualifications deal primarily with the hazard of having omitted facilities and having incomplete data in some instances. Results indicate sedimentary rock mines of minerals of evaporite origin as a first ranking of preference for in situ testing, followed by other sedimentary rocks and then by mines producing minerals from any type rock where the mine is above the local water table. These are general rules and of course there can be exceptions to them

  1. Greenfield Alternative Study LEU-Mo Fuel Fabrication Facility

    Energy Technology Data Exchange (ETDEWEB)

    Washington Division of URS

    2008-07-01

    This report provides the initial “first look” of the design of the Greenfield Alternative of the Fuel Fabrication Capability (FFC); a facility to be built at a Greenfield DOE National Laboratory site. The FFC is designed to fabricate LEU-Mo monolithic fuel for the 5 US High Performance Research Reactors (HPRRs). This report provides a pre-conceptual design of the site, facility, process and equipment systems of the FFC; along with a preliminary hazards evaluation, risk assessment as well as the ROM cost and schedule estimate.

  2. 78 FR 66355 - Pleasant Grove City, UT; Notice of Preliminary Determination of a Qualifying Conduit Hydropower...

    Science.gov (United States)

    2013-11-05

    ... City, UT; Notice of Preliminary Determination of a Qualifying Conduit Hydropower Facility and... Grove City, Utah (Pleasant Grove) filed a notice of intent to construct a qualifying conduit hydropower facility, pursuant to section 30 of the Federal Power Act, as amended by section 4 of the Hydropower...

  3. 78 FR 53752 - City of Sandpoint, Idaho; Notice of Preliminary Determination of a Qualifying Conduit Hydropower...

    Science.gov (United States)

    2013-08-30

    ... Sandpoint, Idaho; Notice of Preliminary Determination of a Qualifying Conduit Hydropower Facility and... intent to construct a qualifying conduit hydropower facility, pursuant to section 30 of the Federal Power Act, as amended by section 4 of the Hydropower Regulatory Efficiency Act of 2013 (HREA). The Little...

  4. 78 FR 61985 - City of Astoria, Oregon; Notice of Preliminary Determination of a Qualifying Conduit Hydropower...

    Science.gov (United States)

    2013-10-09

    ..., Oregon; Notice of Preliminary Determination of a Qualifying Conduit Hydropower Facility and Soliciting... of intent to construct a qualifying conduit hydropower facility, pursuant to section 30 of the Federal Power Act, as amended by section 4 of the Hydropower Regulatory Efficiency Act of 2013 (HREA). The...

  5. Preliminary Results from Second Phase Sea Testing of the Wave Dragon Prototype Wave Energy Converter

    DEFF Research Database (Denmark)

    Soerensen, Hans Chr.; Tedd, James; Friis-Madsen, Erik

    2006-01-01

    In March 2006 the prototype Wave Dragon has been redeployed to a more energetic site in Nissum Bredning an inland sea in Western Denmark. This has followed a period of renovation of many aspects of the device which have resulted in 20% higher energy output. This paper describes the preliminary...

  6. 76 FR 26241 - Polyethylene Retail Carrier Bags From Thailand: Extension of Time Limit for Preliminary Results...

    Science.gov (United States)

    2011-05-06

    ... DEPARTMENT OF COMMERCE International Trade Administration [A-549-821] Polyethylene Retail Carrier Bags From Thailand: Extension of Time Limit for Preliminary Results of Antidumping Duty Administrative...) initiated an administrative review of the antidumping duty order on polyethylene retail carrier bags from...

  7. DETECTION OF Helicobacter pylori IN GASTRIC MUCOSA OF SHEEP: PRELIMINARY RESULTS

    Directory of Open Access Journals (Sweden)

    A. Rella

    2013-02-01

    Full Text Available Helicobacter pylori is an organism widespread in humans and sometimes responsible for serious illnesses. It has been hypothesized the existence of animal reservoirs, and that the infection route by H. pylori involves multiple pathways including food-borne transmission as the microorganism has been detected from sheep, goat and cow milk. This work reports the preliminary results of a survey conducted in order to investigate the presence of H. pylori in gastric mucosa of sheep slaughtered in Apulia region (Italy employing a Nested Polymerase Chain Reaction (Nested-PCR assay for the detection of the phosphoglucosamine mutase gene (glmM, as screening method followed by conventional bacteriological isolation. Out of the 50 gastric mucosa samples examined, 3 (6% resulted positive for the presence of glmMgene, but at this time no strains were isolated. The results deserve further investigations to asses the role of ruminants as possible reservoirs of H. pylori.

  8. Hazard classification criteria for non-nuclear facilities

    International Nuclear Information System (INIS)

    Mahn, J.A.; Walker, S.A.

    1997-01-01

    Sandia National Laboratories' Integrated Risk Management Department has developed a process for establishing the appropriate hazard classification of a new facility or operation, and thus the level of rigor required for the associated authorization basis safety documentation. This process is referred to as the Preliminary Hazard Screen. DOE Order 5481.1B contains the following hazard classification for non-nuclear facilities: high--having the potential for onsite or offsite impacts to large numbers of persons or for major impacts to the environment; moderate--having the potential for considerable onsite impacts but only minor offsite impacts to people or the environment; low--having the potential for only minor onsite and negligible offsite impacts to people or the environment. It is apparent that the application of such generic criteria is more than likely to be fraught with subjective judgment. One way to remove the subjectivity is to define health and safety classification thresholds for specific hazards that are based on the magnitude of the hazard, rather than on a qualitative assessment of possible accident consequences. This paper presents the results of such an approach to establishing a readily usable set of non-nuclear facility hazard classifications

  9. Fast-neutron dosimetry in the seed-irradiation facility, ASTRA reactor, Seibersdorf

    International Nuclear Information System (INIS)

    Ahnstroem, G.; Burtscher, A.; Casta, J.

    1967-01-01

    An important part of the co-ordinated programme on the neutron irradiation of seeds has been the construction of a fast-neutron irradiation facility for swimming-pool reactors. This facility was installed around 70 cm from the core in the ASTRA reactor swimming-pool at the end of December, 1966. Also, for this programme a pair of constant potential ionization chambers have been constructed at the Institute of Biochemistry, Stockholm University. These chambes are of the type described in the technical annex and are the same size as the seed-irradiation vials to be used in the seed-irradiation container (diam. =15 mm, length = 60 mm). Some preliminary dosimetry experiments were undertaken to test the irradiation facility and the ionization chambers, and to investigate the usefulness of the dosimetry instructions in the Technical Annex. The results of these experiments are discussed in this paper. 3 refs, 6 figs, 7 tabs

  10. Preliminary Results of Cleaning Process for Lubricant Contamination

    Science.gov (United States)

    Eisenmann, D.; Brasche, L.; Lopez, R.

    2006-03-01

    Fluorescent penetrant inspection (FPI) is widely used for aviation and other components for surface-breaking crack detection. As with all inspection methods, adherence to the process parameters is critical to the successful detection of defects. Prior to FPI, components are cleaned using a variety of cleaning methods which are selected based on the alloy and the soil types which must be removed. It is also important that the cleaning process not adversely affect the FPI process. There are a variety of lubricants and surface coatings used in the aviation industry which must be removed prior to FPI. To assess the effectiveness of typical cleaning processes on removal of these contaminants, a study was initiated at an airline overhaul facility. Initial results of the cleaning study for lubricant contamination in nickel, titanium and aluminum alloys will be presented.

  11. Preliminary Results of Cleaning Process for Lubricant Contamination

    International Nuclear Information System (INIS)

    Eisenmann, D.; Brasche, L.; Lopez, R.

    2006-01-01

    Fluorescent penetrant inspection (FPI) is widely used for aviation and other components for surface-breaking crack detection. As with all inspection methods, adherence to the process parameters is critical to the successful detection of defects. Prior to FPI, components are cleaned using a variety of cleaning methods which are selected based on the alloy and the soil types which must be removed. It is also important that the cleaning process not adversely affect the FPI process. There are a variety of lubricants and surface coatings used in the aviation industry which must be removed prior to FPI. To assess the effectiveness of typical cleaning processes on removal of these contaminants, a study was initiated at an airline overhaul facility. Initial results of the cleaning study for lubricant contamination in nickel, titanium and aluminum alloys will be presented

  12. Preliminary research results for parameter diagnostics of intense pulsed ion beams

    International Nuclear Information System (INIS)

    Yang Hailiang; Qiu Aici; Sun Jianfeng; He Xiaoping; Tang Junping; Wang Haiyang; Li Jingya; Ren Shuqing; Huang Jianjun; Zhang Jiasheng; Peng Jianchang; Ouyang Xiaoping; Zhang Guoguang; Li Hongyu

    2004-01-01

    The preliminary experimental results for parameter diagnostics of intense pulsed ion beams from the FLASH II accelerator were reported. The ion number of an intense pulsed ion beam were experimentally determined by monitoring delayed radioactivity from protons induced nuclear reactions in a 12 C target. The prompt γ-rays and diode Bremsstrahlung X-rays were measured with PIN semi-conductor detector and a ST401 plastic scintillator detector. The Bremsstrahlung distribution outside of the drift tube was detected with a thermoluminescent detector and the shielding design was also determined. The current densities of beam were measured with biased ion collector array. The ion beams were also recorded with a CR-39 detector. (author)

  13. The NRU blowdown test facility commissioning program

    Energy Technology Data Exchange (ETDEWEB)

    Walsworth, J A; Zanatta, R J; Yamazaki, A R; Semeniuk, D D; Wong, W; Dickson, L W; Ferris, C E; Burton, D H [Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs.

    1990-12-31

    A major experimental program has been established at the Chalk River Nuclear Laboratories (CRL) that will provide essential data on the thermal and mechanical behaviour of nuclear fuel under abnormal reactor operating conditions and on the transient release, transport and deposition of fission product activity from severely degraded fuel. A number of severe fuel damage (SFD) experiments will be conducted within the Blowdown Test Facility (BTF) at CRL. A series of experiments are being conducted to commission this new facility prior to the SFD program. This paper describes the features and the commissioning program for the BTF. A development and testing program is described for critical components used on the reactor test section. In-reactor commissioning with a fuel assembly simulator commenced in 1989 June and preliminary results are given. The paper also outlines plans for future all-effects, in-reactor tests of CANDU-designed fuel. (author). 11 refs., 3 tabs., 7 figs.

  14. Preliminary results in double cusp tandem mirror MM-4U

    International Nuclear Information System (INIS)

    Ming Linzhou; Tian Zhongyu; Feng Xiaozhen

    1990-10-01

    MM-4U device and preliminary experimental results are presented. Main results are as follows: The plasma has been produced by means of the injection of strong electron current; the axial profile of the plasma potential and the plasma electron density have been obtained respectively, they had a simular form; the plasma potential in the centre of the east cusp, the west cusp and the simple mirror; V e = -180V, V w = -164V, V m -1.8V; the electron density: n e = 1.7 x 10 11 cm -3 , n w = 4.7 x 10 10 cm -3 , n m = 7.5 x 10 7 cm -3 ; the electron temperature: T e = (19.9 ± 1.6) eV, T w = (20.7 ± 1.7) eV; the plasma pressure at 8 cm on the right of the west cusp centre is about 6.76 Pa, β ≅ 1.7 x 10 -3 . The plasma instability has been observed in the simple mirror, its vibration frequency was 7∼9.2 kHz. The results are discussed. The next new task of the physical experiment are proposed

  15. New large solar photocatalytic plant: set-up and preliminary results.

    Science.gov (United States)

    Malato, S; Blanco, J; Vidal, A; Fernández, P; Cáceres, J; Trincado, P; Oliveira, J C; Vincent, M

    2002-04-01

    A European industrial consortium called SOLARDETOX has been created as the result of an EC-DGXII BRITE-EURAM-III-financed project on solar photocatalytic detoxification of water. The project objective was to develop a simple, efficient and commercially competitive water-treatment technology, based on compound parabolic collectors (CPCs) solar collectors and TiO2 photocatalysis, to make possible easy design and installation. The design, set-up and preliminary results of the main project deliverable, the first European industrial solar detoxification treatment plant, is presented. This plant has been designed for the batch treatment of 2 m3 of water with a 100 m2 collector-aperture area and aqueous aerated suspensions of polycrystalline TiO2 irradiated by sunlight. Fully automatic control reduces operation and maintenance manpower. Plant behaviour has been compared (using dichloroacetic acid and cyanide at 50 mg l(-1) initial concentration as model compounds) with the small CPC pilot plants installed at the Plataforma Solar de Almería several years ago. The first results with high-content cyanide (1 g l(-1)) waste water are presented and plant treatment capacity is calculated.

  16. 78 FR 56872 - City of Barre, Vermont; Notice of Preliminary Determination of a Qualifying Conduit Hydropower...

    Science.gov (United States)

    2013-09-16

    ..., Vermont; Notice of Preliminary Determination of a Qualifying Conduit Hydropower Facility and Soliciting... construct a qualifying conduit hydropower facility, pursuant to section 30 of the Federal Power Act, as amended by section 4 of the Hydropower Regulatory Efficiency Act of 2013 (HREA). The Nelson Street 17 kW...

  17. The effect of parental involvement in CBT of anxious children: Preliminary results from a RCT study

    DEFF Research Database (Denmark)

    Esbjørn, Barbara Hoff; Breinholst, Sonja; Reinholdt-Dunne, Marie Louise

    2011-01-01

    Esbjørn, B. H., Breinholst, S., Reinholdt-Dunne, M. L., & Leth, I. (2011). The effect of parental involvement in CBT of anxious children: Preliminary results from a RCT study. Poster accepted for the Association for Behavioral and Cognitive Therapies, Toronto, Canada....

  18. 75 FR 25207 - Polyethylene Retail Carrier Bags From Malaysia: Extension of Time Limit for Preliminary Results...

    Science.gov (United States)

    2010-05-07

    ... polyethylene retail carrier bags from Malaysia for the period August 1, 2008, through July 31, 2009. See... DEPARTMENT OF COMMERCE International Trade Administration A-557-813 Polyethylene Retail Carrier Bags From Malaysia: Extension of Time Limit for Preliminary Results of Antidumping Duty Administrative...

  19. Preliminary Safety Analysis Report for the Transuranic Storage Area Retrieval Enclosure at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    1993-03-01

    This Transuranic Storage Area Retrieval Enclosure Preliminary Safety Analysis Report was completed as required by DOE Order 5480.23. The purpose of this document is to construct a safety basis that supports the design and permits construction of the facility. The facility has been designed to the requirements of a Radioactive Solid Waste Facility presented in DOE Order 6430.1A

  20. A preliminary analysis of floating production storage and offloading facilities with gas liquefaction processes

    DEFF Research Database (Denmark)

    Nguyen, Tuong-Van; Carranza-Sánchez, Yamid Alberto; Junior, Silvio de Oliveira

    2016-01-01

    Floating, production, storage and offloading (FPSO) plants are facilities used in upstream petroleum processing. They have gained interest because they are more flexible than conventional plants and can be used for producing oil and gas in deep-water fields. In general, gas export is challenging...... because of the lack of infrastructure in remote locations. The present work investigates the possibility of integrating liquefaction processes on such facilities, considering two mixed-refrigerant and two expansion-based processes suitable for offshore applications. Two FPSO configurations are considered...... in this work, and they were suggested by Brazilian operators for fields processing natural gas with moderate to high content of carbon dioxide. The performance of the combined systems is analysed by conducting energy and exergy analyses. The integration of gas liquefaction results in greater power consumption...

  1. Precise Hypocenter Determination around Palu Koro Fault: a Preliminary Results

    Science.gov (United States)

    Fawzy Ismullah, M. Muhammad; Nugraha, Andri Dian; Ramdhan, Mohamad; Wandono

    2017-04-01

    Sulawesi area is located in complex tectonic pattern. High seismicity activity in the middle of Sulawesi is related to Palu Koro fault (PKF). In this study, we determined precise hypocenter around PKF by applying double-difference method. We attempt to investigate of the seismicity rate, geometry of the fault and distribution of focus depth around PKF. We first re-pick P-and S-wave arrival time of the PKF events to determine the initial hypocenter location using Hypoellipse method through updated 1-D seismic velocity. Later on, we relocated the earthquake event using double-difference method. Our preliminary results show the distribution of relocated events are located around PKF and have smaller residual time than the initial location. We will enhance the hypocenter location through updating of arrival time by applying waveform cross correlation method as input for double-difference relocation.

  2. Preliminary Results of the Louisiana Sex Offender Treatment Program

    OpenAIRE

    Lee A. Underwood; Frances L.L. Dailey; Carrie Merino; Yolanda Crump

    2015-01-01

    The purpose of this study was to offer preliminary support for the Louisiana Sex Offender Treatment Program (LSOTP) in addressing the needs of juvenile sex offenders. Research objectives were (1) to offer statistical evidence for reductions in anxiety, depression, cognitive distortion and negative attitudes towards women comparing a group of 21 adolescents, 12 of whom received services as usual and nine of whom participated in the LSOTP. A controlled experimental evaluation design was utilize...

  3. Mirror Fusion Test Facility magnet system

    International Nuclear Information System (INIS)

    VanSant, J.H.; Kozman, T.A.; Bulmer, R.H.; Ng, D.S.

    1981-01-01

    In 1979, R.H. Bulmer of Lawrence Livermore National Laboratory (LLNL) discussed a proposed tandem-mirror magnet system for the Mirror Fusion Test Facility (MFTF) at the 8th symposium on Engineering Problems in Fusion Research. Since then, Congress has voted funds for expanding LLNL's MFTF to a tandem-mirror facility (designated MFTF-B). The new facility, scheduled for completion by 1985, will seek to achieve two goals: (1) Energy break-even capability (Q or the ratio of fusion energy to plasma heating energy = 1) of mirror fusion, (2) Engineering feasibility of reactor-scale machines. Briefly stated, 22 superconducting magnets contained in a 11-m-diam by 65-m-long vacuum vessel will confine a fusion plasma fueled by 80 axial streaming-plasma guns and over 40 radial neutral beams. We have already completed a preliminary design of this magnet system

  4. Engineering test facility design center

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    The vehicle by which the fusion program would move into the engineering testing phase of fusion power development is designated the Engineering Test Facility (ETF). The ETF would provide a test bed for reactor components in the fusion environment. In order to initiate preliminary planning for the ETF decision, the Office of Fusion Energy established the ETF Design Center activity to prepare the design of the ETF. This section describes the status of this design

  5. Experimental-demonstrative system for energy conversion using hydrogen fuel cell - preliminary results

    International Nuclear Information System (INIS)

    Stoenescu, D.; Stefanescu, I.; Patularu, I.; Culcer, M.; Lazar, R.E.; Carcadea, E.; Mirica, D. . E-mail address of corresponding author: daniela@icsi.ro; Stoenescu, D.)

    2005-01-01

    It is well known that hydrogen is the most promising solution of future energy, both for long and medium term strategies. Hydrogen can be produced using many primary sources (natural gas, methane, biomass, etc.), it can be burned or chemically react having a high yield of energy conversion, being a non-polluted fuel. This paper presents the preliminary results obtained by ICSI Rm. Valcea in an experimental-demonstrative conversion energy system made by a sequence of hydrogen purification units and a CO removing reactors until a CO level lower than 10ppm, that finally feeds a hydrogen fuel stack. (author)

  6. Head teacher professional networks in Italy: preliminary results of a national survey

    Directory of Open Access Journals (Sweden)

    Maurissens Isabel de

    2016-06-01

    Full Text Available In this article, we present the preliminary results of a national survey conducted by INDIRE on head teachers communities and professional networks. About one-fourth of the total population of Italian public school leaders participated in the survey. One of the main intents of this research is to contribute to understanding of the phenomenon of professional networks frequented by school leaders and to pave the way for a further reflection on how to use such networks for head teachers’ training so as to support their daily professional practice conducted too often in isolation.

  7. Design and preliminary results of a fuel flexible industrial gas turbine combustor

    Science.gov (United States)

    Novick, A. S.; Troth, D. L.; Yacobucci, H. G.

    1981-01-01

    The design characteristics are presented of a fuel tolerant variable geometry staged air combustor using regenerative/convective cooling. The rich/quench/lean variable geometry combustor is designed to achieve low NO(x) emission from fuels containing fuel bound nitrogen. The physical size of the combustor was calculated for a can-annular combustion system with associated operating conditions for the Allison 570-K engine. Preliminary test results indicate that the concept has the potential to meet emission requirements at maximum continuous power operation. However, airflow sealing and improved fuel/air mixing are necessary to meet Department of Energy program goals.

  8. Analysis of rainfall-induced shallow landslides in Jamne and Jaszcze stream valleys (Polish Carpathians – preliminary results

    Directory of Open Access Journals (Sweden)

    Zydroń Tymoteusz

    2016-03-01

    Full Text Available Analysis of rainfall-induced shallow landslides in Jamne and Jaszcze stream valleys (Polish Carpathians - preliminary results. Preliminary shallow landslide susceptibility mapping of the Jamne and Jaszcze stream valleys, located in the Polish Flysch Carpathians, is presented in the paper. For the purpose of mapping, there were used SINMAP and Iverson’s models integrating infiltration and slope stability calculations. The calibration of the used models parameters, obtained from limited field and laboratory tests, was performed using data from 8-9 July 1997, when as a consequence of a very intense rainfall, 94 shallow landslides were observed on meadows and arable lands. A comparison of the slope stability calculation results and the localisation of the noticed shallow landslides showed satisfactory agreement between localisation of the observed and computed unstable areas. However, it was concluded that better simulation results were obtained using Iverson’s model.

  9. 78 FR 2363 - Certain Cased Pencils From the People's Republic of China: Preliminary Results of Antidumping...

    Science.gov (United States)

    2013-01-11

    ... the People's Republic of China: Preliminary Results of Antidumping Duty Administrative Review and... Republic of China (``PRC''). The period of review (``POR'') is December 1, 2010, through November 30, 2011. The review covers one exporter of subject merchandise, Beijing Fila Dixon Stationery Company, Ltd. a...

  10. 78 FR 1834 - Magnesium Metal From the People's Republic of China: Preliminary Results of Antidumping Duty...

    Science.gov (United States)

    2013-01-09

    ... People's Republic of China: Preliminary Results of Antidumping Duty Administrative Review; 2011-2012... on magnesium metal from the People's Republic of China (``PRC''). The period of review (``POR'') is April 1, 2011, through March 31, 2012. This review covers one PRC company, Tianjin Magnesium...

  11. Fracture toughness of irradiated candidate materials for ITER first wall/blanket structures: Preliminary results

    International Nuclear Information System (INIS)

    Alexander, D.J.; Pawel, J.E.; Grossbeck, M.L.; Rowcliffe, A.F.

    1993-01-01

    Candidate materials for first wall/blanket structures in ITER have been irradiated to damage levels of about 3 dpa at temperatures of either 60 or 250 degrees C. Preliminary results have been obtained for several of these materials irradiated at 60 degrees C. The results show that irradiation at this temperature reduces the fracture toughness of austenitic stainless steels, but the toughness remains quite high. The unloading compliance technique developed for the subsize disk compact specimens works quite well, particularly for materials with lower toughness. Specimens of materials with very high toughness deform excessively, and this results in experimental difficulties

  12. Sealing a nuclear waste repository in Columbia river basalt: preliminary results

    International Nuclear Information System (INIS)

    Hodges, F.N.

    1980-01-01

    The long containment time required of repositories for nuclear waste (10 4 to 10 6 years) requires that materials used for repository seals be stable in the geologic environment of the repository and of proven longevity. A list of candidate materials for sealing a repository in Columbia River Basalts has been prepared and refined through laboratory testing. The most feasible techniques for emplacing preferred plug materials have been identified and the resultant plugs have been evaluated on the basis of design functions. Preconceptual designs for tunnel, shaft, and borehole seals consist of multiple zone plugs with each zone fulfilling one or more design functions. Zones of disturbed rock around tunnels and shafts, resulting from excavation and subsequent stress release, are zones of higher permeability and of possible fluid migration. In preliminary designs the disturbed zones are blocked by cut-off collars filled with low permeability materials

  13. Effects of an oxidizing atmosphere in a spent fuel packaging facility

    International Nuclear Information System (INIS)

    Einziger, R.E.

    1991-09-01

    Sufficient oxidation of spent fuel can cause a cladding breach to propagate, resulting in dispersion of fuel particulates and gaseous radionuclides. The literature for spent fuel oxidation in storage and disposal programs was reviewed to evaluate the effect of an oxidizing atmosphere in a preclosure packaging facility on (1) physical condition of the fuel and (2) operations in the facility. Effects such as cladding breach propagation, cladding oxidation, rod dilation, fuel dispersal, 14 C and 85 Kr release, and crud release were evaluated. The impact of these effects, due to oxidation, upon a spent fuel handling facility is generally predicted to be less than the impact of similar effects due to fuel rod breached during handling in an inert-atmosphere facility. Preliminary temperature limits of 240 degree C and 227 degree C for a 2-week or 4-week handling period and 175 degree C for 2-year lag storage would prevent breach propagation and fuel dispersal. Additional data that are needed to support the assumptions in this analysis or complete the database were identified

  14. The VIVITRON and its first results

    International Nuclear Information System (INIS)

    Heusch, B.

    1994-01-01

    A presentation of the new electrostatic accelerator facility called the VIVITRON is given following from the starting period during which the first 16 experiments using EUROGAM have all been successfully completed. Special emphasize is put on new concepts used for the construction of the machine. The first preliminary results from Eurogam experiments are shown together with the other equipment which be used soon and which are mainly the outcome of european collaborations. The perspective for reaching 30 MV maximum voltage is discussed. (authors). 7 refs., 10 figs

  15. Preliminary results on a 4 kJ, 140 k A plasma focus

    International Nuclear Information System (INIS)

    Silva, Patricio; Favre, Mario; Chuaqui, Hernan; Wyndham, Edmund

    1996-01-01

    Preliminary results on the operation of a 4 kJ, 140 kA Plasma Focus device are presented. The machine operates Hydrogen and Hydrogen-Argon mixtures at pressures between 400 m Torr to 10 Torr. Main diagnostics include electric and current measurements, time and space resolved X-ray observations, with limited spectral resolution, and B-dot sensors to monitor the evolution of de current sheet during the run up phase of the discharge. The results indicate that good focus is obtained in the above pressure range. This is inferred from I-dot traces and Pin diode and pin-hole camera X-ray observations. The B-dot loops suggest that a symmetric current sheet is produced. These results show that the machine exhibits a reliable performance, which allows further studies on dense transient plasmas to be developed. (author)

  16. Preliminary results of L2 facility dynamics with RELAP5

    International Nuclear Information System (INIS)

    Mezio, F.; Giménez, M

    2011-01-01

    Conclusions: • We are working in the loop model; • RELAP5 may have some severe problems predicting the phenomena under study: –Some Correlations may be out of applicability domain; –Its numeric scheme is a diffusive one, which tends to artificially stabilize the system. But this wasn’t observed

  17. Introducing handheld computing into a residency program: preliminary results from qualitative and quantitative inquiry.

    OpenAIRE

    Manning, B.; Gadd, C. S.

    2001-01-01

    Although published reports describe specific handheld computer applications in medical training, we know very little yet about how, and how well, handheld computing fits into the spectrum of information resources available for patient care and physician training. This paper reports preliminary quantitative and qualitative results from an evaluation study designed to track changes in computer usage patterns and computer-related attitudes before and after introduction of handheld computing. Pre...

  18. Overview of recent results from the Advanced Toroidal Facility

    International Nuclear Information System (INIS)

    Anabitarte, E.; Hidalgo-Vera, C.; Anderson, F.S.B.; Bell, G.L.; Gandy, R.F.; Bell, J.D.; Charlton, L.A.; Lee, D.K.; Lynch, V.E.; Morris, R.N.; Tolliver, J.S.; Hanson, G.R.; Kwon, M.; Rogers, P.S.; Shaw, P.L.; Wade, M.R.; Kaneko, H.; Sudo, S.; Yamada, H.; Zielinski, J.J.; Murakami, M.; Bigelow, T.S.; Carreras, B.A; Colchin, R.J.; Crume, E.C.; Dominguez, N.; Dunlap, J.L.; Dyer, G.R.; England, A.C.; Fisher, P.W.; Glowienka, J.C.; Goulding, R.H.; Harris, J.H.; Haste, G.R.; Hillis, D.L.; Hiroe, S.; Horton, L.D.; Howe, H.C.; Hutchinson, D.E.; Isler, R.C.; Jernigan, T.C.; Kannan, K.L.; Langley, R.A.; Leboeuf, J.G.; Lue, J.W.; Lyon, J.F.; Ma, C.H.; Menon, M.M.; Mioduszewski, P.K.; Neilson, G.H.; Rasmussen, D.A.; Schwenterly, S.W.; Shaing, K.C.; Shepard, T.D.; Simpkins, J.E.; Stewart, K.A.; Uckan, T.; Wilgen, J.B.; Wing, W.R.

    1989-01-01

    An overview of recent experimental results from the Advanced Toroidal Facility (ATF) is presented. Beam-heated plasmas with bar n e of 10 20 m -3 and τ E * of ∼20 ms have been achieved. Thermal collapse of the plasmas is mitigated by wall conditioning and particle fueling. Confinement time scales positively with density and magnetic field, offsetting deterioration with power. Results fit the LHD scaling and the drift wave turbulence scaling. Bootstrap currents observed during ECH agree with neoclassical theory in magnitude and parameter dependences. Fast reciprocating Langmuir probe measurements show that edge fluctuations in ATF have many similarities to those in the TEXT tokamak. The location of B instabilities has shifted outward in radius, consistent with the broader pressure profiles. 14 refs., 6 figs

  19. Experimental subcritical facility driven by D-D/D-T neutron generator at BARC, India

    Energy Technology Data Exchange (ETDEWEB)

    Sinha, Amar, E-mail: image@barc.gov.in; Roy, Tushar; Kashyap, Yogesh; Ray, Nirmal; Shukla, Mayank; Patel, Tarun; Bajpai, Shefali; Sarkar, P.S.; Bishnoi, Saroj

    2015-05-01

    Highlights: •Experimental subcritical facility BRAHMMA coupled to D-D/D-T neutron generator. •Preliminary results of PNS experiments reported. •Feynman-alpha noise measurements explored with continuous source. -- Abstract: The paper presents design of an experimental subcritical assembly driven by D-D/D-T neutron and preliminary experimental measurements. The system has been developed for investigating the static and dynamic neutronic properties of accelerator driven sub-critical systems. This system is modular in design and it is first in the series of subcritical assemblies being designed. The subcritical core consists of natural uranium fuel with high density polyethylene as moderator and beryllium oxide as reflector. The fuel is embedded in high density polyethylene moderator matrix. Estimated k{sub eff} of the system is ∼0.89. One of the unique features of subcritical core is the use of Beryllium oxide (BeO) as reflector and HDPE as moderator making the assembly a compact modular system. The subcritical core is coupled to Purnima Neutron Generator which works in D-D and D-T mode with both DC and pulsed operation. It has facility for online source strength monitoring using neutron tagging and programmable source modulation. Preliminary experiments have been carried out for spatial flux measurement and reactivity estimation using pulsed neutron source (PNS) techniques with D-D neutrons. Further experiments are being planned to measure the reactivity and other kinetic parameters using noise methods. This facility would also be used for carrying out studies on effect of source importance and measurement of source multiplication factor k{sub s} and external neutron source efficiency φ{sup ∗} in great details. Experiments with D-T neutrons are also underway.

  20. 77 FR 73422 - Seamless Refined Copper Pipe and Tube From Mexico: Preliminary Results of Antidumping Duty...

    Science.gov (United States)

    2012-12-10

    ... Refined Copper Pipe and Tube From Mexico and the People's Republic of China: Antidumping Duty Orders and... and Tube From Mexico: Preliminary Results of Antidumping Duty Administrative Review; 2010-2011 AGENCY... on seamless refined copper pipe and tube from Mexico. The review covers two producers/ exporters of...

  1. 78 FR 6069 - Laminated Woven Sacks From the People's Republic of China: Preliminary Results of Antidumping...

    Science.gov (United States)

    2013-01-29

    ... the People's Republic of China: Preliminary Results of Antidumping Duty Administrative Review; 2011... antidumping duty order on laminated woven sacks (``sacks'') from the People's Republic of China (``PRC''). The period of review (``POR'') is August 1, 2011, through July 31, 2012. The review covers one exporter of...

  2. Preliminary technical data summary No. 3 for the Defense Waste Processing Facility

    International Nuclear Information System (INIS)

    Landon, L.F.

    1980-05-01

    This document presents an update on the best information presently available for the purpose of establishing the basis for the design of a Defense Waste Processing Facility. Objective of this project is to provide a facility to fix the radionuclides present in Savannah River Plant (SRP) high-level liquid waste in a high-integrity form (glass). Flowsheets and material balances reflect the alternate CAB case including the incorporation of low-level supernate in concrete

  3. 2010 Criticality Accident Alarm System Benchmark Experiments At The CEA Valduc SILENE Facility

    International Nuclear Information System (INIS)

    Miller, Thomas Martin; Dunn, Michael E.; Wagner, John C.; McMahan, Kimberly L.; Authier, Nicolas; Jacquet, Xavier; Rousseau, Guillaume; Wolff, Herve; Piot, Jerome; Savanier, Laurence; Baclet, Nathalie; Lee, Yi-kang; Masse, Veronique; Trama, Jean-Christophe; Gagnier, Emmanuel; Naury, Sylvie; Lenain, Richard; Hunter, Richard; Kim, Soon; Dulik, George Michael; Reynolds, Kevin H.

    2011-01-01

    Several experiments were performed at the CEA Valduc SILENE reactor facility, which are intended to be published as evaluated benchmark experiments in the ICSBEP Handbook. These evaluated benchmarks will be useful for the verification and validation of radiation transport codes and evaluated nuclear data, particularly those that are used in the analysis of CAASs. During these experiments SILENE was operated in pulsed mode in order to be representative of a criticality accident, which is rare among shielding benchmarks. Measurements of the neutron flux were made with neutron activation foils and measurements of photon doses were made with TLDs. Also unique to these experiments was the presence of several detectors used in actual CAASs, which allowed for the observation of their behavior during an actual critical pulse. This paper presents the preliminary measurement data currently available from these experiments. Also presented are comparisons of preliminary computational results with Scale and TRIPOLI-4 to the preliminary measurement data.

  4. First results on the GOL-3-II facility

    International Nuclear Information System (INIS)

    Agafonov, M.A.; Arzhannikov, A.V.; Astrelin, V.T.

    1996-01-01

    The first experiments on injection of 8-s, 200-kJ GOL-3-II relativistic electron beam into a plasma are reported. The possibility of a macroscopically stable beam transport through a plasma column 12 m long under the conditions of the developed plasma microturbulence is demonstrated. As a result of collective beam-plasma interaction the effective heating of a dense plasma (∼ 1015 cm -3 ) is observed. According to the data from Thomson scattering the plasma electrons are heated up to the temperature of ∼ 1 keV, the beam energy loss reaching 25-30 %. Putting the facility into operation opens up prospects to carry out the experiments with a dense and hot plasma in a multimirror trap. (J.U.). 4 figs., 10 refs

  5. Uranium and thorium recovery in thorianite ore-preliminary results

    Energy Technology Data Exchange (ETDEWEB)

    Gaiotte, Joao V.M. [Universidade Federal de Alfenas, Pocos de Caldas, MG (Brazil); Villegas, Raul A.S.; Fukuma, Henrique T., E-mail: rvillegas@cnen.gov.br, E-mail: htfukuma@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Pocos de Caldas, MG (Brazil). Lab. de Pocos de Caldas

    2011-07-01

    This work presents the preliminary results of the studies aiming to develop a hydrometallurgical process to produce uranium and thorium concentrates from thorianite ore from Amapa State, Brazil. This process comprises two major parts: acid leaching and Th/U recovery using solvent extraction strategies. Thorianite ore has a typical composition of 60 - 70% of thorium, 8 - 10% lead and 7 - 10% uranium. Sulfuric acid leaching operational conditions were defined as follows: acid/ore ratio 7.5 t/t, ore size below 65 mesh (Tyler), 2 hours leaching time and temperature of 100 deg C. Leaching tests results showed that uranium and thorium recovery exceeded 95%, whereas 97% of lead ore content remained in the solid form. Uranium and thorium simultaneous solvent extraction is necessary due to high sulfate concentration in the liquor obtained from leaching, so the Primene JM-T primary anime was used for this extraction step. Aqueous raffinate from extraction containing sulfuric acid was recycled to the leaching step, reducing acid uptake around 60%, to achieve a net sulfuric acid consumption of 3 t/t of ore. Uranium and thorium simultaneous stripping was performed using sodium carbonate solution. In the aqueous stripped it was added sulfuric acid at pH 1.5, followed by a second solvent extraction step using the tertiary amine Alamine 336. The following stripping step was done with a solution of sodium chloride, resulting in a final solution of 23 g L-1 uranium. (author)

  6. Preliminary results from the Chicago air shower array and the Michigan muon array

    International Nuclear Information System (INIS)

    Krimm, H.A.; Cronin, J.W.; Fick, B.E.; Gibbs, K.G.; Mascarenhas, N.C.; McKay, T.A.; Mueller, D.; Newport, B.J.; Ong, R.A.; Rosenberg, L.J.; Wiedenbeck, M.E.; Green, K.D.; Matthews, J.; Nitz, D.; Sinclair, D.; van der Velde, J.C.

    1991-01-01

    The Chicago Air Shower Array (CASA) is a large area surface array designed to detect extensive air showers (EAS) produced by primaries with energy ∼100 TeV. It operates in coincidence with the underground Michigan Muon Array (MIA). Preliminary results are presented from a search for steady emission and daily emission from three astrophysical sources: Cygnus X-3, Hercules X-1, and the Crab nebula and pulsar. There is no evidence for a significant signal from any of these sources in the 1989 data

  7. Thermoluminescent dosemeters characterization for patient dosimetry in diagnostic radiology preliminary results

    International Nuclear Information System (INIS)

    Castro, William J.; Squair, Peterson L.; Gonzaga, Natalia B.; Nogueira, Maria S.; Silva, Teogenes A. da

    2009-01-01

    The determination of the metrological characteristics of thermoluminescent (TL) dosimeters plays an important role in dosimetry of patients submitted to x-ray examinations for diagnostic purpose. Entrance surface doses can be measured with TL dosimeters to verify the compliance with the diagnostic reference levels. Organ doses can be estimated through TL measurements in an anthropomorphic phantom which it allows the radiation risk assessment. In this work, LiF:Mg,Ti (TLD-100) rod and chip thermoluminescent dosimeters were characterized considering their use for patient dosimetry in computerized tomography and mammography. Preliminary results showed that TL dosimeters have a response reproducibility of 7.8% and 4.8% and homogeneity of 18.4% and 6.5% for rod and chip shapes, respectively. (author)

  8. Evaluation of syngas production unit cost of bio-gasification facility using regression analysis techniques

    Energy Technology Data Exchange (ETDEWEB)

    Deng, Yangyang; Parajuli, Prem B.

    2011-08-10

    Evaluation of economic feasibility of a bio-gasification facility needs understanding of its unit cost under different production capacities. The objective of this study was to evaluate the unit cost of syngas production at capacities from 60 through 1800Nm 3/h using an economic model with three regression analysis techniques (simple regression, reciprocal regression, and log-log regression). The preliminary result of this study showed that reciprocal regression analysis technique had the best fit curve between per unit cost and production capacity, with sum of error squares (SES) lower than 0.001 and coefficient of determination of (R 2) 0.996. The regression analysis techniques determined the minimum unit cost of syngas production for micro-scale bio-gasification facilities of $0.052/Nm 3, under the capacity of 2,880 Nm 3/h. The results of this study suggest that to reduce cost, facilities should run at a high production capacity. In addition, the contribution of this technique could be the new categorical criterion to evaluate micro-scale bio-gasification facility from the perspective of economic analysis.

  9. Preliminary Analysis of Rapid Condensation Experiment with MARS-KS Code

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Jae Ho; Jun, Hwang Yong; Jeong, Hae Yong [Sejong University, Seoul (Korea, Republic of)

    2016-05-15

    In the present study, the rapid condensation experiment performed in MANOTEA facility is analyzed with the MARS-KS code. It is known that there exists some limitation with a system code to predict this kind of a very active condensation due to direct mixing of cold injection flow and steam. Through the analysis we investigated the applicability of MARS-KS code for the design of various passive safety systems in the future. The configuration of the experimental facility MANOTEA, which has been constructed at the University of Maryland - United States Naval Academy, is described and the modeling approach using the MARS-KS code is also provided. The preliminary result shows that the MARS-KS predicts the general trend of pressure and temperature in the condensing part correctly. However, it is also found that there exist some limitations in the simulation such as an unexpected pressure peak or a sudden temperature change.

  10. Preliminary engineering specifications for a test demonstration multilayer protective barrier cover system

    International Nuclear Information System (INIS)

    Phillips, S.J.; Gilbert, T.W.; Adams, M.R.

    1985-03-01

    This report presents preliminary engineering specifications for a test protective barrier cover system and support radiohydrology facility to be constructed at the Hanford Protective Barrier Test Facility (PBTF). Construction of this test barrier and related radiohydrology facility is part of a continuing effort to provide construction experience and performance evaluation of alternative barrier designs used for long-term isolation of disposed radioactive waste materials. Design specifications given in this report are tentative, based on interim engineering and computer simulation design efforts. Final definitive design specifications and engineering prints will be produced in FY 1986. 6 refs., 10 figs., 1 tab

  11. Preliminary hazard classification for Building 107-N

    International Nuclear Information System (INIS)

    Kloster, G.L.; Smith, R.L.

    1997-06-01

    Deactivation activities are planned for Building 107-N (Basin Recirculation Building). This document establishes the preliminary hazard classification (PHC) for the 100-N Area facility segment that includes this building.To establish the PHC, the inventories of radioactive and nonradioactive hazardous materials present within Building 107-N are identified and then compared to the corresponding threshold quantity values in DOE (1992) and reportable quantity values in 40 CFR 302.4. In this evaluation, no credit is taken for the form, location, and dispersibility of the materials; for their interaction with available energy sources; or for safety features that could prevent or mitigate a radioactive release. The result of this effort concluded that the PHC for Building 107-N is Nuclear Category 3

  12. Preliminary results on epidemiology of Coconut Lethal Yellowing in Ghana

    Directory of Open Access Journals (Sweden)

    Bonnot François

    2009-03-01

    Full Text Available Epidemiological studies are of major importance in understanding the determinants of plant diseases in order to control the risks of their spreading. A research programme on the epidemiology of coconut lethal yellowing, or Cape Saint Paul Wilt Disease (CSPWD, in Ghana was launched in March 2007. The objective was to characterize the distribution and spread of the disease in space and time at various scales, and their relation with the environment. This article presents the general strategy used to evaluate the incidence of CSPWD along with the environmental, ecological and agronomical variables at regional level. A survey was undertaken on 1,166 plots of Coconut Sector Development Project (CSDP planted with Malayan Yellow Dwarf (MYD × Vanuatu Tall (VTT hybrids in Western Region and Central Region. Preliminary results on the distribution of CSPWD and outside variables at regional scale, along with their relations, are given.

  13. Disposal facility data for the interim performance

    International Nuclear Information System (INIS)

    Eiholzer, C.R.

    1995-01-01

    The purpose of this report is to identify and provide information on the waste package and disposal facility concepts to be used for the low-level waste tank interim performance assessment. Current concepts for the low-level waste form, canister, and the disposal facility will be used for the interim performance assessment. The concept for the waste form consists of vitrified glass cullet in a sulfur polymer cement matrix material. The waste form will be contained in a 2 x 2 x 8 meter carbon steel container. Two disposal facility concepts will be used for the interim performance assessment. These facility concepts are based on a preliminary disposal facility concept developed for estimating costs for a disposal options configuration study. These disposal concepts are based on vault type structures. None of the concepts given in this report have been approved by a Tank Waste Remediation Systems (TWRS) decision board. These concepts will only be used in th interim performance assessment. Future performance assessments will be based on approved designs

  14. Initial tank calibration at NUCEF critical facility. 1. Measurement procedure and its result

    International Nuclear Information System (INIS)

    Yanagisawa, Hiroshi; Mineo, Hideaki; Tonoike, Kotaro; Takeshita, Isao; Hoshi, Katsuya; Hagiwara, Hiroyuki.

    1994-07-01

    Initial tank calibrations were carried out prior to hot operation of critical facilities in NUCEF: Nuclear Fuel Cycle Safety Engineering Research Facility, for the purpose of the nuclear material accountancy and control for the facility. Raw calibration data were collected from single run per one tank by measuring differential pressure with dip-tube systems, weight of calibration liquid (demineralized water) poured into the tank, temperature in the tank and so on, without operation of tank ventilation system. Volume and level data were obtained by applying density and buoyancy corrections to the raw data. As a result, the evaluated measurement errors of volume and level were small enough, e.g. within 0.2 lit. and 1.0 mm, respectively, for Pu accountancy tanks. This paper summarizes the above-mentioned measurement procedures, collected data, data correction procedures and evaluated measurement errors. (author)

  15. 78 FR 13321 - Silicon Metal From the People's Republic of China: Preliminary Results of Antidumping Duty...

    Science.gov (United States)

    2013-02-27

    ... People's Republic of China: Preliminary Results of Antidumping Duty Administrative Review; 2011-2012... administrative review of the antidumping duty order on silicon metal from the People's Republic of China (``PRC'') for the period of review (``POR'') June 1, 2011, through May 31, 2012. This review covers one PRC...

  16. Tellurium in active volcanic environments: Preliminary results

    Science.gov (United States)

    Milazzo, Silvia; Calabrese, Sergio; D'Alessandro, Walter; Brusca, Lorenzo; Bellomo, Sergio; Parello, Francesco

    2014-05-01

    Tellurium is a toxic metalloid and, according to the Goldschmidt classification, a chalcophile element. In the last years its commercial importance has considerably increased because of its wide use in solar cells, thermoelectric and electronic devices of the last generation. Despite such large use, scientific knowledge about volcanogenic tellurium is very poor. Few previous authors report result of tellurium concentrations in volcanic plume, among with other trace metals. They recognize this element as volatile, concluding that volcanic gases and sulfur deposits are usually enriched with tellurium. Here, we present some results on tellurium concentrations in volcanic emissions (plume, fumaroles, ash leachates) and in environmental matrices (soils and plants) affected by volcanic emissions and/or deposition. Samples were collected at Etna and Vulcano (Italy), Turrialba (Costa Rica), Miyakejima, Aso, Asama (Japan), Mutnovsky (Kamchatka) at the crater rims by using common filtration techniques for aerosols (polytetrafluoroethylene filters). Filters were both eluted with Millipore water and acid microwave digested, and analyzed by inductively coupled plasma mass spectrometry (ICP-MS). Volcanic ashes emitted during explosive events on Etna and Copahue (Argentina) were analyzed for tellurium bulk composition and after leaching experiments to evaluate the soluble fraction of tellurium. Soils and leaves of vegetation were also sampled close to active volcanic vents (Etna, Vulcano, Nisyros, Nyiragongo, Turrialba, Gorely and Masaya) and investigated for tellurium contents. Preliminary results showed very high enrichments of tellurium in volcanic emissions comparing with other volatile elements like mercury, arsenic, thallium and bismuth. This suggests a primary transport in the volatile phase, probably in gaseous form (as also suggested by recent studies) and/or as soluble salts (halides and/or sulfates) adsorbed on the surface of particulate particles and ashes. First

  17. Preliminary radiological assessments of low-level waste repositories

    International Nuclear Information System (INIS)

    Nancarrow, D.J.; Sumerling, T.J.; Ashton, J.

    1988-06-01

    Preliminary assessments of the post-closure radiological impact from the disposal of low-level radioactive wastes in shallow engineered facilities at four sites are presented. This provides a framework to practice and refine a methodology that could be used, on behalf of the Department, for independent assessment of any similar proposal from Nirex. Information and methodological improvements that would be required are identified. (author)

  18. First results of laser welding of neutron irradiated stainless steel

    International Nuclear Information System (INIS)

    Osch, E.V. van; Hulst, D.S. d'; Laan, J.G. van der.

    1994-10-01

    First results of experimental investigations on the laser reweldability of neutron irradiated material are reported. These experiments include the manufacture of 'heterogeneous' joints, which means joining of irradiated stainless steel of type AISI 316L-SPH to 'fresh' unirradiated material. The newly developed laser welding facility in the ECN Hot Cell Laboratory and experimental procedures are described. Visual inspections of welded joints are reported as well as results of electron microscopy and preliminary metallographic examinations. (orig.)

  19. Preliminary Results of Autotuning GEMM Kernels for the NVIDIA Kepler Architecture- GeForce GTX 680

    Energy Technology Data Exchange (ETDEWEB)

    Kurzak, Jakub [Univ. of Tennessee, Knoxville, TN (United States); Luszczek, Pitor [Univ. of Tennessee, Knoxville, TN (United States); Tomov, Stanimire [Univ. of Tennessee, Knoxville, TN (United States); Dongarra, Jack [Univ. of Tennessee, Knoxville, TN (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Manchester (United Kingdom)

    2012-04-01

    Kepler is the newest GPU architecture from NVIDIA, and the GTX 680 is the first commercially available graphics card based on that architecture. Matrix multiplication is a canonical computational kernel, and often the main target of initial optimization efforts for a new chip. This article presents preliminary results of automatically tuning matrix multiplication kernels for the Kepler architecture using the GTX 680 card.

  20. Results of measurements of particulate matter concentrations inside a pig fattening facility

    Directory of Open Access Journals (Sweden)

    Ulens, T.

    2016-01-01

    Full Text Available Description of the subject. This research note discusses the results of measurements of particulate matter concentrations inside a pig fattening facility. Objectives. The objectives of the present study were to investigate the correlations between the different size fractions of indoor particulate matter (PM inside a pig fattening facility and to investigate the evolution of particle size distribution (PSD through a fattening period and between two housing systems and two cleaning protocols. Method. Data from two consecutive fattening periods in a commercial pig barn were used. Results. Very high correlations were found between PM10 and PM2.5 indoor concentrations. Depending on the measuring instrument, high or low correlations were found between PM1 and PM10 or PM2.5 indoor concentrations. No differences in PSD could be found between the two housing systems or the two cleaning protocols. Conclusions. The results from the present study showed high correlations between the indoor concentrations of PM10 and PM2.5. In the present study, no differences in PSD were found.

  1. Overview of recent results from the Advanced Toroidal Facility

    International Nuclear Information System (INIS)

    Murakami, M.; Anabitarte, E.; Anderson, F.S.B.; Bell, G.L.; Bell, J.D.; Bigelow, T.S.; Carreras, B.A.; Charlton, L.A.; Clark, T.L.; Colchin, R.J.; Crume, E.C. Jr.; Dominguez, N.; Dunlap, J.L.; Dyer, G.R.; England, A.C.; Fisher, P.W.; Gandy, R.F.; Glowienka, J.C.; Goulding, R.H.; Hanson, G.R.; Harris, J.H.; Haste, G.R.; Hidalgo-Vera, C.; Hillis, D.L.; Hiroe, S.; Horton, L.D.; Howe, H.C.; Hutchinson, D.E.; Isler, R.C.; Jernigan, T.C.; Kannan, K.L.; Kaneko, H.; Kwon, M.; Langley, R.A.; Leboeuf, J.N.; Lee, D.K.; Lue, J.W.; Lynch, V.E.; Lyon, J.F.; Ma, C.H.; Menon, M.M.; Mioduszewski, P.K.; Morris, R.N.; Neilson, G.H.; Qualls, A.L.; Rasmussen, D.A.; Ritz, C.P.; Rogers, P.S.; Schwenterly, S.W.; Shaing, K.C.; Shaw, P.L.; Shepard, T.D.; Simpkins, J.E.; Stewart, K.A.; Sudo, S.; Thomas, C.E.; Tolliver, J.S.; Uckan, T.; Wade, M.R.; Wilgen, J.B.; Wing, W.R.; Yamada, H.; Zielinski, J.J.

    1990-02-01

    An overview of recent experimental results from the Advanced Toroidal Facility (ATF) is presented. Beam-heated plasmas with bar n e of 10 20 m -3 and τ E * of ∼ 20 ms have been achieved. Thermal collapse of the plasmas is mitigated by wall conditioning and particle fueling. Confinement time scales positively with density and magnetic field, offsetting deterioration with power. Results fit the Large Helical Device (LHD) scaling and the drift wave turbulence scaling. Bootstrap currents observed during electron cyclotron heating agree with neoclassical theory in magnitude and parameter dependences. Fast reciprocating Langmuir probe measurements show that edge fluctuations in ATF have many similarities to those in the Texas Experimental Tokamak (TEXT). The location of B instabilities has shifted outward in radius, consistent with the broader pressure profiles. 14 refs., 6 figs

  2. Development of a distress inventory for cancer: preliminary results.

    Directory of Open Access Journals (Sweden)

    Thomas B

    2002-01-01

    Full Text Available CONTEXT: Advances in cancer treatment have led to cure and prolongation of patients′ lives; however associated psychosocial problems, including distress, can detrimentally affect patients′ compliance with treatment and ultimately, their outcome. Symptom distress has been well addressed in many studies; however, psychological distress has only been quantified by using depression or anxiety scales/checklists or quality of life scales containing a distress sub scale/component or by the use of scales that are not psychological distress-specific. AIMS: The present study is an attempt to construct a psychological distress inventory for specific use with cancer patients. SETTINGS AND DESIGN: The standardisation sample consisted of 63 randomly selected patients with head and neck cancer who had undergone/ were undergoing curative treatment at the Regional Cancer Centre, Trivandrum. PATIENTS AND METHODS: The Distress Inventory for Cancer contained 57 positively and negatively toned items. An item analysis was conducted, followed by a factor analysis, thereby identifying the domains influencing distress. RESULTS: The final questionnaire contained 26 items subdivided into four domains viz. the personal, spiritual, physical, and the family domains, with each domain providing a sub score. The reliability coefficient (Cronbach′s alpha of the scale was found to be 0.85. CONCLUSIONS: These are the preliminary results of an ongoing study on global distress and tool development process. Reported here is the first step towards development of such tool.

  3. Stokes polarimetry probe for skin lesion evaluation: preliminary results

    Science.gov (United States)

    Louie, Daniel C.; Tchvialeva, Lioudmilla; Kalia, Sunil; Lui, Harvey; Lee, Tim K.

    2018-02-01

    This paper reports on the design of a prototype in-vivo Stokes polarimetry probe for skin lesion evaluation, and preliminary results from skin phantom and clinical trials of this device. The probe releases a single millisecond-long pulse from a laser diode with either linear or circular polarization. It then captures the resulting backscattered far-field polarization speckle and calculates the Stokes parameters. This probe was designed with three novel innovations in mind. First, the Stokes vector is captured quickly, using low-cost components without the use of moving parts. Second, a compact collimated laser diode was used as the light source. Third, the device and detector geometry were designed to produce and capture a uniform speckle field. In the first clinical trial of this device, measurements were taken from a variety of skin lesions, both cancerous and benign. The Stokes vector was measured and used to calculate the degree of polarization (DOP), the azimuth angle, and the ellipticity angle of the polarization ellipse for two input light polarizations. Among other findings, the DOP for circular polarized input light was consistently lower than the DOP for linear polarized input light. These findings indicate the potential for a fast and low-cost in-vivo skin cancer screening tool, and encourages the continuing development of this probe's techniques.

  4. Preliminary analysis of West Valley Waste Removal System equipment development and mock demonstration facilities

    International Nuclear Information System (INIS)

    Janicek, G.P.

    1981-06-01

    This report defines seven areas requiring further investigation to develop and demonstrate a safe and viable West Valley Waste Removal System. These areas of endeavor are discussed in terms of their minimum facility requirements. It is concluded that utilizing separated specific facilities at different points in time is of a greater advantage than an exact duplication of the West Valley tanks. Savannah River Plant's full-scale, full-circle and half-circle tanks, and their twelfth scale model tank would all be useful to varying degrees but would require modifications. Hanford's proposed full-size mock tank would be useful, but is not seriously considered because its construction may not coincide with West Valley needs. Costs of modifying existing facilities and/or constructing new facilities are assessed in terms of their benefit to the equipment development and mock demonstration. Six facilities were identified for further analysis which would benefit development of waste removal equipment

  5. Preliminary results from the U.S. participation in the 2000 Beam Park Experiment

    Science.gov (United States)

    Stansbery, Gene

    2001-10-01

    The United States participated in the 2000 Beam Park Experiment (BPE) conducted in late October, 2000 under the auspices of the Inter-Agency Space Debris Coordination Committee (IADC). The U.S. participated using several sensors which have participated in previous campaigns: Haystack, TRADEX, and COBRA DANE radars, and the Liquid Mirror Telescope. New to the BPE experiments this time are the GBR-P radar located at Kwajalein Atoll and the Haystack Auxiliary (HAX) radar located in Massachusetts. This paper will present and discuss preliminary results from each of the participating U.S. sensors.

  6. Preliminary Results on the Experimental Investigation of the Structure Functions of Bound Nucleons

    Energy Technology Data Exchange (ETDEWEB)

    Bodek, Arie [Univ. of Rochester, NY (United States); Thomas Jefferson National Accelerator Facility (TJNAF), Newport News, VA (United States)

    2016-08-01

    We present preliminary results on an experimental study of the nuclear modification of the longitudinal ($\\sigma_L$) and transverse ($\\sigma_T$) structure functions of nucleons bound in nuclear targets. The origin of these modifications (commonly referred as as the EMC effect) is not fully understood. Our measurements of R= $\\sigma_L / \\sigma_T$ for nuclei ($R_A$) and for deuterium ($R_D$) indicate that nuclear modifications of the structure functions of bound nucleons are different for the longitudinal and transverse structure functions, and that contrary to expectation from several theoretical models, $R_A< R_D$.

  7. Preliminary results from a novel CVD diamond detector system for molecular imaging applications

    International Nuclear Information System (INIS)

    Mahon, A.R.

    1996-01-01

    A novel biomolecular imaging system incorporating a Chemical Vapour Deposition diamond detector is in development. The synthetic diamond is used as a UV detector to image nucleic acids in electrophoresis gels. The microstrip diamond detector currently has a spatial resolution of 30 μm. Preliminary results are presented which include: QE measurements of diamond detectors, detector time response, detector UV response and current detection limits of biomolecules in gel. The potential applications of the technology, and its significant advantages in speed and sensitivity over the current systems are discussed

  8. Results of the RAMI analyses performed for the IFMIF accelerator facility in the engineering design phase

    Energy Technology Data Exchange (ETDEWEB)

    Bargalló, Enric, E-mail: enric.bargallo@esss.se [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia (UPC) Barcelona-Tech, Barcelona (Spain); Arroyo, Jose Manuel [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, Madrid (Spain); Abal, Javier; Dies, Javier; De Blas, Alfredo; Tapia, Carlos [Fusion Energy Engineering Laboratory (FEEL), Technical University of Catalonia (UPC) Barcelona-Tech, Barcelona (Spain); Moya, Joaquin; Ibarra, Angel [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, Madrid (Spain)

    2015-10-15

    Highlights: • RAMI methodology used for IFMIF accelerator facility is presented. • Availability analyses and results are shown. • Main accelerator design changes are proposed. • Consequences and conclusions of the RAMI analyses are described. - Abstract: This paper presents a summary of the RAMI (Reliability Availability Maintainability Inspectability) analyses done for the IFMIF (International Fusion Materials Irradiation Facility) Accelerator facility in the Engineering Design Phase. The methodology followed, the analyses performed, the results obtained and the conclusions drawn are described. Moreover, the consequences of the incorporation of the RAMI studies in the IFMIF design are presented and the main outcomes of these analyses are shown.

  9. Results of the RAMI analyses performed for the IFMIF accelerator facility in the engineering design phase

    International Nuclear Information System (INIS)

    Bargalló, Enric; Arroyo, Jose Manuel; Abal, Javier; Dies, Javier; De Blas, Alfredo; Tapia, Carlos; Moya, Joaquin; Ibarra, Angel

    2015-01-01

    Highlights: • RAMI methodology used for IFMIF accelerator facility is presented. • Availability analyses and results are shown. • Main accelerator design changes are proposed. • Consequences and conclusions of the RAMI analyses are described. - Abstract: This paper presents a summary of the RAMI (Reliability Availability Maintainability Inspectability) analyses done for the IFMIF (International Fusion Materials Irradiation Facility) Accelerator facility in the Engineering Design Phase. The methodology followed, the analyses performed, the results obtained and the conclusions drawn are described. Moreover, the consequences of the incorporation of the RAMI studies in the IFMIF design are presented and the main outcomes of these analyses are shown.

  10. Encapsulation plant preliminary design, phase 2. Repository connected facility

    International Nuclear Information System (INIS)

    Kukkola, T.

    2006-12-01

    The disposal facility of the spent nuclear fuel will be located in Olkiluoto. The encapsulation plant is a part of the disposal facility. In this report, an independent encapsulation plant is located above the underground repository. In the encapsulation plant, the spent fuel is received and treated for disposal. In the fuel handling cell, the spent fuel assemblies are unloaded from the spent fuel transport casks and loaded into the disposal canisters. The gas atmosphere of the disposal canister is changed, the bolted inner canister lid is closed, and the electron beam welding method is used to close the lid of the outer copper canister. The disposal canisters are cleaned and transferred into the buffer store after the machining and inspection of the copper lid welds. From the buffer store, the disposal canisters are transferred into the repository spaces by help of the canister lift. All needed stages of operation are to be performed safely without any activity releases or remarkable personnel doses. The bentonite block interim storage is associated with the encapsulation plant. The bentonite blocks are made from bentonite powder. The bentonite blocks are used as buffer material around the disposal canister in the deposition hole. The average production rate of the encapsulation plant is 40 canisters per year. The nominal maximum production capacity is 100 canisters per year in one shift operation. (orig.)

  11. Results of Cesar II critical facility with low enriched fuel balls

    Energy Technology Data Exchange (ETDEWEB)

    Langlet, G; Guerange, J; Laponche, B; Morier, F; Neef, R D; Bock, H J; Kring, F J; Scherer, W

    1972-06-15

    The Cesar facility has been transformed to load in its center a pebble bed fuel. This new Cesar assembly is called Cesar II. The program for the measurements with HTR type fuel balls is managed under a cooperation between physicists of CEA/CADARACHE and KFA/JUELICH. A description of the measuring zones of Cesar II and of the experimental results is given.

  12. Needs of Advanced Safeguards Technologies for Future Nuclear Fuel Cycle (FNFC) Facilities and a Trial Application of SBD Concept to Facility Design of a Hypothetical FNFC Facility

    International Nuclear Information System (INIS)

    Seya, M.; Hajima, R.; Nishimori, N.; Hayakawa, T.; Kikuzawa, N.; Shizuma, T.; Fujiwara, M.

    2010-01-01

    Some of future nuclear fuel cycle (FNFC) facilities are supposed to have the characteristic features of very large throughput of plutonium, low decontamination reprocessing (no purification process; existence of certain amount of fission products (FP) in all process material), full minor actinides (MA) recycle, and treatment of MOX with FP and MA in fuel fabrication. In addition, the following international safeguards requirements have to be taken into account for safeguards approaches of the FNFC facilities. -Application of integrated safeguards (IS) approach; -Remote (unattended) verification; - 'Safeguards by Design' (SBD) concept. These features and requirements compel us to develop advanced technologies, which are not emerged yet. In order to realize the SBD, facility designers have to know important parts of design information on advanced safeguards systems before starting the facility design. The SBD concept requires not only early start of R and D of advanced safeguards technologies (before starting preliminary design of the facility) but also interaction steps between researchers working on safeguards systems and nuclear facility designers. The interaction steps are follows. Step-1; researchers show images of advanced safeguards systems to facility designers based on their research. Step-2; facility designers take important design information on safeguards systems into process systems of demonstration (or test) facility. Step-3; demonstration and improvement of both systems based on the conceptual design. Step-4; Construction of a FNFC facility with the advanced safeguards systems We present a trial application of the SBD concept to a hypothetical FNFC facility with an advanced hybrid K-edge densitometer and a Pu NDA system for spent nuclear fuel assembly using laser Compton scattering (LCS) X-rays and γ-rays and other advanced safeguards systems. (author)

  13. ROUND-ROBIN ATOM-PROBE EXPERIMENT : PRELIMINARY RESULTS IN JAPAN

    OpenAIRE

    Nakamura , S.

    1986-01-01

    A round-robin experiment were to be carried out by 6 laboratories in Japan (Nishikawa ; Tokyo Inst. Tech., Sakurai and Igata ; Univ. of Tokyo, Ishikawa ; Hitachi, Tanino ; Nippon Steel Corp. and Nakamura ; Osaka Univ.) under the normal operating condition (T < l00 °K,. pulse fraction ~ 15% ~, P < 10-9 torr). Fe-Cr-Al and W-25%Re alloys, which are divided from a single wire were chosen as the specimen materials. A preliminary analysis of the W-Re alloy of the laboratory concerned show the good...

  14. Rough order of magnitude cost estimate for immobilization of 50 MT of plutonium using existing facilities at Hanford: alternative 11B

    International Nuclear Information System (INIS)

    DiSabatino, A.

    1998-01-01

    The purpose of this Cost Estimate Report is to identify preliminary capital and operating costs for a facility to immobilize 50 metric tons (nominal) of plutonium as a ceramic in an existing facility at Hanford, the Fuels and Materials Examination Facility (FMEF)

  15. Recent results from the TwinSol low-energy RIB facility

    Energy Technology Data Exchange (ETDEWEB)

    Becchetti, F.D. [U. Michigan, Ann Arbor, MI 48109 (United States); Kolata, J.J. [U. Notre Dame, Notre Dame, IN 46556 (United States)

    2016-06-01

    We report on some of the recent developments and experimental work done at the twin-solenoid low-energy radioactive-ion-beam (RIB) facility TwinSol installed at the U Notre Dame 10 MV FN tandem accelerator. The TwinSol facility is a joint project of the University of Michigan (UM) and the University of Notre Dame (UND), and includes several U.S. and foreign collaborators. A number of significant experiments including RIB-induced transfer reactions, elastic scattering, resonant scattering, and fusion at energies near and well below the Coulomb barrier have been performed with this facility. Several of these as well as future work and upgrades planned will be described.

  16. Aerial infrared monitoring for nuclear fuel cycle facilities in Ukraine

    International Nuclear Information System (INIS)

    Stankevich, S.A.; Dudar, T.V.; Kovalenko, G.D.; Kartashov, V.V.

    2015-01-01

    The scientific research overall objective is rapid express detection and preliminary identification of pre-accidental conditions at nuclear fuel cycle facilities. We consider development of a miniature unmanned aerial vehicle equipped with high-precision infrared spectroradiometer able to detect remotely internal warming up of hazardous facilities by its thermal infrared radiation. The possibility of remote monitoring using unmanned aerial vehicle is considered at the example of the dry spent fuel storage facility of the Zaporizhzhya Nuclear Power Plant. Infrared remote monitoring is supposed to present additional information on the monitored facilities based on different physical principles rather than those currently in use. Models and specifications towards up-to-date samples of infrared surveying equipment and its small-sized unmanned vehicles are presented in the paper.

  17. Use of the KineSpring system in the treatment of medial knee osteoarthritis: preliminary results.

    Science.gov (United States)

    Madonna, Vincenzo; Condello, Vincenzo; Piovan, Gianluca; Screpis, Daniele; Zorzi, Claudio

    2015-01-01

    the purpose of this study was to analyze our preliminary results obtained with the KineSpring system in patients suffering from medial compartment knee osteoarthritis (OA). between September 2012 and May 2014, 53 patients underwent treatment with the KineSpring system. Patient self-assessment was performed pre-operatively and at 3, 6 and 12 months postoperatively, and included the KOOS, Tegner activity score, Lysholm functional knee score, VAS knee pain score, and IKDC score. Device- and procedure-related adverse events were recorded. mean KOOS subscales, except for the Sport/Recreation subscale at six months, improved over time. Mean WOMAC Pain and Function domains, Lysholm score, IKDC score and VAS knee pain score improved over the follow-up period and were significantly improved at 3, 6 and 12 months postoperatively compared to baseline. Mean Tegner score improved slightly over time. In 5 of the 53 (9.4%) patients re-operation was necessary. In 3 patients the device was removed due to infection (one case) or persistent knee pain (two cases). Surgical arthrolysis was performed in two patients. in our preliminary experience, the KineSpring system gave good short-term clinical results. Level IV, therapeutic case series.

  18. Using VIIRS Day/Night Band to Measure Electricity Supply Reliability: Preliminary Results from Maharashtra, India

    Directory of Open Access Journals (Sweden)

    Michael L. Mann

    2016-08-01

    Full Text Available Unreliable electricity supplies are common in developing countries and impose large socio-economic costs, yet precise information on electricity reliability is typically unavailable. This paper presents preliminary results from a machine-learning approach for using satellite imagery of nighttime lights to develop estimates of electricity reliability for western India at a finer spatial scale. We use data from the Visible Infrared Imaging Radiometer Suite (VIIRS onboard the Suomi National Polar Partnership (SNPP satellite together with newly-available data from networked household voltage meters. Our results point to the possibilities of this approach as well as areas for refinement. With currently available training data, we find a limited ability to detect individual outages identified by household-level measurements of electricity voltage. This is likely due to the relatively small number of individual outages observed in our preliminary data. However, we find that the approach can estimate electricity reliability rates for individual locations fairly well, with the predicted versus actual regression yielding an R2 > 0.5. We also find that, despite the after midnight overpass time of the SNPP satellite, the reliability estimates derived are representative of daytime reliability.

  19. Argonne Fuel Cycle Facility ventilation system -- modeling and results

    International Nuclear Information System (INIS)

    Mohr, D.; Feldman, E.E.; Danielson, W.F.

    1995-01-01

    This paper describes an integrated study of the Argonne-West Fuel Cycle Facility (FCF) interconnected ventilation systems during various operations. Analyses and test results include first a nominal condition reflecting balanced pressures and flows followed by several infrequent and off-normal scenarios. This effort is the first study of the FCF ventilation systems as an integrated network wherein the hydraulic effects of all major air systems have been analyzed and tested. The FCF building consists of many interconnected regions in which nuclear fuel is handled, transported and reprocessed. The ventilation systems comprise a large number of ducts, fans, dampers, and filters which together must provide clean, properly conditioned air to the worker occupied spaces of the facility while preventing the spread of airborne radioactive materials to clean am-as or the atmosphere. This objective is achieved by keeping the FCF building at a partial vacuum in which the contaminated areas are kept at lower pressures than the other worker occupied spaces. The ventilation systems of FCF and the EBR-II reactor are analyzed as an integrated totality, as demonstrated. We then developed the network model shown in Fig. 2 for the TORAC code. The scope of this study was to assess the measured results from the acceptance/flow balancing testing and to predict the effects of power failures, hatch and door openings, single-failure faulted conditions, EBR-II isolation, and other infrequent operations. The studies show that the FCF ventilation systems am very controllable and remain stable following off-normal events. In addition, the FCF ventilation system complex is essentially immune to reverse flows and spread of contamination to clean areas during normal and off-normal operation

  20. Preliminary Experimental Results for Indirect Vector-Control of Induction Motor Drives with Forced Dynamics

    Directory of Open Access Journals (Sweden)

    Jan Vittek

    2003-01-01

    Full Text Available The contribution presents an extension of indirect vector control of electric drives employing induction motors to 'Forced Dynamic Control'. This method of control offers an accurate realisation of dynamic response profiles, which can be selected by the user. The developed system can be integrated into a drive with a shaft position encoder or a shaft sensoriess drive, in which only the stator currents are measured. The applied stator voltages are determined by a computed inverter switching algorithm. Simulation results and preliminary experimental results for indirect vector control of an idle running induction motor indicate good agreement with the theoretical predictions.

  1. Preliminary results of the first paleontologic investigations in Uruguayan Antarctica

    International Nuclear Information System (INIS)

    Perea, D.; Masquelin, E.; Verde, M.; Querequiz, R.

    1998-01-01

    Preliminary results of the first Uruguayan paleontollogic and biostratigraphical investigations in Antartica are presented. The field work was performed in fildes Peninsula, King George Island, near Uruguayan station Base Cientifica Antarctica Artigas.Some fossiliferous outcrops were geologic and paleontologically analyzed, among them Fossil Hills, situated in the center part of the peninsula, in front of Ardley Island, between the chinese and chilean stations.This hill is composed of fossil bearing piroclastic and epiclastic rocks, assigned to the fossil Hill Fm. Vegetal remains(petrified wood and leaf impronts) were observed and collected in this unit and it is remarkable the presence of Nothofagus sp. and invertebrate trace fossils, Cochlichmus isp and Helminthopsis isp.The depositional environment deduced from the fossil association in lacustrine, under a warm and humid climate.In the same deposits, other investigators have collected aquatic and ratite bird trace fossils. Paleontologic evidence is not contradictory with the Eocene age previously proposed for the studied deposits. (author)

  2. Subcritical neutron generator-test facility for nuclear waste transmutation studies

    Energy Technology Data Exchange (ETDEWEB)

    Chuvilo, I.V.; Kolomiets, A.A.; Kozodaev, A.M. [ITEP, Moscow (Russian Federation)] [and others

    1995-10-01

    The development of the optimal design of high power facility for NPP transmutation and for a number of applications can not be carried out without preliminary tests of much cheaper prototypes. It has been proposed to combine in new test facility 36 MeV Linac ISTRA constructed in ITEP, original Be target and subcritical blanket that will be mounted on the place of partly disassembled heavy water ITEP experimental reactor. The basic parameters of Linac, schemes of the target and blanket are described. It will provide the direct experiments on installation which can be considered as prototype for future linac driven high power facilities.

  3. Raman scattering investigation of the water-bridge phenomenon: Some preliminary results

    Directory of Open Access Journals (Sweden)

    Francesco Aliotta

    2010-09-01

    Full Text Available A floating water-bridge is formed if a high-voltage direct current is applied between two beakers filled of chemically pure water. Raman spectra of the OH-stretching region have been obtained at ambient condition of temperature and pressure. These preliminary results seem to indicate that the hydrogen-bond structure is only slightly modified by the presence of the electric field applied to form the floating water-bridge in agreement with recent neutron scattering investigation. In fact, the polarized Raman spectrum of the pure water and of the water-bridge is almost superimposable. We are planning to carry out further spectroscopic analysis, at different thermodynamic conditions, for better understanding the role played by the hydrogen-bond in driving the formation of the floating water-bridge.

  4. 75 FR 78968 - Magnesium Metal From the Russian Federation: Extension of Time Limit for Preliminary Results of...

    Science.gov (United States)

    2010-12-17

    ... DEPARTMENT OF COMMERCE International Trade Administration [A-821-819] Magnesium Metal From the Russian Federation: Extension of Time Limit for Preliminary Results of Antidumping Duty Administrative... administrative review of the antidumping duty order on magnesium metal from the Russian Federation for the period...

  5. 77 FR 11065 - Certain Pasta From Turkey: Extension of Time Limit for the Preliminary Results of the...

    Science.gov (United States)

    2012-02-24

    ... DEPARTMENT OF COMMERCE International Trade Administration [C-489-806] Certain Pasta From Turkey: Extension of Time Limit for the Preliminary Results of the Countervailing Duty Administrative Review AGENCY... initiation of administrative review of the countervailing duty order on certain pasta from Turkey, covering...

  6. 77 FR 15718 - Certain Pasta from Italy: Extension of Time Limit for the Preliminary Results of the...

    Science.gov (United States)

    2012-03-16

    ... DEPARTMENT OF COMMERCE International Trade Administration [C-475-819] Certain Pasta from Italy: Extension of Time Limit for the Preliminary Results of the Countervailing Duty Administrative Review AGENCY... notice of initiation of administrative review of the countervailing duty order on certain pasta from...

  7. 76 FR 6604 - Certain Pasta From Italy: Extension of Time Limit for the Preliminary Results of the...

    Science.gov (United States)

    2011-02-07

    ... DEPARTMENT OF COMMERCE International Trade Administration [C-475-819] Certain Pasta From Italy: Extension of Time Limit for the Preliminary Results of the Countervailing Duty Administrative Review AGENCY... initiation of administrative review of the countervailing duty order on certain pasta from Italy, covering...

  8. 77 FR 17410 - Solid Urea From the Russian Federation: Extension of Time Limit for Preliminary Results of...

    Science.gov (United States)

    2012-03-26

    ... DEPARTMENT OF COMMERCE International Trade Administration [A-821-801] Solid Urea From the Russian Federation: Extension of Time Limit for Preliminary Results of Antidumping Duty Administrative Review AGENCY... Commerce (the Department) initiated an administrative review of the antidumping duty order on solid urea...

  9. 75 FR 19369 - Certain Hot-Rolled Flat-Rolled Carbon Quality Steel Products from Brazil: Preliminary Results of...

    Science.gov (United States)

    2010-04-14

    .... Hot-rolled dual phase steel, phase-hardened, primarily with a ferritic-martensitic microstructure.... See Preliminary Results of Antidumping Duty Administrative Review: Stainless Steel Sheet and Strip in... Antidumping Duty Administrative Review: Stainless Steel Sheet and Strip in Coils From France, 68 FR 69379...

  10. 78 FR 55676 - Certain Frozen Fish Fillets From the Socialist Republic of Vietnam: Preliminary Results of the...

    Science.gov (United States)

    2013-09-11

    ... DEPARTMENT OF COMMERCE International Trade Administration [A-552-801] Certain Frozen Fish Fillets... order on certain frozen fish fillets (``fish fillets'') from the Socialist Republic of Vietnam... preliminary results. \\1\\ See Notice of Antidumping Duty Order: Certain Frozen Fish Fillets From the Socialist...

  11. 78 FR 34340 - Welded Carbon Steel Standard Pipe and Tube Products From Turkey: Preliminary Results of...

    Science.gov (United States)

    2013-06-07

    ... Pipe and Tube Products From Turkey: Preliminary Results of Antidumping Duty Administrative Review; 2011... tube products (welded pipe and tube) from Turkey.\\2\\ The period of review is May 1, 2011, to April 30... A.S. (BMB) had reviewable sales during this period of review. DATES: As of June 7, 2013. FOR FURTHER...

  12. 78 FR 38313 - Kings River Conservation District; Notice of Preliminary Permit Application Accepted for Filing...

    Science.gov (United States)

    2013-06-26

    ...-hours utilizing one Kaplan-bulb turbine. A preliminary design of the facilities and selection of the turbine and generator would be performed during the feasibility study. Applicant Contact: Mr. David Orth...

  13. Preliminary results from MBE-4: A four beam induction linac for heavy ion fusion research

    International Nuclear Information System (INIS)

    Fessenden, T.J.; Judd, D.L.; Keefe, D.; Kim, C.; Laslett, L.J.; Smith, L.; Warwick, A.I.; Warwick, P.b.A.I.

    1986-01-01

    Preliminary results are presented from a scaled experimental multiple beam induction linac. This experiment is part of a program of accelerator research for heavy ion fusion. It is shown that multiple beams can be accelerated without significant mutual interaction. Measurements of the longitudinal dynamics of a current-amplifying induction linac are presented and compared to calculations. Coupling of transverse and longitudinal dynamics is discussed

  14. Preliminary results from MBE-4: a four beam induction linac for heavy ion fusion research

    International Nuclear Information System (INIS)

    Fessenden, T.J.; Judd, D.L.; Keefe, D.; Kim, C.; Laslett, L.J.; Smith, L.; Warwick, A.I.

    1986-05-01

    Preliminary results are presented from a scaled experimental multiple beam induction linac. This experiment is part of a program of accelerator research for heavy ion fusion. It is shown that multiple beams can be accelerated without significant mutual interaction. Measurements of the longitudinal dynamics of a current-amplifying induction linac are presented and compared to calculations. Coupling of transverse and longitudinal dynamics is discussed

  15. Breast tomography with synchrotron radiation: preliminary results

    International Nuclear Information System (INIS)

    Pani, Silvia; Longo, Renata; Dreossi, Diego; Montanari, Francesco; Olivo, Alessandro; Arfelli, Fulvia; Bergamaschi, Anna; Poropat, Paolo; Rigon, Luigi; Zanconati, Fabrizio; Palma, Ludovico Dalla; Castelli, Edoardo

    2004-01-01

    A system for in vivo breast imaging with monochromatic x-rays has been designed and built at the synchrotron radiation facility Elettra in Trieste (Italy) and will be operational in 2004. The system design involves the possibility of performing both planar mammography and breast tomography. In the present work, the first results obtained with a test set-up for breast tomography are shown and discussed. Tomographic images of in vitro breasts were acquired using monochromatic x-ray beams in the energy range 20-28 keV and a linear array silicon pixel detector. Tomograms were reconstructed using standard filtered backprojection algorithms; the effect of different filters was evaluated. The attenuation coefficients of fibroglandular and adipose tissue were measured, and a quantitative comparison of images acquired at different energies was performed by calculating the differential signal-to-noise ratio of fibroglandular details in adipose tissue. All images required a dose comparable to the dose delivered in clinical, conventional mammography and showed a high resolution of the breast structures without the overlapping effects that limit the visibility of the structures in 2D mammography. A quantitative evaluation of the images proves that the image quality at a given dose increases in the considered energy range and for the considered breast sizes

  16. Preliminary results about Electrodeposition of Cobalt at laboratory level

    International Nuclear Information System (INIS)

    Cornejo, N.

    1992-01-01

    As of an organic compound, an extraction and Cobalt electrodeposition method had been developed as a part of fabrication aim of a sealed radioactive source with objective to the construction of density meter prototype. It was performed preliminary test of electrodeposition in the laboratory level in a simple cell. The used electrolyte had been a sulphate solution obtained by extraction of an organic solution. It is obtained a Co film by electrodeposition at 55 o C temperature and with an approximately Co concentration in 70 g/lt. (Author) 3 refs., 1 fig., 1 tab

  17. Most significant preliminary results of the probabilistic safety analysis on the Juragua nuclear power plant

    International Nuclear Information System (INIS)

    Perdomo, Manuel

    1995-01-01

    Since 1990 the Group for PSA Development and Applications (GDA/APS) is working on the Level-1 PSA for the Juragua-1 NPP, as a part of an IAEA Technical Assistance Project. The main objective of this study, which is still under way, is to assess, in a preliminary way, the Reactor design safety to find its potential 'weak points' at the construction stage, using a eneric data base. At the same time, the study allows the PSA team to familiarize with the plant design and analysis techniques for the future operational PSA of the plant. This paper presents the most significant preliminary results of the study, which reveal some advantages of the safety characteristics of the plant design in comparison with the homologous VVER-440 reactors and some areas, where including slight modifications would improve the plant safety, considering the level of detail at which the study is carried out. (author). 13 refs, 1 fig, 2 tabs

  18. Gas delivery system and beamline studies for the test beam facility of the Collider Detector at Fermilab

    International Nuclear Information System (INIS)

    Franke, H.G. III.

    1987-12-01

    A fixed-target test beam facility has been designed and constructed at the Meson Test (MT) site to support studies of components of the Collider Detector at Fermi National Accelerator Laboratory (CDF). I assisted in the design and constuction of the test beam facility gas delivery system, and I conducted the initial studies to document the ability of the MT beamline to meet the needs of CDF. Analysis of the preliminary performance data on MT beamline components and beam tunes at required particle energies is presented. Preliminary studies show that the MT beamline has the necessary flexibility to satisfy most CDF requirements now

  19. Environmental Survey preliminary report, Sandia National Laboratories, Livermore, California

    International Nuclear Information System (INIS)

    1988-01-01

    This report contains the preliminary findings based on the first phase of an Environmental Survey at the Department of Energy (DOE) Sandia National Laboratories Livermore (SNLL), located at Livermore, California. The Survey is being conducted by DOE's Office of Environment, Safety and Health. The SNLL Survey is a portion of the larger, comprehensive DOE Environmental Survey encompassing all major operating facilities of DOE. The DOE Environmental Survey is one of a series of initiatives announced on September 18, 1985, by Secretary of Energy, John S. Herrington, to strengthen the environmental, safety, and health programs and activities within DOE. The purpose of the Environmental Survey is to identify, via a ''no fault'' baseline Survey of all the Department's major operating facilities, environmental problems and areas of environmental risk. The identified problem areas will be prioritized on a Department-wide basis in order of importance in 1989. The findings in this report are subject to modification based on the results from the Sampling and Analysis Phase of the Survey. The findings are also subject to modification based on comments from the Albuquerque Operations Office concerning the technical accuracy of the findings. The modified preliminary findings and any other appropriate changes will be incorporated into an Interim Report. The Interim Report will serve as the site-specific source for environmental information generated by the Survey, and ultimately as the primary source of information for the DOE-wide prioritization of environmental problems in the Survey Summary Report. 43 refs., 21 figs., 24 tabs

  20. Environmental Survey preliminary report, Sandia National Laboratories, Livermore, California

    Energy Technology Data Exchange (ETDEWEB)

    1988-01-01

    This report contains the preliminary findings based on the first phase of an Environmental Survey at the Department of Energy (DOE) Sandia National Laboratories Livermore (SNLL), located at Livermore, California. The Survey is being conducted by DOE's Office of Environment, Safety and Health. The SNLL Survey is a portion of the larger, comprehensive DOE Environmental Survey encompassing all major operating facilities of DOE. The DOE Environmental Survey is one of a series of initiatives announced on September 18, 1985, by Secretary of Energy, John S. Herrington, to strengthen the environmental, safety, and health programs and activities within DOE. The purpose of the Environmental Survey is to identify, via a no fault'' baseline Survey of all the Department's major operating facilities, environmental problems and areas of environmental risk. The identified problem areas will be prioritized on a Department-wide basis in order of importance in 1989. The findings in this report are subject to modification based on the results from the Sampling and Analysis Phase of the Survey. The findings are also subject to modification based on comments from the Albuquerque Operations Office concerning the technical accuracy of the findings. The modified preliminary findings and any other appropriate changes will be incorporated into an Interim Report. The Interim Report will serve as the site-specific source for environmental information generated by the Survey, and ultimately as the primary source of information for the DOE-wide prioritization of environmental problems in the Survey Summary Report. 43 refs., 21 figs., 24 tabs.

  1. Report of preliminary investigations on the next-generation large-scale synchrotron radiation facility projects

    International Nuclear Information System (INIS)

    1990-01-01

    The Special Committee for Future Project of the Japanese Society for Synchrotron Radiation Research investigated the construction-projects of the large-scaled synchrotron radiation facilities which are presently in progress in Japan. As a result, the following both projects are considered the very valuable research-project which will carry the development of Japan's next-generation synchrotron radiation science: 1. the 8 GeV synchrotron radiation facilities (SPring-8) projected to be constructed by Japan Atomic Energy Research Institute and the Institute of Physical and Chemical Research under the sponsorship of Science Technology Agency at Harima Science Park City, Hyogo Pref., Japan. 2. The project to utilize the Tristan Main Ring (MR) of the National Laboratory for High Energy Physics as the radiation source. Both projects are unique in research theme and technological approach, and complemental each other. Therefore it has been concluded that both projects should be aided and ratified by the Society. (M.T.)

  2. Hydraulically driven control rod concept for integral reactors: fluid dynamic simulation and preliminary test

    International Nuclear Information System (INIS)

    Ricotti, M.E.; Cammi, A.; Lombardi, C.; Passoni, M.; Rizzo, C.; Carelli, M.; Colombo, E.

    2003-01-01

    The paper deals with the preliminary study of the Hydraulically Driven Control Rod concept, tailored for PWR control rods (spider type) with hydraulic drive mechanism completely immersed in the primary water. A specific solution suitable for advanced versions of the IRIS integral reactor is under investigation. The configuration of the Hydraulic Control Rod device, made up by an external movable piston and an internal fixed cylinder, is described. After a brief description of the whole control system, particular attention is devoted to the Control Rod characterization via Computational Fluid Dynamics (CFD) analysis. The investigation of the system behavior, including dynamic equilibrium and stability properties, has been carried out. Finally, preliminary tests were performed in a low pressure, low temperature, reduced length experimental facility. The results are compared with the dynamic control model and CFD simulation model, showing good agreement between simulations and experimental data. During these preliminary tests, the control system performs correctly, allowing stable dynamic equilibrium positions for the Control Rod and stable behavior during withdrawal and insertion steps. (author)

  3. Fuel-cycle facilities: preliminary safety and environmental information document. Volume VII

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    Information is presented concerning the mining and milling of uranium and thorium; uranium hexafluoride conversion; enrichment; fuel fabrication; reprocessing; storage options; waste disposal options; transportation; heavy-water-production facilities; and international fuel service centers.

  4. Fuel-cycle facilities: preliminary safety and environmental information document. Volume VII

    International Nuclear Information System (INIS)

    1980-01-01

    Information is presented concerning the mining and milling of uranium and thorium; uranium hexafluoride conversion; enrichment; fuel fabrication; reprocessing; storage options; waste disposal options; transportation; heavy-water-production facilities; and international fuel service centers

  5. Preliminary liver dose estimation in the new facility for biomedical applications at the RA-3 reactor

    International Nuclear Information System (INIS)

    Gadan, M.; Crawley, V.; Thorp, S.; Miller, M.

    2009-01-01

    As a part of the project concerning the irradiation of a section of the human liver left lobe, a preliminary estimation of the expected dose was performed. To obtain proper input values for the calculation, neutron flux and gamma dose rate characterization were carried out using adequate portions of cow or pig liver covered with demineralized water simulating the preservation solution. Irradiations were done inside a container specially designed to fulfill temperature preservation of the organ and a reproducible irradiation position (which will be of importance for future planification purposes). Implantable rhodium based self-powered neutron detectors were developed to obtain neutron flux profiles both external and internal. Implantation of SPND was done along the central longitudinal axis of the samples, where lowest flux is expected. Gamma dose rate was obtained using a neutron shielded graphite ionization chamber moved along external surfaces of the samples. The internal neutron profile resulted uniform enough to allow for a single and static irradiation of the liver. For dose estimation, irradiation condition was set in order to obtain a maximum of 15 Gy-eq in healthy tissue. Additionally, literature reported boron concentrations of 47 ppm in tumor and 8 ppm in healthy tissue and a more conservative relationship (30/10 ppm) were used. To make a conservative estimation of the dose the following considerations were done: (i).Minimum measured neutron flux inside the sample (∼5x10 9 n cm -2 s -1 ) was considered to calculate dose in tumor. (ii).Maximum measured neutron flux (considering both internal as external profiles) was used to calculate dose in healthy tissue (∼8.7x10 9 n cm -2 s -1 ). (iii).Maximum measured gamma dose rate (∼13.5 Gy h -1 ) was considered for both tumor and healthy tissue. Tumor tissue dose was ∼69 Gy-eq for 47 ppm of 10 B and ∼42 Gy-eq for 30 ppm, for a maximum dose of 15 Gy-eq in healthy tissue. As can be seen from these results

  6. 75 FR 4779 - Certain Cut-to-Length Carbon-Quality Steel Plate Products From Italy: Preliminary Results of...

    Science.gov (United States)

    2010-01-29

    ...-Quality Steel Plate Products From Italy: Preliminary Results of Antidumping Duty Administrative Review... administrative review of the antidumping duty order on certain cut-to-length carbon- quality steel plate products... that the Department conduct an administrative review of its sales and entries of subject merchandise...

  7. 75 FR 4044 - Stainless Steel Bar From Brazil: Extension of Time Limit for Preliminary Results of Antidumping...

    Science.gov (United States)

    2010-01-26

    ... DEPARTMENT OF COMMERCE International Trade Administration [A-351-825] Stainless Steel Bar From... antidumping duty order on certain stainless steel bar from Brazil for the period February 1, 2008, through... Steel Bar From Brazil: Extension of Time Limit for Preliminary Results of Antidumping Duty...

  8. 77 FR 11485 - Certain Pasta From Turkey: Extension of Time Limit for the Preliminary Results of Antidumping...

    Science.gov (United States)

    2012-02-27

    ... DEPARTMENT OF COMMERCE International Trade Administration [A-489-805] Certain Pasta From Turkey: Extension of Time Limit for the Preliminary Results of Antidumping Duty Administrative Review AGENCY: Import... initiation of the administrative review of the antidumping duty order on certain pasta from Turkey, covering...

  9. 75 FR 81218 - Laminated Woven Sacks From the People's Republic of China: Preliminary Results of the Second...

    Science.gov (United States)

    2010-12-27

    ... the People's Republic of China: Preliminary Results of the Second Administrative Review AGENCY: Import... laminated woven sacks (``LWS'') from the People's Republic of China (``PRC'') covering the period August 1, 2009, through July 31, 2010. This review covers imports of subject merchandise from one manufacturer...

  10. 77 FR 46030 - Pure Magnesium in Granular Form From the People's Republic of China: Preliminary Results of...

    Science.gov (United States)

    2012-08-02

    ... granular magnesium'') from the People's Republic of China (``PRC'') with respect to one producer/ exporter... Form From the People's Republic of China: Preliminary Results of Antidumping Duty Administrative Review...-2012 Administrative Review of Pure Magnesium in Granular Form from the People's Republic of China...

  11. 76 FR 13358 - Persulfates From the People's Republic of China: Preliminary Results of the 2009-2010 Antidumping...

    Science.gov (United States)

    2011-03-11

    ...'s Republic of China: Preliminary Results of the 2009-2010 Antidumping Duty Administrative Review... conducting an administrative review of the antidumping duty order on persulfates from the People's Republic... review covers one producer/exporter of the subject merchandise, i.e., United Initiators (Shanghai) Co...

  12. 76 FR 33194 - Pure Magnesium From the People's Republic of China: Preliminary Results of the 2009-2010...

    Science.gov (United States)

    2011-06-08

    ... assessment rates are above de minimis. We invite interested parties to comment on these preliminary results... Determination of Sales at Less Than Fair Value: Antidumping Duty Investigation of Pure Magnesium From the... the following alloying elements: aluminum, manganese, zinc, silicon, thorium, zirconium and rare...

  13. 78 FR 69820 - Seamless Refined Copper Pipe and Tube From the People's Republic of China: Preliminary Results...

    Science.gov (United States)

    2013-11-21

    ...\\ \\1\\ See Seamless Refined Copper Pipe and Tube From Mexico and the People's Republic of China... and Tube From the People's Republic of China: Preliminary Results and Partial Rescission of... China (``PRC''), covering the period November 1, 2011 through October 31, 2012. The Department has...

  14. Do provisions to advance chemical facility safety also advance chemical facility security? - An analysis of possible synergies

    OpenAIRE

    Hedlund, Frank Huess

    2012-01-01

    The European Commission has launched a study on the applicability of existing chemical industry safety provisions to enhancing security of chemical facilities covering the situation in 18 EU Member States. This paper reports some preliminary analytical findings regarding the extent to which existing provisions that have been put into existence to advance safety objectives due to synergy effects could be expected advance security objectives as well.The paper provides a conceptual definition of...

  15. The Agricultural Model Intercomparison and Improvement Project (AgMIP): Progress and Preliminary Results

    Science.gov (United States)

    Rosenzweig, C.

    2011-12-01

    The Agricultural Model Intercomparison and Improvement Project (AgMIP) is a distributed climate-scenario simulation exercise for historical model intercomparison and future climate change conditions with participation of multiple crop and agricultural trade modeling groups around the world. The goals of AgMIP are to improve substantially the characterization of risk of hunger and world food security due to climate change and to enhance adaptation capacity in both developing and developed countries. Recent progress and the current status of AgMIP will be presented, highlighting three areas of activity: preliminary results from crop pilot studies, outcomes from regional workshops, and emerging scientific challenges. AgMIP crop modeling efforts are being led by pilot studies, which have been established for wheat, maize, rice, and sugarcane. These crop-specific initiatives have proven instrumental in testing and contributing to AgMIP protocols, as well as creating preliminary results for aggregation and input to agricultural trade models. Regional workshops are being held to encourage collaborations and set research activities in motion for key agricultural areas. The first of these workshops was hosted by Embrapa and UNICAMP and held in Campinas, Brazil. Outcomes from this meeting have informed crop modeling research activities within South America, AgMIP protocols, and future regional workshops. Several scientific challenges have emerged and are currently being addressed by AgMIP researchers. Areas of particular interest include geospatial weather generation, ensemble methods for climate scenarios and crop models, spatial aggregation of field-scale yields to regional and global production, and characterization of future changes in climate variability.

  16. Recent improvements in the calculation of prompt fission neutron spectra: Preliminary results

    International Nuclear Information System (INIS)

    Madland, D.G.; LaBauve, R.J.; Nix, J.R.

    1989-01-01

    We consider three topics in the refinement and improvement of our original calculations of prompt fission neutron spectra. These are an improved calculation of the prompt fission neutron spectrum N(E) from the spontaneous fission of 252 Cf, a complete calculation of the prompt fission neutron spectrum matrix N(E,E n ) from the neutron-induced fission of 235 U, at incident neutron energies ranging from 0 to 15 MeV, and an assessment of the scission neutron component of the prompt fission neutron spectrum. Preliminary results will be presented and compared with experimental measurements and an evaluation. A suggestion is made for new integral cross section measurements. (author). 45 refs, 12 figs, 1 tab

  17. A guide to introducing burnup credit, preliminary version (English translation)

    International Nuclear Information System (INIS)

    Okuno, Hiroshi; Suyama, Kenya; Ryufuku, Susumu

    2017-06-01

    There is an ongoing discussion on the application of burnup credit to the criticality safety controls of facilities that treat spent fuels. With regard to such application of burnup credit in Japan, this document summarizes the current technical status of the prediction of the isotopic composition and criticality of spent fuels, as well as safety evaluation concerns and the current status of legal affairs. This report is an English translation of A Guide to Introducing Burnup Credit, Preliminary Version, originally published in Japanese as JAERI-Tech 2001-055 by the Nuclear Fuel Cycle Facility Safety Research Committee. (author)

  18. Facility accident considerations in the US Department of Energy Waste Management Program

    International Nuclear Information System (INIS)

    Mueller, C.

    1994-01-01

    A principal consideration in developing waste management strategies is the relative importance of Potential radiological and hazardous releases to the environment during postulated facility accidents with respect to protection of human health and the environment. The Office of Environmental Management (EM) within the US Department of Energy (DOE) is currently formulating an integrated national program to manage the treatment, storage, and disposal of existing and future wastes at DOE sites. As part of this process, a Programmatic Environmental impact Statement (PEIS) is being prepared to evaluate different waste management alternatives. This paper reviews analyses that have been Performed to characterize, screen, and develop source terms for accidents that may occur in facilities used to store and treat the waste streams considered in these alternatives. Preliminary results of these analyses are discussed with respect to the comparative potential for significant releases due to accidents affecting various treatment processes and facility configurations. Key assumptions and sensitivities are described

  19. Preliminary concepts for detecting national diversion of LWR spent fuel

    International Nuclear Information System (INIS)

    Sonnier, C.S.; Cravens, M.N.

    1978-04-01

    Preliminary concepts for detecting national diversion of LWR spent fuel during storage, handling and transportation are presented. Principal emphasis is placed on means to achieve timely detection by an international authority. This work was sponsored by the Department of Energy/Office of Safeguards and Security (DOE/OSS) as part of the overall Sandia Fixed Facility Physical Protection Program

  20. Preliminary results for the helicity asymmetry E for eta photoproduction on the proton

    International Nuclear Information System (INIS)

    2012-01-01

    Polarization observables are an important tool for clarifying the nucleon resonance spectrum. No previous measurements for double polarization asymmetries have been published for eta photoproduction. Double polarization measurements have been made at Jefferson Lab using a polarized photon beam and protons in a polarized frozen spin target (FROST). Data were taken during the first running period of FROST using the CLAS detector with photon energies from 0.33 to 2.35 GeV. Preliminary results for the E polarization observable for eta meson photoproduction from the proton at threshold and above, along with comparisons to several theoretical predictions are presented.