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Sample records for anl

  1. Prospects for vitrification of mixed wastes at ANL-E

    International Nuclear Information System (INIS)

    This report summarizes a study evaluating the prospects for vitrification of some of the mixed wastes at ANL-E. This project can be justified on the following basis: Some of ANL-E's mixed waste streams will be stabilized such that they can be treated as a low-level radioactive waste. The expected volume reduction that results during vitrification will significantly reduce the overall waste volume requiring disposal. Mixed-waste disposal options currently used by ANL-E may not be permissible in the near future without treatment technologies such as vitrification

  2. Prospects for vitrification of mixed wastes at ANL-E

    Energy Technology Data Exchange (ETDEWEB)

    Mazer, J.; No, Hyo

    1993-12-01

    This report summarizes a study evaluating the prospects for vitrification of some of the mixed wastes at ANL-E. This project can be justified on the following basis: Some of ANL-E`s mixed waste streams will be stabilized such that they can be treated as a low-level radioactive waste. The expected volume reduction that results during vitrification will significantly reduce the overall waste volume requiring disposal. Mixed-waste disposal options currently used by ANL-E may not be permissible in the near future without treatment technologies such as vitrification.

  3. Preliminary investigation of the 317 Area, ANL-E

    International Nuclear Information System (INIS)

    The 317 Area at Argonne National Laboratory-East (ANL-E) is scheduled to undergo a Resource Conservation and Recovery Act (RCRA) Facility Investigation, Act or RFI. Prior to the formal RFI, a voluntary, preliminary characterization of the 317 Area was conducted by ANL-E. The characterization results were used to formulate the RFI work plan and provided a better focus for the formal investigation. This site presents a difficult engineering challenge. The nature of the waste disposed at this site in the past includes both liquid chemicals and radioactive waste. The 317 Area is classified as a radiologically controlled area because of operations currently performed there. Present Department of Energy policy stipulates that waste material from such an area must be considered radioactive. The possible presence of hazardous constituents in the soil and groundwater would require the investigation-derived waste generated at the site be disposed as radioactive mixed waste. Besides the nature of the waste possibly contaminating this site, the geology of the site poses an equally enigmatic situation. The ANL-E site is located in a region of recessional glacial moraine deposits

  4. ANL-W 779 pond seepage test

    International Nuclear Information System (INIS)

    The ANL-W 779 sanitary wastewater treatment ponds are located on the Idaho National Engineering Laboratory (INEL), north of the Argonne National Laboratory -- West (ANL-W) site A seepage test was performed for two Argonne National Laboratory -- West (ANL-W) sanitary wastewater treatment ponds, Facility 779. Seepage rates were measured to determine if the ponds are a wastewater land application facility. The common industry standard for wastewater land application facilities is a field-measured seepage rate of one quarter inch per day or greater

  5. ENPEP model enhancements at ANL

    International Nuclear Information System (INIS)

    Argonne National Laboratory (ANL) has been involved in energy and electricity planning analyses for almost 20 years. Their activities include the development of analytical tools and methodologies along with their application to a wide variety of national energy planning studies. The methodologies cover all aspects of energy planning. In response to a request by the US Department of Energy (USDOE) to integrate existing tools into a package that could be distributed to developing countries for their own use, the ENergy and Power Evaluation Program (ENPEP) was developed. The USDOE wanted an all purpose tool that would allow the user to do a complete energy analysis, from demand forecast through primary energy resources allocation to electricity generation system expansion plan and environmental analysis. Since its original development, the ENPEP modules have been improved and enhanced to incorporate advancements in computer hardware and software technology, as well as to correct bugs that were identified in the programs. In cooperation with other organizations (e.g. The World Bank - IBRD - and the International Atomic Energy Agency - IAEA -), the ENPEP package has been used at national, regional and inter-regional training courses, as well as in the conduct of national energy/electricity planning studies. This paper reviews the development of the ENPEP package and the proposed enhancements to the package. (author). 1 fig., 2 tabs

  6. Electrometallurgical treatment demonstration at ANL-West

    International Nuclear Information System (INIS)

    Electrometallurgical treatment (EMT) was developed by Argonne National Laboratory (ANL) to ready sodium-bonded spent nuclear fuel for geological disposal. A demonstration of this technology was successfully completed in August 1999. EMT was used to condition irradiated EBR-II driver and blanket fuel at ANL-West. The results of this demonstration, including the production of radioactive high-level waste forms, are presented

  7. Electrometallurgical treatment demonstration at ANL-West

    Energy Technology Data Exchange (ETDEWEB)

    Goff, K. M.; Benedict, R. W.; Johnson, S. G.; Mariani, R. D.; Simpson, M. F.; Westphal, B. R.

    2000-03-20

    Electrometallurgical treatment (EMT) was developed by Argonne National Laboratory (ANL) to ready sodium-bonded spent nuclear fuel for geological disposal. A demonstration of this technology was successfully completed in August 1999. EMT was used to condition irradiated EBR-II driver and blanket fuel at ANL-West. The results of this demonstration, including the production of radioactive high-level waste forms, are presented.

  8. Spent fuel treatment at ANL-West

    International Nuclear Information System (INIS)

    At Argonne National Laboratory-West (ANL-West) there are several thousand kilograms of metallic spent nuclear fuel containing bond sodium. This fuel will be treated in the Fuel Cycle Facility at ANL-West to produce stable waste forms for storage and disposal. The treatment operations will employ a pyrochemical process that also has applications for treating most of the fuel types within the Department of Energy complex. The treatment equipment is in its last stage of readiness, and operations will begin in the Fall of 1994

  9. ANL's electric vehicle battery activities for USABC

    Science.gov (United States)

    The Electrochemical Technology Program at Argonne National Laboratory (ANL) provides advanced battery R&D technology transfer to industry; technical analyses, assessments, modeling, and databases; and independent testing and post-test analyses of advanced batteries. These capabilities and services are being offered to the US Advanced Battery Consortium (USABC) and Cooperative Research and Development Agreements (CRADA) are being negotiated for USABC-sponsored work at ANL. A small portion of DOE's cost share for USABC projects has been provided to ANL to continue R&D and testing activities on key technologies that were previously supported directly by DOE. This report summarizes progress on these USABC projects during the period of April 1 through September 30, 1992. In this report, the objective, background, technical progress, and status are described for each task. The work is organized into the following task areas: 1.0 Lithium/Sulfide Batteries; 2.0 Nickel/Metal Hydride Support 3.0 EV Battery Performance; and Life Evaluation.

  10. A User Guide to PARET/ANL

    Energy Technology Data Exchange (ETDEWEB)

    Olson, A. P. [Argonne National Lab. (ANL), Argonne, IL (United States); Dionne, B. [Argonne National Lab. (ANL), Argonne, IL (United States); Marin-Lafleche, A. [Argonne National Lab. (ANL), Argonne, IL (United States); Kalimullah, M. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2015-01-01

    PARET was originally created in 1969 at what is now Idaho National Laboratory (INL), to analyze reactivity insertion events in research and test reactor cores cooled by light or heavy water, with fuel composed of either plates or pins. The use of PARET is also appropriate for fuel assemblies with curved fuel plates when their radii of curvatures are large with respect to the fuel plate thickness. The PARET/ANL version of the code has been developed at Argonne National Laboratory (ANL) under the sponsorship of the U.S. Department of Energy/NNSA, and has been used by the Reactor Conversion Program to determine the expected transient behavior of a large number of reactors. PARET/ANL models the various fueled regions of a reactor core as channels. Each of these channels consists of a single flat fuel plate/pin (including cladding and, optionally, a gap) with water coolant on each side. In slab geometry the coolant channels for a given fuel plate are of identical dimensions (mirror symmetry), but they can be of different thickness in each channel. There can be many channels, but each channel is independent and coupled only through reactivity feedback effects to the whole core. The time-dependent differential equations that represent the system are replaced by an equivalent set of finite-difference equations in space and time, which are integrated numerically. PARET/ANL uses fundamentally the same numerical scheme as RELAP5 for the time-integration of the point-kinetics equations. The one-dimensional thermal-hydraulic model includes temperature-dependent thermal properties of the solid materials, such as heat capacity and thermal conductivity, as well as the transient heat production and heat transfer from the fuel meat to the coolant. Temperature- and pressure-dependent thermal properties of the coolant such as enthalpy, density, thermal conductivity, and viscosity are also used in determining parameters such as friction factors and heat transfer coefficients. The code

  11. ANL results for LMFR reactivity coefficients benchmark

    International Nuclear Information System (INIS)

    The fast reactor analysis methods developed at ANL were extensively tested in ZPR and ZPPR experiments, applied to EBR-2 and FFTF test reactors. The basic nuclear data library used was ENDF/B-V.2 with the ETOE-2 data processing code and the ENDF/B-VI. Multigroup constants were generated by Monte Carlo code MCNP2-2. Neutron flux calculation were done by DIF3D code applying neutron diffusion theory and finite difference method. The results obtained include basic parameters; fuel and structure regional Doppler coefficients; geometry expansion fuel coefficients; kinetics parameters. In general, agreement between phase 1 and 2 results were excellent

  12. Recommended documentation for computer users at ANL

    Energy Technology Data Exchange (ETDEWEB)

    Heiberger, A.A.

    1992-04-01

    Recommended Documentation for Computer Users at ANL is for all users of the services available from the Argonne National Laboratory (ANL) Computing and Telecommunications Division (CTD). This document will guide you in selecting available documentation that will best fill your particular needs. Chapter 1 explains how to use this document to select documents and how to obtain them from the CTD Document Distribution Counter. Chapter 2 contains a table that categorizes available publications. Chapter 3 gives descriptions of the online DOCUMENT command for CMS, and VAX, and the Sun workstation. DOCUMENT allows you to scan for and order documentation that interests you. Chapter 4 lists publications by subject. Categories I and IX cover publications of a general nature and publications on telecommunications and networks respectively. Categories II, III, IV, V, VI, VII, VIII, and X cover publications on specific computer systems. Category XI covers publications on advanced scientific computing at Argonne. Chapter 5 contains abstracts for each publication, all arranged alphabetically. Chapter 6 describes additional publications containing bibliographies and master indexes that the user may find useful. The appendix identifies available computer systems, applications, languages, and libraries.

  13. ANL Advanced Photon Source crotch absorber design

    International Nuclear Information System (INIS)

    The ANL 7-GeV Advanced Photon Source storage ring crotch absorber will be subjected to a very high photon loading power density, approximately 750 W/mm2 at normal incidence. To accommodate this high heat load, two designs were studied: one is a V-type compound angle absorber and the other is a horizontally rotated plate absorber. For both models, thermal and structural analyses have been carried out using 3-D finite element analysis. The analysis indicates that the V-type compound angle absorber controlled the peak temperatures effectively within the given geometric constraints. Test samples made of GlidCop AL 15 (alumina dispersion strengthened copper) were evaluated with an electron beam welder. The predicted and measured temperatures were in reasonable agreement. The overall absorber design includes a perforated screen in the positron beam area of the storage ring vacuum chamber to reduce RF impedance and to provide pumping access for the high local gas load

  14. ANL experimental program for pulsed superconducting coils

    International Nuclear Information System (INIS)

    Argonne National Laboratory (ANL) had recognized the clear advantage of a superconducting ohmic-heating (OH) coil and started in aggressive development program in FY 1977. The main objectives for FY 1977 are to develop cryostable basic cable configurations with reasonably low ac losses, to develop 12 kA cryostable cable, using it to design and build a 1.5 MJ pulsed coil, and to develop a rather inexpensive large fiberglass reinforced helium cryostat for the 1.5 MJ pulsed coil. The principal objective in building the 1.5 MJ ac coil is to demonstrate ac cryostability of a large coil ranging from 2 T/s up to 12 T/s. Another objective in the pulsed coil program is to determine the feasibility of parallel coil operation in order to avoid excessive voltage and current requirements and to minimize the number of turns for the equilibrium field (EF) coils, should the EF coils be connected in parallel with the OH coils. A two-coil section model using the 11 kA cable will be built and tested

  15. ANL Advanced Photon Source crotch absorber design

    International Nuclear Information System (INIS)

    The ANL 7-GeV Advanced Photon Source storage ring crotch absorber will be subjected to a very high photon loading power density, approximately 750 W/mm2 at normal incidence. To accommodate this high heat load, two designs were studied: one is a V-type compound angle absorber and the other is a horizontally rotated plate absorber. For both models, thermal and structural analyses have been carried out using 3-D finite element analysis. The analysis indicates that the V-type compound angle absorber controlled the peak temperatures effectively within the given geometric constraints. Test samples made of GlidCop Al 15 (alumina dispersion strengthened copper) were evaluated with an electron beam welder. The predicted and measured temperatures were in reasonable agreement. The overall absorber design includes a perforated screen in the positron beam area of the storage ring vacuum chamber to reduce rf impedance and to provide pumping access for the high local gas load. 3 refs., 4 figs., 2 tabs

  16. Colloid-Associated Radionuclide Concentration Limits: ANL

    International Nuclear Information System (INIS)

    The purpose and scope of this report is to describe the analysis of available colloidal data from waste form corrosion tests at Argonne National Laboratory (ANL) to extract characteristics of these colloids that can be used in modeling their contribution to the source term for sparingly soluble radioelements (e.g., Pu). Specifically, the focus is on developing a useful description of the following waste form colloid characteristics: (1) composition, (2) size distribution, and (3) quantification of the rate of waste form colloid generation. The composition and size distribution information are intended to support analysis of the potential transport of the sparingly soluble radionuclides associated with the waste form colloids. The rate of colloid generation is intended to support analysis of the waste form colloid-associated radionuclide concentrations. In addressing the above characteristics, available data are interpreted to address mechanisms controlling colloid formation and stability. This report was developed in accordance with the ''Technical Work Plan for Waste Form Degradation Process Model Report for SR'' (CRWMS M and O 2000). Because the end objective is to support the source term modeling we have organized the conclusions into two categories: (1) data analysis conclusions and (2) recommendations for colloid source term modeling. The second category is included to facilitate use of the conclusions from the data analysis in the abstraction of a colloid source term model. The data analyses and conclusions that are presented in this report are based on small-scale laboratory tests conducted on a limited number of waste glass compositions and spent fuel types

  17. Degradation modeling of the ANL ceramic waste form

    International Nuclear Information System (INIS)

    A ceramic waste form composed of glass-bonded sodalite is being developed at Argonne National Laboratory (ANL) for immobilization and disposition of the molten salt waste stream from the electrometallurgical treatment process for metallic DOE spent nuclear fuel. As part of the spent fuel treatment program at ANL, a model is being developed to predict the long-term release of radionuclides under repository conditions. Dissolution tests using dilute, pH-buffered solutions have been conducted at 40, 70, and 90 C to determine the temperature and pH dependence of the dissolution rate. Parameter values measured in these tests have been incorporated into the model, and preliminary repository performance assessment modeling has been completed. Results indicate that the ceramic waste form should be acceptable in a repository environment

  18. Større anlæg til overfladenedsivning af separat regnvand

    DEFF Research Database (Denmark)

    Vollertsen, Jes; Hvitved-Jacobsen, Thorkild; Nielsen, Asbjørn Haaning

    2012-01-01

    Nedsivning af regnvand kan foregå i underjordiske anlæg eller i anlæg til overfladenedsivning. Sidstnævnte kan være udformet decentralt med nedsivning på fx græsplæner, i grøfter, vejtrug, eller i beplantede bede. Alternativt kan overfladenedsivning ske i centrale anlæg, der modtager vand fra et ...

  19. Recommended documentation for computer users at ANL. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    Heiberger, A.A.

    1992-04-01

    Recommended Documentation for Computer Users at ANL is for all users of the services available from the Argonne National Laboratory (ANL) Computing and Telecommunications Division (CTD). This document will guide you in selecting available documentation that will best fill your particular needs. Chapter 1 explains how to use this document to select documents and how to obtain them from the CTD Document Distribution Counter. Chapter 2 contains a table that categorizes available publications. Chapter 3 gives descriptions of the online DOCUMENT command for CMS, and VAX, and the Sun workstation. DOCUMENT allows you to scan for and order documentation that interests you. Chapter 4 lists publications by subject. Categories I and IX cover publications of a general nature and publications on telecommunications and networks respectively. Categories II, III, IV, V, VI, VII, VIII, and X cover publications on specific computer systems. Category XI covers publications on advanced scientific computing at Argonne. Chapter 5 contains abstracts for each publication, all arranged alphabetically. Chapter 6 describes additional publications containing bibliographies and master indexes that the user may find useful. The appendix identifies available computer systems, applications, languages, and libraries.

  20. A user's guide to the PLTEMP/ANL code

    International Nuclear Information System (INIS)

    PLTEMP/ANL V4.1 is a FORTRAN program that obtains a steady-state flow and temperature solution for a nuclear reactor core, or for a single fuel assembly. It is based on an evolutionary sequence of ''PLTEMP'' codes in use at ANL for the past 20 years. Fueled and non-fueled regions are modeled. Each fuel assembly consists of one or more plates or tubes separated by coolant channels. The fuel plates may have one to five layers of different materials, each with heat generation. The width of a fuel plate may be divided into multiple longitudinal stripes, each with its own axial power shape. The temperature solution is effectively 2-dimensional. It begins with a one-dimensional solution across all coolant channels and fuel plates/tubes within a given fuel assembly, at the entrance to the assembly. The temperature solution is repeated for each axial node along the length of the fuel assembly. The geometry may be either slab or radial, corresponding to fuel assemblies made of a series of flat (or slightly curved) plates, or of nested tubes. A variety of thermal-hydraulic correlations are available with which to determine safety margins such as Onset-of-Nucleate boiling (ONB), departure from nucleate boiling (DNB), and onset of flow instability (FI). Coolant properties for either light or heavy water are obtained from FORTRAN functions rather than from tables. The code is intended for thermal-hydraulic analysis of research reactor performance in the sub-cooled boiling regime. Both turbulent and laminar flow regimes can be modeled. Options to calculate both forced flow and natural circulation are available. A general search capability is available (Appendix XII) to greatly reduce the reactor analyst's time.

  1. Acceptable noise level (ANL) with Danish and non-semantic speech materials in adult hearing-aid users

    DEFF Research Database (Denmark)

    Olsen, Steen Østergaard; Lantz, Johannes; Nielsen, Lars Holme;

    2012-01-01

    The acceptable noise level (ANL) test is used for quantification of the amount of background noise subjects accept when listening to speech. This study investigates Danish hearing-aid users' ANL performance using Danish and non-semantic speech signals, the repeatability of ANL, and the associatio...

  2. Acceptable noise level (ANL) with Danish and non-semantic speech materials in adult hearing-aid users

    DEFF Research Database (Denmark)

    Olsen, Steen Østergaard; Lantz, Johannes; Nielsen, Lars Holme;

    2012-01-01

    The acceptable noise level (ANL) test is used for quantification of the amount of background noise subjects accept when listening to speech. This study investigates Danish hearing-aid users' ANL performance using Danish and non-semantic speech signals, the repeatability of ANL, and the association...

  3. Survey of ANL organization plans for word processors, personal computers, workstations, and associated software

    Energy Technology Data Exchange (ETDEWEB)

    Fenske, K.R.; Rockwell, V.S.

    1992-08-01

    The Computing and Telecommunications Division (CTD) has compiled this Survey of ANL Organization plans for Word Processors, Personal Computers, Workstations, and Associated Software (ANL/TM, Revision 4) to provide DOE and Argonne with a record of recent growth in the acquisition and use of personal computers, microcomputers, and word processors at ANL. Laboratory planners, service providers, and people involved in office automation may find the Survey useful. It is for internal use only, and any unauthorized use is prohibited. Readers of the Survey should use it as a reference document that (1) documents the plans of each organization for office automation, (2) identifies appropriate planners and other contact people in those organizations and (3) encourages the sharing of this information among those people making plans for organizations and decisions about office automation. The Survey supplements information in both the ANL Statement of Site Strategy for Computing Workstations (ANL/TM 458) and the ANL Site Response for the DOE Information Technology Resources Long-Range Plan (ANL/TM 466).

  4. Survey of ANL organization plans for word processors, personal computers, workstations, and associated software. Revision 4

    Energy Technology Data Exchange (ETDEWEB)

    Fenske, K.R.; Rockwell, V.S.

    1992-08-01

    The Computing and Telecommunications Division (CTD) has compiled this Survey of ANL Organization plans for Word Processors, Personal Computers, Workstations, and Associated Software (ANL/TM, Revision 4) to provide DOE and Argonne with a record of recent growth in the acquisition and use of personal computers, microcomputers, and word processors at ANL. Laboratory planners, service providers, and people involved in office automation may find the Survey useful. It is for internal use only, and any unauthorized use is prohibited. Readers of the Survey should use it as a reference document that (1) documents the plans of each organization for office automation, (2) identifies appropriate planners and other contact people in those organizations and (3) encourages the sharing of this information among those people making plans for organizations and decisions about office automation. The Survey supplements information in both the ANL Statement of Site Strategy for Computing Workstations (ANL/TM 458) and the ANL Site Response for the DOE Information Technology Resources Long-Range Plan (ANL/TM 466).

  5. Does the acceptable noise level (ANL) predict hearing-aid use?

    DEFF Research Database (Denmark)

    Olsen, Steen Østergaard; Brännström, K Jonas

    2014-01-01

    OBJECTIVE: It has been suggested that individuals have an inherent acceptance of noise in the presence of speech, and that different acceptance of noise results in different hearing-aid (HA) use. The acceptable noise level (ANL) has been proposed for measurement of this property. It has been...... reviewed journals as well as a number of papers from trade journals, posters and oral presentations from audiologyconventions. CONCLUSIONS: An inherent acceptance of noise in the presence of speech may exist, but no method for precise measurement of ANL is available. The ANL model for prediction of HA use...

  6. ANL statement of site strategy for computing workstations

    Energy Technology Data Exchange (ETDEWEB)

    Fenske, K.R. (ed.); Boxberger, L.M.; Amiot, L.W.; Bretscher, M.E.; Engert, D.E.; Moszur, F.M.; Mueller, C.J.; O' Brien, D.E.; Schlesselman, C.G.; Troyer, L.J.

    1991-11-01

    This Statement of Site Strategy describes the procedure at Argonne National Laboratory for defining, acquiring, using, and evaluating scientific and office workstations and related equipment and software in accord with DOE Order 1360.1A (5-30-85), and Laboratory policy. It is Laboratory policy to promote the installation and use of computing workstations to improve productivity and communications for both programmatic and support personnel, to ensure that computing workstations acquisitions meet the expressed need in a cost-effective manner, and to ensure that acquisitions of computing workstations are in accord with Laboratory and DOE policies. The overall computing site strategy at ANL is to develop a hierarchy of integrated computing system resources to address the current and future computing needs of the laboratory. The major system components of this hierarchical strategy are: Supercomputers, Parallel computers, Centralized general purpose computers, Distributed multipurpose minicomputers, and Computing workstations and office automation support systems. Computing workstations include personal computers, scientific and engineering workstations, computer terminals, microcomputers, word processing and office automation electronic workstations, and associated software and peripheral devices costing less than $25,000 per item.

  7. Demonstration personnel and material tracking system at ANL-W

    International Nuclear Information System (INIS)

    A Personnel and Material Tracking System (PMTS) was demonstrated in the Fuel Manufacturing Facility (FMF) at Argonne National Laboratories-West (ANL-W) in July, 1987. The PMTS is intended to aid in the transfer of inventory materials from area to area within a facility such as FMF. It is also intended to assure that only those personnel who are authorized to do so may conduct these transfer operations. The PMTS Personnel Movement (PM) subsystem uses portals installed between areas to alert the system to the movement of personnel between areas. The portals are composed to two sensors, one on either side of a proximity badge reader, to detect the presence of personnel entering the portal area. However, a restricted area can be assigned to any badge holder which will cause the system to issue an alert if the badge holder passes into his/her restricted area. The PM subsystem is intended to be transparent when in use. The PMTS Inventory Material Access (IMA) subsystem provides two functions: material control and material access. The material control is provided by the Wireless Alarm Transmission of Container Handling (WATCH) system which is a sensor rf transmitter system that detects item movements. Material access is provided by the Mobile Accountability Verification Inventory Station (MAVIS) system which is a self-powered smart barcode reader

  8. Survey of ANL organization plans for word processors, personal computers, workstations, and associated software. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    Fenske, K.R.

    1991-11-01

    The Computing and Telecommunications Division (CTD) has compiled this Survey of ANL Organization Plans for Word Processors, Personal Computers, Workstations, and Associated Software to provide DOE and Argonne with a record of recent growth in the acquisition and use of personal computers, microcomputers, and word processors at ANL. Laboratory planners, service providers, and people involved in office automation may find the Survey useful. It is for internal use only, and any unauthorized use is prohibited. Readers of the Survey should use it as a reference that documents the plans of each organization for office automation, identifies appropriate planners and other contact people in those organizations, and encourages the sharing of this information among those people making plans for organizations and decisions about office automation. The Survey supplements information in both the ANL Statement of Site Strategy for Computing Workstations and the ANL Site Response for the DOE Information Technology Resources Long-Range Plan.

  9. Survey of ANL organization plans for word processors, personal computers, workstations, and associated software

    Energy Technology Data Exchange (ETDEWEB)

    Fenske, K.R.

    1991-11-01

    The Computing and Telecommunications Division (CTD) has compiled this Survey of ANL Organization Plans for Word Processors, Personal Computers, Workstations, and Associated Software to provide DOE and Argonne with a record of recent growth in the acquisition and use of personal computers, microcomputers, and word processors at ANL. Laboratory planners, service providers, and people involved in office automation may find the Survey useful. It is for internal use only, and any unauthorized use is prohibited. Readers of the Survey should use it as a reference that documents the plans of each organization for office automation, identifies appropriate planners and other contact people in those organizations, and encourages the sharing of this information among those people making plans for organizations and decisions about office automation. The Survey supplements information in both the ANL Statement of Site Strategy for Computing Workstations and the ANL Site Response for the DOE Information Technology Resources Long-Range Plan.

  10. The effect of repeated measurements and working memory on the most comfortable level in the ANL test

    DEFF Research Database (Denmark)

    Brännström, K Jonas; Olsen, Steen Østergaard; Holm, Lucas;

    2014-01-01

    OBJECTIVE: To study the effect of a large number of repetitions on the most comfortable level (MCL) when doing the acceptable noise level (ANL) test, and explore if MCL variability is related to central cognitive processes. DESIGN: Twelve MCL repetitions were measured within the ANL test using in...

  11. The ANL electric vehicle battery R&D program for DOE-EHP

    Science.gov (United States)

    1993-06-01

    The Electrochemical Technology Program at Argonne National Laboratory (ANL) provides technical and programmatic support to DOE's Electric and Hybrid Propulsion Division (DOE-EHP). The goal of DOE-EHP is to advance promising electric-vehicle (EV) propulsion technologies to levels where industry will continue their commercial development and thereby significantly reduce air pollution and petroleum consumption due to the transportation sector of the economy. In support of this goal, ANL provides research, development, testing/evaluation, post-test analysis, modeling, and project management on advanced battery technologies for DOE-EHP. The battery-related activities undertaken during the period of 1 Jan. 1993 through 31 Mar. 1993 are summarized. The objective, background, technical progress, and status are described for each task. The work is organized into the following task areas: Project Management; Sodium/Metal Chloride R&D and Microreference Electrodes for Lithium/Polymer Batteries.

  12. ANL progress in developing an LEU target and process for Mo-99 production: Cooperation with CNEA

    International Nuclear Information System (INIS)

    The primary mission of the Reduced Enrichment in Research and Test Reactors (RERTR) Program is to facilitate the conversion of research and test-reactor fuel and targets from high-enriched uranium (HEU) to low-enriched uranium (LEU). One of the current goals at Argonne National Laboratory (ANL) is to assist the Argentine Comision Nacional de Energia Atomica (CNEA) in developing an LEU foil target and a process for 99Mo production. Specifically addressed in this paper is ANL R and D related to this conversion: (1) designing a prototype production vessel for digesting irradiated LEU foils in alkaline solutions and (2) developing a new digestion method to address all issues related to HEU to LEU conversion. (author)

  13. Current research using the ANL High Voltage Electron Microscope-Tandem Accelerator Facility

    International Nuclear Information System (INIS)

    Recent work at the Argonne National Laboratory, (ANL), HVEM-Tandem Accelerator user facility is summarized: direct observation of cluster defects formed by in-situ ion irradiation at low temperature using the ion-beam interface has led to important fundamental results on defect production processes. Results on solute segregation at elevated temperatures induced by electron and ion irradiation are reported. Other published work is briefly summarized and/or referenced

  14. Current research using the ANL High Voltage Electron Microscope-Tandem Accelerator Facility

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, A.; Ryan, E.A.

    1984-11-01

    Recent work at the Argonne National Laboratory, (ANL), HVEM-Tandem Accelerator user facility is summarized: direct observation of cluster defects formed by in-situ ion irradiation at low temperature using the ion-beam interface has led to important fundamental results on defect production processes. Results on solute segregation at elevated temperatures induced by electron and ion irradiation are reported. Other published work is briefly summarized and/or referenced.

  15. The ANL X6B beamline at NSLS: A versatile facility

    International Nuclear Information System (INIS)

    We have described the x-ray optics and beamline performance of the ANL X6B beam line at the NSLS. Considerable flexibility has been built into the beam line to accommodate a wide range of x-ray diffraction, scattering, and spectroscopy experiments with various requirements. We presented selected examples of experimental results and showed that with the high intensity, high energy resolution, high-q resolution, and energy tunability, the X6B beam line has become a versatile facility

  16. Light-quark baryon spectroscopy within ANL-Osaka dynamical coupled-channels approach

    CERN Document Server

    Kamano, Hiroyuki

    2016-01-01

    Recent results on the study of light-quark baryons with the ANL-Osaka dynamical coupled-channels (DCC) approach are presented, which contain the N* and Delta* spectroscopy via the analysis of pi N and gamma N reactions and the Lambda* and Sigma* spectroscopy via the analysis of K- p reactions. A recent application of our DCC approach to neutrino-nucleon reactions in the resonance region is also presented.

  17. ANL site response for the DOE FY1994 information resources management long-range plan

    Energy Technology Data Exchange (ETDEWEB)

    Boxberger, L.M.

    1992-03-01

    Argonne National Laboratory's ANL Site Response for the DOE FY1994 Information Resources Management (IRM) Long-Range Plan (ANL/TM 500) is one of many contributions to the DOE information resources management long-range planning process and, as such, is an integral part of the DOE policy and program planning system. The Laboratory has constructed this response according to instructions in a Call issued in September 1991 by the DOE Office of IRM Policy, Plans and Oversight. As one of a continuing series, this Site Response is an update and extension of the Laboratory's previous submissions. The response contains both narrative and tabular material. It covers an eight-year period consisting of the base year (FY1991), the current year (FY1992), the budget year (FY1993), the plan year (FY1994), and the out years (FY1995-FY1998). This Site Response was compiled by Argonne National Laboratory's Computing and Telecommunications Division (CTD), which has the responsibility to provide leadership in optimizing computing and information services and disseminating computer-related technologies throughout the Laboratory. The Site Response consists of 5 parts: (1) a site overview, describes the ANL mission, overall organization structure, the strategic approach to meet information resource needs, the planning process, major issues and points of contact. (2) a software plan for DOE contractors, Part 2B, Software Plan FMS plan for DOE organizations, (3) computing resources telecommunications, (4) telecommunications, (5) printing and publishing.

  18. ANL site response for the DOE FY1994 information resources management long-range plan

    Energy Technology Data Exchange (ETDEWEB)

    Boxberger, L.M.

    1992-03-01

    Argonne National Laboratory`s ANL Site Response for the DOE FY1994 Information Resources Management (IRM) Long-Range Plan (ANL/TM 500) is one of many contributions to the DOE information resources management long-range planning process and, as such, is an integral part of the DOE policy and program planning system. The Laboratory has constructed this response according to instructions in a Call issued in September 1991 by the DOE Office of IRM Policy, Plans and Oversight. As one of a continuing series, this Site Response is an update and extension of the Laboratory`s previous submissions. The response contains both narrative and tabular material. It covers an eight-year period consisting of the base year (FY1991), the current year (FY1992), the budget year (FY1993), the plan year (FY1994), and the out years (FY1995-FY1998). This Site Response was compiled by Argonne National Laboratory`s Computing and Telecommunications Division (CTD), which has the responsibility to provide leadership in optimizing computing and information services and disseminating computer-related technologies throughout the Laboratory. The Site Response consists of 5 parts: (1) a site overview, describes the ANL mission, overall organization structure, the strategic approach to meet information resource needs, the planning process, major issues and points of contact. (2) a software plan for DOE contractors, Part 2B, ``Software Plan FMS plan for DOE organizations, (3) computing resources telecommunications, (4) telecommunications, (5) printing and publishing.

  19. Performance assessment of KORAT-3D on the ANL IBM-SP computer

    International Nuclear Information System (INIS)

    The TENAR code is currently being developed at the Russian Federal Nuclear Center (VNIIEF) as a coupled dynamics code for the simulation of transients in VVER and RBMK systems and other nuclear systems. The neutronic module in this code system is KORAT-3D. This module is also one of the most computationally intensive components of the code system. A parallel version of KORAT-3D has been implemented to achieve the goal of obtaining transient solutions in reasonable computational time, particularly for RBMK calculations that involve the application of >100,000 nodes. An evaluation of the KORAT-3D code performance was recently undertaken on the Argonne National Laboratory (ANL) IBM ScalablePower (SP) parallel computer located in the Mathematics and Computer Science Division of ANL. At the time of the study, the ANL IBM-SP computer had 80 processors. This study was conducted under the auspices of a technical staff exchange program sponsored by the International Nuclear Safety Center (INSC)

  20. Status of ANL out-of-pile investigations of severe accident phenomena for liquid metal reactors

    Energy Technology Data Exchange (ETDEWEB)

    Spencer, B.W.; Marchaterre, J.F.; Anderson, R.P.; Armstrong, D.R.; Baker, L.; Cho, D.H.; Gabor, J.D.; Pedersen, D.R.; Sienicki, J.J.; Stein, R.P.

    1986-01-01

    Research addressing LMFBR whole core accidents has been terminated, and there is now emphasis on quantifying reactivity feedbacks, and in particular enhancing negative feedback, so that advanced LMR designs will provide inherently safe operation. The status of recent HCDA-related laboratory research performed at ANL, up to the time that such activities were no longer needed to support CRBR licensing, is described. Included are descriptions of programs addressing sodium channel voiding, fuel sweepout, fuel dispersal and plugging, boiled-up pool, UO/sub 2//sodium FCI, and debris coolability. Descriptions of recent investigations involving the metal fuel/sodium system are also included.

  1. Status of ANL out-of-pile investigations of severe accident phenomena for liquid metal reactors

    International Nuclear Information System (INIS)

    Research addressing LMFBR whole core accidents has been terminated, and there is now emphasis on quantifying reactivity feedbacks, and in particular enhancing negative feedback, so that advanced LMR designs will provide inherently safe operation. The status of recent HCDA-related laboratory research performed at ANL, up to the time that such activities were no longer needed to support CRBR licensing, is described. Included are descriptions of programs addressing sodium channel voiding, fuel sweepout, fuel dispersal and plugging, boiled-up pool, UO2/sodium FCI, and debris coolability. Descriptions of recent investigations involving the metal fuel/sodium system are also included

  2. Fire Environment Mechanism of Lightning-groundfire for Daxing anling Mountains

    Institute of Scientific and Technical Information of China (English)

    2003-01-01

    Ground fire is an igniting phenomenon that is difficult to control and lightning is the main cause of ground fire. The mechanism of lightning-ground fire is very complex. Daxing'anling Mountains forest region is the place that lighting-groundfire occurs more often and regularly. Our study on lightning-groundfire of this zone in 2002 shows: much more soil near the surface and the ground fuel is the matter preconditions of lightning-groundfire, and the weather conditions hasten the occurrence of lightning...

  3. Assessment Using ANL Experiments on Void Fraction in a Vertical Tube

    Energy Technology Data Exchange (ETDEWEB)

    Han, KyuHyun; Bang, YoungSeok [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2015-05-15

    A licensing application of a safety analysis code, SPACE, was submitted and is currently under KINS' review. This code was developed to consider three fluid fields, i.e. liquid, vapor and droplet, for a realistic simulation of accident phenomena. Therefore, there may be a concern that this code could predict different behavior compared to the existing codes. To assess the important performance independently and to compare with prediction results of SPACE might be helpful to regulatory review for identifying validity of the code. The interfacial friction could largely affect prediction of thermal hydraulic phenomena during LOCA or non- LOCA. This paper provides MARS-KS prediction of void fraction experiments in a vertical tube by ANL and compares with SPACE prediction results. It was found that the similar interfacial friction model adopting the drift flux correlations were implemented in both codes. Experimental void fractions of the ANL test presented in this paper correspond to bubbly, slug and churn flow regions. Agreements in general sense between the experiment and the predicted values were identified through calculations. Thus, similar accuracy for this experiment can be expected in SPACE and MARS-KS. It was also shown that drift flux interfacial friction model for intermediate flow channel (diameter of 7cm) is valid.

  4. The ANL electric vehicle battery R/D program for DOE-EHP

    Science.gov (United States)

    1993-03-01

    The Electrochemical Technology Program at Argonne National Laboratory (ANL) provides technical and programmatic support to DOE's Electric and Hybrid PropuLsion Division (DOE-EHP). The goal of DOE-EHP is to advance promising electric-vehicle (EV) propulsion technologies to levels where industry will continue their commercial development and thereby significantly reduce air pollution and petroleum consumption. In support of this goal, ANL provides research, development, testing/evaluation, post-test analysis, modeling, and technical management of industrial R&D contracts on advanced battery technologies for DOE-EHP. This report summarizes the battery-related activities undertaken during the period of 1 Oct. 1992 - 31 Dec. 1992. In this report, the objective, background, technical progress, and status are described for each task. The work is organized into the following task areas: 1.0 Project Management and Coordination; 2.0 Sodium/Metal Chloride R&D 3.0 Microreference Electrodes for Lithium/Polymer Batteries; and 4.0 USABC Support. The Project Management and Coordination Task Area encompasses planning, organization, coordination, integration, and overall management of battery R&D projects for DOE-EHP, as well as work performed in behalf of DOE-directed inter-laboratory tasks. Section 3 of this report recounts the work performed during this reporting period on each task within these task areas.

  5. The ANL Electrochemical Program for DOE on electric vehicle R/D

    Science.gov (United States)

    1992-11-01

    The Electrochemical Technology Program at Argonne National Laboratory (ANL) provides technical and programmatic support to DOE's Electric and Hybrid Propulsion Division (DOE-EHP). The goal of DOE-EHP is to advance promising electric-vehicle (EV) propulsion technologies to levels where industry will continue their commercial development and thereby significantly reduce petroleum consumption in the transportation sector of the economy. In support of this goal, ANL provides research, development, testing/evaluation, post-test analysis, modeling, database management, and technical management of industrial R&D contracts on advanced battery technologies for DOE-EHP. This report summarizes the battery-related activities undertaken during the period of July 1, 1992 through September 30, 1992. In this report, the objective, background, technical progress, and status are described for each task. The work is organized into the following task areas: Project Management and Coordination; Lithium/Sulfide Batteries; Advanced Sodium/Beta Batteries; Advanced Ambient-Temperature Batteries; and EV Battery Performance and Life Evaluation.

  6. A general evaluation of poisoning cases occured from 1990 to 1996in Şanlıurfa

    OpenAIRE

    OCAK, Dr. Seyfullah O. ARSLAN Dr. Mustafa KÖSE

    1998-01-01

    The aim of this study is to evaluate the causes and the results of acute poisoning cases occurred in Şanlıurfa. Record books of emergency departments of State and Children Hospital from 1990 to 1996 in Şanlı/ifa were retrospectively investigated. Acute poisoning cases were evaluated with regard to sex, age, poisoning causes and results. Of total 2379 poisoning cases, 818 (34.4 %) were in childhood and 1561 (65.6 %) were in adolescents. The incidence of acute poisoning cases was 0.97 %. The mo...

  7. ANL Technical Support Program for DOE Environmental Restoration and Waste Management

    International Nuclear Information System (INIS)

    This report provides an overview of progress during FY 1991 for the Technical Support Program that is part of the ANL Technology Support Activity for DOE, Environmental Restoration and Waste Management (EM). The purpose is to evaluate, before hot start-up of the Defenses Waste Processing Facility (DWPF) and the West Valley Demonstration Project (WVDP), factors that are likely to affect glass reaction in an unsaturated environment typical of what may be expected for the candidate Yucca Mountain repository site. Specific goals for the testing program include the following: (1) to review and evaluate available information on parameters that will be important in establishing the long-term performance of glass in a repository environment; (2) to perform testing to further quantify the effects of important variables where there are deficiencies in the available data; and (3) to initiate long-term testing that will bound glass performance under a range of conditions applicable to repository disposal

  8. Analysis of the KUCA MEU experiments using the ANL code system

    Energy Technology Data Exchange (ETDEWEB)

    Shiroya, S.; Hayashi, M.; Kanda, K.; Shibata, T.; Woodruff, W.L.; Matos, J.E.

    1982-01-01

    This paper provides some preliminary results on the analysis of the KUCA critical experiments using the ANL code system. Since this system was employed in the earlier neutronics calculations for the KUHFR, it is important to assess its capabilities for the KUHFR. The KUHFR has a unique core configuration which is difficult to model precisely with current diffusion theory codes. This paper also provides some results from a finite-element diffusion code (2D-FEM-KUR), which was developed in a cooperative research program between KURRI and JAERI. This code provides the capability for mockup of a complex core configuration as the KUHFR. Using the same group constants generated by the EPRI-CELL code, the results of the 2D-FEM-KUR code are compared with the finite difference diffusion code (DIF3D(2D) which is mainly employed in this analysis.

  9. Revised ANL-reported tensile data for V-Ti and V-Cr-Ti alloys

    Energy Technology Data Exchange (ETDEWEB)

    Billone, M.C. [Argonne National Lab., IL (United States)

    1997-08-01

    The tensile for all irradiated vanadium alloy samples and several unirradiated vanadium alloys tested at Argonne National Laboratory (ANL) have been critically reviewed and revised, as necessary. The review and revision are based on re-analyzing the original load-displacement strip-chart recording using a methodology consistent with current ASTM standards. No significant difference has been found between the newly-revised and previously-reported values of yield strength (YS) and ultimate tensile strength (UTS). However, by correctly subtracting the non-gauge-length displacement and linear gauge-length displacement from the total cross-head displacement, the uniform elongation (UE) of the gauge length decreases by 4-9% strain and the total elongation (TE) of the gauge length decreases by 1-7% strain. These differences are more significant for lower-ductility irradiated alloys than for higher-ductility alloys.

  10. A user's guide to the PLTEMP/ANL code.

    Energy Technology Data Exchange (ETDEWEB)

    Kalimullah, M. (Nuclear Engineering Division)

    2011-07-05

    PLTEMP/ANL V4.1 is a FORTRAN program that obtains a steady-state flow and temperature solution for a nuclear reactor core, or for a single fuel assembly. It is based on an evolutionary sequence of ''PLTEMP'' codes in use at ANL for the past 20 years. Fueled and non-fueled regions are modeled. Each fuel assembly consists of one or more plates or tubes separated by coolant channels. The fuel plates may have one to five layers of different materials, each with heat generation. The width of a fuel plate may be divided into multiple longitudinal stripes, each with its own axial power shape. The temperature solution is effectively 2-dimensional. It begins with a one-dimensional solution across all coolant channels and fuel plates/tubes within a given fuel assembly, at the entrance to the assembly. The temperature solution is repeated for each axial node along the length of the fuel assembly. The geometry may be either slab or radial, corresponding to fuel assemblies made of a series of flat (or slightly curved) plates, or of nested tubes. A variety of thermal-hydraulic correlations are available with which to determine safety margins such as Onset-of-Nucleate boiling (ONB), departure from nucleate boiling (DNB), and onset of flow instability (FI). Coolant properties for either light or heavy water are obtained from FORTRAN functions rather than from tables. The code is intended for thermal-hydraulic analysis of research reactor performance in the sub-cooled boiling regime. Both turbulent and laminar flow regimes can be modeled. Options to calculate both forced flow and natural circulation are available. A general search capability is available (Appendix XII) to greatly reduce the reactor analyst's time.

  11. A User's Guide to the PLTEMP/ANL Code

    Energy Technology Data Exchange (ETDEWEB)

    Olson, Arne P. [Argonne National Lab. (ANL), Argonne, IL (United States); Kalimullah, M. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2015-07-07

    PLTEMP/ANL V4.2 is a FORTRAN program that obtains a steady-state flow and temperature solution for a nuclear reactor core, or for a single fuel assembly. It is based on an evolutionary sequence of ''PLTEMP'' codes in use at ANL for the past 20 years. Fueled and non-fueled regions are modeled. Each fuel assembly consists of one or more plates or tubes separated by coolant channels. The fuel plates may have one to five layers of different materials, each with heat generation. The width of a fuel plate may be divided into multiple longitudinal stripes, each with its own axial power shape. The temperature solution is effectively 2-dimensional. It begins with a one-dimensional solution across all coolant channels and fuel plates/tubes within a given fuel assembly, at the entrance to the assembly. The temperature solution is repeated for each axial node along the length of the fuel assembly. The geometry may be either slab or radial, corresponding to fuel assemblies made of a series of flat (or slightly curved) plates, or of nested tubes. A variety of thermal-hydraulic correlations are available with which to determine safety margins such as Onset-of- Nucleate boiling (ONB), departure from nucleate boiling (DNB), and onset of flow instability (FI). Coolant properties for either light or heavy water are obtained from FORTRAN functions rather than from tables. The code is intended for thermal-hydraulic analysis of research reactor performance in the sub-cooled boiling regime. Both turbulent and laminar flow regimes can be modeled. Options to calculate both forced flow and natural circulation are available. A general search capability is available (Appendix XII) to greatly reduce the reactor analyst’s time.

  12. A User's Guide to the PLTEMP/ANL Code

    International Nuclear Information System (INIS)

    PLTEMP/ANL V4.2 is a FORTRAN program that obtains a steady-state flow and temperature solution for a nuclear reactor core, or for a single fuel assembly. It is based on an evolutionary sequence of ''PLTEMP'' codes in use at ANL for the past 20 years. Fueled and non-fueled regions are modeled. Each fuel assembly consists of one or more plates or tubes separated by coolant channels. The fuel plates may have one to five layers of different materials, each with heat generation. The width of a fuel plate may be divided into multiple longitudinal stripes, each with its own axial power shape. The temperature solution is effectively 2-dimensional. It begins with a one-dimensional solution across all coolant channels and fuel plates/tubes within a given fuel assembly, at the entrance to the assembly. The temperature solution is repeated for each axial node along the length of the fuel assembly. The geometry may be either slab or radial, corresponding to fuel assemblies made of a series of flat (or slightly curved) plates, or of nested tubes. A variety of thermal-hydraulic correlations are available with which to determine safety margins such as Onset-of- Nucleate boiling (ONB), departure from nucleate boiling (DNB), and onset of flow instability (FI). Coolant properties for either light or heavy water are obtained from FORTRAN functions rather than from tables. The code is intended for thermal-hydraulic analysis of research reactor performance in the sub-cooled boiling regime. Both turbulent and laminar flow regimes can be modeled. Options to calculate both forced flow and natural circulation are available. A general search capability is available (Appendix XII) to greatly reduce the reactor analyst's time.

  13. A review of ANL base technology studies in support of the U.S. LMFBR vibration program

    International Nuclear Information System (INIS)

    Argonne National Laboratory (ANL) is the center for base technology studies of flow induced vibration for the U.S. LMFBR Program. This paper reviews and summarizes published results, reports on the status of ongoing programs, and discusses future needs as outlined in the U.S. LMFBR Vibrations Program Plan. (author)

  14. Superfund record of decision (EPA Region 10): Idaho National Engineering Lab (USDOE) (ANL-W), Operable Unit 9-04, Idaho Falls, ID, September 29, 1998

    International Nuclear Information System (INIS)

    The Argonne National Laboratory-West (ANL-W) Waste Area Group 9 (WAG 9) is one of the ten Idaho National Engineering and Environmental Laboratory (INEEL) WAGs identified in the Federal Facility Agreement and Consent Order (FFA/CO). The eight affected areas at ANL-W include the Sanitary Sewage Lagoons (ANL-04), Industrial Waste Pond, Ditches A, Ditch B, (all from ANL-01), Main Cooling Tower Blowdown Ditch (ANL-01A), Interceptor Canal-Canal and-Mound (sub-portions of ANL-09), and the Industrial Waste Lift Station Discharge Ditch (ANL-35). The major components of the selected remedy for ANL-W are: Completion of phytoremediation workplan for the field-scale testing; Conducting a field-scale phytoremediation test of selected plant species at the sites that pose unacceptable risks; Determining the effectiveness and implementability of phytoremediation based on results of field-scale testing; Collecting soil and plant samples after a two-year field season to be used to determine the effectiveness of phytoremediation on the ANL-W soils; Harvesting, compacting, incinerating, and disposing of the above- and below-ground plant matter that will be sent to a permitted landfill; Continuing the planting, harvesting process for phytoremediation only if completion of the two-year field-scale testing is successful; Installing access restrictions consisting of fences, bird netting, and posting warning signs; Review of the remedy no less than every five years after the RAOs have been met until the year 2098; and Implementing DOE controls which limit residential land use for at least 100 years from now (2098)

  15. WIMS-ANL 4.0, Deterministic Code System for Lattice Calculation

    International Nuclear Information System (INIS)

    1 - Description of program or function: The WIMS-ANL code is an extension of the Winfrith WIMS-D4 code for lattice cell computations. This code has been tailored to address some of the problem areas encountered in dealing with research reactor fuels, experiment, reflector and control regions. The SUPERCELL option eliminates some of the limitations of the traditional SPECTROX solution and supports the solution of more complex geometries with a more detailed spatial mesh and multiple resonance materials. The code generates both macroscopic and microscopic cross sections in the ISOTXS format with any selected number of energy groups. The user can specify which fission product isotopes are to be explicitly included in the microscopic burnup dependent ISOTXS library. Fission product library data can be generated for use with the MCNP code and burnup dependent applications. The cross section library data provided are based on ENDF/B version VI (69 group) and V (69 and 172 group) data. A revised 172 group library based on ENDF/B-VI is being generated with newer data and additional isotopes. This library will be made available at a later time. The code is variably dimensioned so that other group structures could be used. The source code and output format have been completely revised to reflect current coding practices and to permit display of the results on typical desk top monitors. The content of the output displayed is completely under the user's control. 2 - Methods:The methods of solution in WIMS-ANL remain unchanged from those used in the original WIMS-D4 code with the same resonance treatment and a choice of collision probability and DSN solutions for the simple lattice cell. The SUPERCELL option provides for the selection of supporting auxiliary cells that might represent the various different elements and varying spectra of the final SUPERCELL model. The resonance treatments where applicable are carried out in the auxiliary cells. These data are combined in the

  16. Review of ANL research on lithium--hydrogen chemistry and tritium-containment technology

    International Nuclear Information System (INIS)

    Experimental data on the thermodynamic properties of solutions of protium, deuterium, and tritium in liquid lithium are reported. The significance of the results is discussed with regard to problems that are pertinent to the development of controlled thermonuclear fusion reactors. Values are given for the equilibrium constants, free energies of formation, plateau dissociation pressures, and Sieverts' constants in the Li-LiH, Li-LiD, and Li-LiT systems. The observed isotope effects in these systems appear to reside predominantly in the gas phase. Results of studies of the distribution of tritium between liquid lithium and selected molten salts indicate that molten-salt extraction has potential utility as a means of recovering tritium from liquid lithium fusion reactor blankets. Other recent work at ANL has given evidence that multilayered bonded-metal composites could be useful in reducing tritium permeation rates through thermally hot structures (e.g., steam generator tubes) in fusion devices and power reactors. Hydrogen permeation data are presented for three bonded-metal composites (i.e., 316-SS/Cu/316-SS, 304-SS/Nb, and 304-SS/Cu/Nb) as well as for 304-SS and 316-SS. The data are compared to calculated permeabilities for the bonded-metal composites based on an electro-analog model. (auth)

  17. Analysis of Moderator Temperature Reactivity Coefficient of the PWR Core Using WIMS-ANL

    International Nuclear Information System (INIS)

    The Moderator Temperature Reactivity Coefficient (MTRC) is an important parameter in design, control and safety, particularly in PWR reactor. It is then very important to validate any new processed library for an accurate prediction of this parameter. The objective of this work is to validate the newly WIMS library based on ENDF/B-VI nuclear data files, especially for the prediction of the MTRC parameter. For this purpose, it is used a set of light water moderated lattice experiments as the NORA experiment and R1-100H critical reactors, both of reactors using UO2 fuel pellet. Analysis is used with WIMSD/4 lattice code with original cross section libraries and WIMS-ANL with ENDF/B-VI cross section libraries. The results showed that the moderator temperatures reactivity coefficients for the NORA reactor using original libraries is - 5.039E-04 %Δk/k/℃ but for ENDF/B-VI libraries is - 2.925E-03 %Δk/k/℃. Compared to the designed value of the reactor core, the difference is in the range of 1.8 - 3.8 % for ENDF/B-IV libraries. It can be concluded that for reactor safety and control analysis, it has to be used ENDF/B- VI libraries because the original libraries is not accurate any more. (author)

  18. Short communication: Aflatoxin M₁ in dairy products sold in Şanlıurfa, Turkey.

    Science.gov (United States)

    Temamogullari, F; Kanici, A

    2014-01-01

    The aim of this study was to detect the presence of aflatoxin M₁ (AFM1) in samples of raw milk (n=38), UHT milk (n=12), white pickled cheese (n=50), and yogurt (n=50) collected from the Şanlıurfa city markets and locally produced dairy products by ELISA. The mean contamination rates were 56.74 ± 40.32, 43.1 ± 23.19, 103.2 ± 29.13, and 55.28 ± 12.68 ng/kg, respectively, for raw milk, UHT milk, white pickled cheese, and yogurt. According to the data, 21 (55%) raw milk, 3 (25%) UHT milk, 10 (20%) white pickled cheese, and 10 (20%) yogurt samples were contaminated with AFM1 over the acceptable levels (≥50 ng/kg), ranging from 0.82 to 130.89 ng/kg. None of the white pickled cheese samples contained AFM1 levels above the Turkish legal limit (250 ng/kg). Consequently, the AFM1 contamination levels determined in this study in white pickled cheese were not considered to pose a serious public health hazard. However, the AFM1 levels in raw and UHT milk and yogurt samples indicate an increased human health risk in Turkey related to high aflatoxin levels. Therefore, milk and dairy products have to be monitored by the Turkish public health authorities continuously to detect AFM1 contamination. PMID:24239070

  19. High power test results of the first SRRC/ANL high current L-band RF gun.

    Energy Technology Data Exchange (ETDEWEB)

    Ho, C. H.

    1998-09-11

    A joint program is underway between the SRRC (Synchrotrons Radiation Research Center, Taiwan) and ANL (Argonne National Laboratory, USA) for developing a high current L-band photocathode rf guns. We have constructed an L-Band (1.3 Ghz), single cell rf photocathode gun and conducted low power tests at SRRC. High power rf conditioning of the cavity has been completed at ANL. In this paper we report on the construction and high power test results. So far we have been able to achieve > 120 MV/m axial electric field with minimal dark current. This gun will be used to replace the AWA (Argonne Wakefield Accelerator)[l] high current gun.

  20. Mapping the Anthocyaninless (anl) Locus in Rapid-Cycling Brassica rapa (RBr) to Linkage Group R9

    OpenAIRE

    Wendell Douglas L; Burdzinski Carrie

    2007-01-01

    Abstract Background Anthocyanins are flavonoid pigments that are responsible for purple coloration in the stems and leaves of a variety of plant species. Anthocyaninless (anl) mutants of Brassica rapa fail to produce anthocyanin pigments. In rapid-cycling Brassica rapa, also known as Wisconsin Fast Plants, the anthocyaninless trait, also called non-purple stem, is widely used as a model recessive trait for teaching genetics. Although anthocyanin genes have been mapped in other plants such as ...

  1. Effect of age on inter and intra-subject variability in acceptable noise level (ANL in listeners with normal hearing

    Directory of Open Access Journals (Sweden)

    Bankole K. Fasanya

    2013-02-01

    Full Text Available Several industrial engineering and psychological studies have shown that noise affects the important aspects of communication for both adults and children. For speech understanding by hearing aids users and language development in children, an accurate hearing is very important. A metric has been developed for measuring an individual's acceptance of noise while listening to speech in quiet. This metric is known as Acceptable Noise Levels (ANLs. Studies have shown large inter-subject variability in acceptance of background noise. An argument has been made that an acceptance of background noise is a “means” that will help to solve the puzzle and monumental problem of hearing aid rejection. Meanwhile, within subject age dependency has not been investigated. This study is conducted to determine if ANL inter and intra-subject variability under music signal depends on age. Twenty subjects participated in the study (average age = 29; SD = 3.7; range 23-35 years. All participants had hearing level not worse than 25dB HL at octave frequencies from 250Hz to 4000Hz. Listeners’ task was to adjust the level of music played in quiet to their most comfortable listening level and then to adjust the level of background noise to the maximum level that they still consider acceptable while listening to music. Further, music is not a speech signal that many researchers have used to determine the significance of age on ANL inter-subject variability. Results of this study supported the findings of others on age dependency, which shows that ANL inter and intra-subject variability is independent of age.

  2. Effect of age on inter and intra-subject variability in acceptable noise level (ANL) in listeners with normal hearing

    OpenAIRE

    Fasanya, Bankole K.; Oluseun Omotoso; Olariyike A. Fasanya

    2013-01-01

    Several industrial engineering and psychological studies have shown that noise affects the important aspects of communication for both adults and children. For speech understanding by hearing aids users and language development in children, an accurate hearing is very important. A metric has been developed for measuring an individual's acceptance of noise while listening to speech in quiet. This metric is known as Acceptable Noise Levels (ANLs). Studies have shown large inter-subject variabil...

  3. A plan for administrative computing at ANL FY1991 through FY1993

    Energy Technology Data Exchange (ETDEWEB)

    Caruthers, L.E. (ed.); O' Brien, D.E.; Bretscher, M.E.; Hischier, R.C.; Moore, N.J.; Slade, R.G.

    1990-10-01

    In July of 1988, Argonne National Laboratory management approved the restructuring of Computing Services into the Computing and Telecommunications Division, part of the Physical Research area of the Laboratory. One major area of the Computing and Telecommunications Division is Management Information Systems (MIS). A significant aspect of Management Information Systems' work is the development of proposals for new and enhanced administrative computing systems based on an analysis of informational needs. This document represent the outcome of the planning process for FY1991 through FY1993. The introduction of the FY1991 through FY1993 Long-Range Plan assesses the state of administrative computing at ANL and the implications of FY1991 funding recommendations. It includes a history of MIS planning for administrative data processing. This document discusses the strategy and goals which are an important part of administrative data processing plans for the Laboratory. It also describes the management guidelines established by the Administrative Data Processing Oversight Committee for the proposal and implementation of administrative computing systems. Summaries of the proposals for new or enhanced administrative computing systems presented by individual divisions or departments with assistance of Management Information Systems, to the Administrative Data Processing Oversight Committee are given. The detailed tables in this paper give information on how much the resources to develop and implement a given systems will cost its users. The tables include development costs, computing/operations costs, software and hardware costs, and efforts costs. They include both systems funded by Laboratory General Expense and systems funded by the users themselves.

  4. Determination of adult population development of Tomato Leafminer [Tuta absoluta (Meyrick) (Lepidoptera: Gelechiidae)] in tomato growing areas in Şanlıurfa province

    OpenAIRE

    mamay, mehmet; YANIK, Ertan

    2012-01-01

    This study was performed in tomato growing areas of Çamlıdere, Göktepe and Yığınak location in Şanlıurfa during the 2010 and 2011 growing seasons. In the study, we intended to determine some critical time points (such as first adult emergence, maximum adult flight, number of generations per year and flight activity in nature) in the population dynamics of Tomato Leafminer [Tuta absoluta (Meyrick) (Lepidoptera: Gelechiidae)] in Şanlıurfa. Adult population dynamic of Tomato Leafminer was monito...

  5. ANL Technical Support Program for DOE Environmental Restoration and Waste Management. Annual report, October 1990--September 1991

    Energy Technology Data Exchange (ETDEWEB)

    Bates, J.K.; Bradley, C.R.; Buck, E.C.; Cunnane, J.C.; Dietz, N.L.; Ebert, W.L.; Emery, J.W.; Feng, X.; Gerding, T.J.; Gong, M.; Hoh, J.C.; Mazer, J.J.; Wronkiewicz, D.J. [Argonne National Lab., IL (United States); Bourcier, W.L.; Morgan, L.E.; Nielsen, J.K.; Steward, S.A. [Lawrence Livermore National Lab., CA (United States); Ewing, R.C.; Wang, L.M. [New Mexico Univ., Albuquerque, NM (United States); Han, W.T.; Tomozawa, M. [Rensselaer Polytechnic Inst., Troy, MI (United States)

    1992-03-01

    This report provides an overview of progress during FY 1991 for the Technical Support Program that is part of the ANL Technology Support Activity for DOE, Environmental Restoration and Waste Management (EM). The purpose is to evaluate, before hot start-up of the Defenses Waste Processing Facility (DWPF) and the West Valley Demonstration Project (WVDP), factors that are likely to affect glass reaction in an unsaturated environment typical of what may be expected for the candidate Yucca Mountain repository site. Specific goals for the testing program include the following: (1) to review and evaluate available information on parameters that will be important in establishing the long-term performance of glass in a repository environment; (2) to perform testing to further quantify the effects of important variables where there are deficiencies in the available data; and (3) to initiate long-term testing that will bound glass performance under a range of conditions applicable to repository disposal.

  6. Verification and Validation of the PLTEMP/ANL Code for Thermal-Hydraulic Analysis of Experimental and Test Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kalimullah, M. [Argonne National Lab. (ANL), Argonne, IL (United States); Olson, Arne P. [Argonne National Lab. (ANL), Argonne, IL (United States); Feldman, E. E. [Argonne National Lab. (ANL), Argonne, IL (United States); Hanan, N. [Argonne National Lab. (ANL), Argonne, IL (United States); Dionne, B. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2015-04-07

    The document compiles in a single volume several verification and validation works done for the PLTEMP/ANL code during the years of its development and improvement. Some works that are available in the open literature are simply referenced at the outset, and are not included in the document. PLTEMP has been used in conversion safety analysis reports of several US and foreign research reactors that have been licensed and converted. A list of such reactors is given. Each chapter of the document deals with the verification or validation of a specific model. The model verification is usually done by comparing the code with hand calculation, Microsoft spreadsheet calculation, or Mathematica calculation. The model validation is done by comparing the code with experimental data or a more validated code like the RELAP5 code.

  7. Revision of the tensile database for V-Ti and V-Cr-Ti alloys tested at ANL.

    Energy Technology Data Exchange (ETDEWEB)

    Billone, M. C.

    1998-01-13

    The published database for the tensile properties of unirradiated and irradiated vanadium-based alloys tested at Argonne National Laboratory (ANL) has been reviewed. The alloys tested are in the ranges of V-(0-18)wt.%Ti and V-(4-15)wt.%Cr-(3-15)wt.%Ti. A consistent methodology, based on ASTM terminology and standards, has been used to re-analyze the unpublished load vs. displacement curves for 162 unirradiated samples and 91 irradiated samples to determine revised values for yield strength (YS), ultimate tensile strength (UTS), uniform elongation (UE) and total elongation (TE). The revised data set contains lower values for UE ({minus}5{+-}2% strain) and TE ({minus}4{+-}2% strain) than previously reported. Revised values for YS and UTS are consistent with the previously-published values in that they are within the scatter usually associated with these properties.

  8. ANL Technical Support Program for DOE Environmental Restoration and Waste Management. Annual report, October 1992--September 1993

    International Nuclear Information System (INIS)

    This report is an overview of the progress during FY 1993 for the Technical Support Program that is part of the ANL Technology Support Activity for DOE Environmental Restoration and Waste Management (EM). The purpose is to evaluate, before hot start-up of the Defense Waste Processing Facility (DWPF) and the West Valley Demonstration Project (WVDP), factors that are anticipated to affect glass reaction in an unsaturated environment typical of what may be expected for the candidate Yucca Mountain repository site. Specific goals for the testing program include the following: reviewing and evaluating available data on parameters that will be important in establishing the long-term performance of glass in a repository environment; performing tests to further quantify the effects of important variables where there are deficiencies in the available data; and initiating long-term tests to determine glass performance under a range of conditions applicable to repository disposal

  9. ANL progress on the cooperation with CNEA for the MO-99 production: Base-side digestion process

    International Nuclear Information System (INIS)

    Conversion from high-enriched uranium (HEU) to low-enriched uranium (LEU) targets for the Mo-99 production requires certain modifications of the target design, the digestion and the purification processes. ANL and the Argentine Comision Nacional de Energia Atomica (CNEA) are collaborating to overcome all the concerns caused by the conversion of the CNEA process to use LEU foil targets. A new digester with stirring system has been successfully applied for the digestion of the low burn-up U foil targets in KMnO4 alkaline media. In this paper, we report the progress on the development of the digestion procedure utilizing effective stirring and focusing on minimization of the liquid radioactive waste. (author)

  10. Verification and Validation of the PLTEMP/ANL Code for Thermal-Hydraulic Analysis of Experimental and Test Reactors

    International Nuclear Information System (INIS)

    The document compiles in a single volume several verification and validation works done for the PLTEMP/ANL code during the years of its development and improvement. Some works that are available in the open literature are simply referenced at the outset, and are not included in the document. PLTEMP has been used in conversion safety analysis reports of several US and foreign research reactors that have been licensed and converted. A list of such reactors is given. Each chapter of the document deals with the verification or validation of a specific model. The model verification is usually done by comparing the code with hand calculation, Microsoft spreadsheet calculation, or Mathematica calculation. The model validation is done by comparing the code with experimental data or a more validated code like the RELAP5 code.

  11. Steady state thermal hydraulics analysis of GHARR-1 using the pl temp/anl v 4.0 code

    International Nuclear Information System (INIS)

    Thermal-hydraulics analysis of the Ghana Research Reactor-1 (GHARR-1) has been carried out. The reactor consists of an assembly of 344 HEU vertical fuel rods cooled by natural convection. The Steady State thermal-hydraulics Analysis of the axial temperature distributions of the fuel rods, cladding surface and coolant channels in a sub-cooled boiling regime using the PLTEMP/ANL v 4.0 code has been modeled. External coupling of the Monte Carlo N Particle version 5 (MCNP5) Code provided the axial power peaking factors that sufficed the entire modeling process. At a steady state inlet temperature of 30°Celsius and pressure of 0.1237 MPa, the peak fuel and clad surface temperatures were predicted to be 110.55°Celsius and 104.25°Celsius respectively which are all below the eutectic temperature of the U-Al alloy i.e. (640°Celsius). The maximum outlet coolant temperature was predicted to be 50°Celsius giving a coolant temperature rise of 20°Celsius. Standard correlations in the PLTEMP/ANL code was used to compute the various axial properties of the fuel rods such as: coolant flow rates, coolant velocity, density, pressure drop, heat fluxes, fractional powers per rod at the margins to Onset-of-Nucleate Boiling (ONB), Minimum Departure from Nucleate Boiling ratio (MDNBR) and the Minimum Flow instability Power ratio (FIR). Most of the model predictions in this study were consistent with experimental results in the Safety Analysis Report (SAR). Outcomes of the research certify that GHARR-1 can be operated at a steady state thermal power of 30kW without compromising on safety. (au)

  12. Stibine/arsine monitoring during EV operation: summary report on preliminary tests at ANL and at LILCO

    Energy Technology Data Exchange (ETDEWEB)

    Loutfy, R.O.; Graczyk, D.G.; Varma, R.; Hayes, E.R.; Williams, F.L.; Yao, N.P.

    1981-02-01

    A series of tests was performed to monitor the evolution and dispersal of stibine and arsine from the lead-acid propulsion batteries in three different Electra-Van Model 600 vehicles operated by Argonne National Laboratory (ANL) and by the Long Island Lighting Company (LILCO). Ambient air was sampled at several locations inside the vehicles and in the garages where testing was done during charge, equalization charge, and on-the-road discharge operations. In addition, direct sampling of cell off-gases was performed with the ANL van. Interpretation of the individual test results was carried out in the context of vehicle characteristics, sampling protocol, and operating conditions. The test results demonstrated that under the test conditions only small concentrations of stibine and arsine accumulated in occupiable work areas. Measured concentrations in the vehicles and in the garages never exceeded 25% of the Threshold Limit Value-Time Weighted Average (TLV-TWA) standards. A threshold voltage for hydride production, at about 2.45 V per cell, was reflected in the results of the experiments performed during charging of the batteries. Hydride evolution rates were lower during equalization charge than during the overcharge portion of a charge cycle when the on-board charger was used in a normal operating mode. A delayed release of the metal hydrides from the battery cells was observed during on-the-road operation of the vehicles. The implications of these observations for electric vehicle (EV) operation are discussed. An engineering analysis of the generation and dispersal of the metal hydrides is presented, and equations are derived for estimating minimum ventilation requirements for the EV battery compartment and for garages housing EV operations. Recommendations are made regarding safe handling procedures for battery off-gases, procedures for conducting stibine/arsine monitoring tests and future work.

  13. Transient behavior during reactivity insertion in the Moroccan TRIGA Mark II reactor using the PARET/ANL code

    Energy Technology Data Exchange (ETDEWEB)

    Boulaich, Y., E-mail: boulaich@cnesten.org.ma [CEN-Maamora, CNESTEN, Rabat (Morocco); Nacir, B. [CEN-Maamora, CNESTEN, Rabat (Morocco); El Bardouni, T. [Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetouan (Morocco); CEN-Maamora, CNESTEN, Rabat (Morocco); Boukhal, H. [Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetouan (Morocco); Chakir, E. [LHESIR, Department of Physics, Faculty of Sciences, Kénitra (Morocco); El Bakkari, B.; El Younoussi, C. [CEN-Maamora, CNESTEN, Rabat (Morocco)

    2015-04-01

    Highlights: • PARET model for the Moroccan TRIGA MARK II reactor has been developed. • Transient behavior under reactivity insertion has been studied based on PARET code. • Power factors required by PARET code have been calculated by using MCNP5 code. • The dependence on time of the main thermal-hydraulic parameters was calculated. • Results are largely far to compromise the thermal design limits. - Abstract: A three dimensional model for the Moroccan 2 MW TRIGA MARK II reactor has been developed for thermal-hydraulic and safety analysis by using the PARET/ANL and MCNP5 codes. This reactor is located at the nuclear studies center of Mâamora (CENM), Morocco. The model has been validated through temperature measurements inside two instrumented fuel elements located near the center of the core, at various power levels, and also through the power and fuel temperature evolution after the reactor shutdown (SCRAM). The axial distributions of power factors required by the PARET code have been calculated in each fuel element rod by using MCNP5 code. Based on this thermal-hydraulic model, a safety analysis under the reactivity insertion phenomenon has been carried out and the dependence on time of the main thermal-hydraulic parameters was calculated. Results were compared to the thermal design limits imposed to maintain the integrity of the clad.

  14. Transient behavior during reactivity insertion in the Moroccan TRIGA Mark II reactor using the PARET/ANL code

    International Nuclear Information System (INIS)

    Highlights: • PARET model for the Moroccan TRIGA MARK II reactor has been developed. • Transient behavior under reactivity insertion has been studied based on PARET code. • Power factors required by PARET code have been calculated by using MCNP5 code. • The dependence on time of the main thermal-hydraulic parameters was calculated. • Results are largely far to compromise the thermal design limits. - Abstract: A three dimensional model for the Moroccan 2 MW TRIGA MARK II reactor has been developed for thermal-hydraulic and safety analysis by using the PARET/ANL and MCNP5 codes. This reactor is located at the nuclear studies center of Mâamora (CENM), Morocco. The model has been validated through temperature measurements inside two instrumented fuel elements located near the center of the core, at various power levels, and also through the power and fuel temperature evolution after the reactor shutdown (SCRAM). The axial distributions of power factors required by the PARET code have been calculated in each fuel element rod by using MCNP5 code. Based on this thermal-hydraulic model, a safety analysis under the reactivity insertion phenomenon has been carried out and the dependence on time of the main thermal-hydraulic parameters was calculated. Results were compared to the thermal design limits imposed to maintain the integrity of the clad

  15. Characterization of mixed CH-TRU waste for the WIPP Experimental Test Program conducted at ANL-W

    International Nuclear Information System (INIS)

    Argonne National Laboratory is participating in the Department of Energy's Waste Isolation Pilot Plant (WIPP) Experimental Test Program by characterizing and repackaging mixed contact-handled transuranic waste. Characterization activities include gas sampling the waste containers, visually examining the waste contents, categorizing the contents according to their gas generation potentials, and weighing the contents. The waste is repackaged from 0.21m3 (55 gallon) drums into instrumented steel test bins which can hold up to six drum-equivalents in volume. Eventually the loaded test bins will be shipped to WIPP where they will be evaluated during a five-year test program. Three test bins of inorganic solids (primarily glass) were prepared between March and September 1991 and are ready for shipment to WIPP. The characterization activities confirmed process knowledge of the waste and verified the nondestructive examinations; the gas sample analyses showed the target constituents to be within allowable regulatory limits. A new waste characterization chamber is being developed at ANL-W which will improve worker safety, decrease the potential for contamination spread, and increase the waste characterization throughput. The new facility is expected to begin operations by Fall 1992. A comprehensive summary of the project is contained herein

  16. Genes involved in the astrocyte-neuron lactate shuttle (ANLS) are specifcally regulated in cortical astrocytes following sleep deprivation in mice

    KAUST Repository

    Petit, Jean Marie

    2013-10-01

    Study Objectives: There is growing evidence indicating that in order to meet the neuronal energy demands, astrocytes provide lactate as an energy substrate for neurons through a mechanism called "astrocyte-neuron lactate shuttle" (ANLS). Since neuronal activity changes dramatically during vigilance states, we hypothesized that the ANLS may be regulated during the sleep-wake cycle. To test this hypothesis we investigated the expression of genes associated with the ANLS specifcally in astrocytes following sleep deprivation. Astrocytes were purifed by fuorescence-activated cell sorting from transgenic mice expressing the green fuorescent protein (GFP) under the control of the human astrocytic GFAP-promoter. Design: 6-hour instrumental sleep deprivation (TSD). Setting: Animal sleep research laboratory. Participants: Young (P23-P27) FVB/N-Tg (GFAP-GFP) 14Mes/J (Tg) mice of both sexes and 7-8 week male Tg and FVB/Nj mice. Interventions: Basal sleep recordings and sleep deprivation achieved using a modifed cage where animals were gently forced to move. Measurements and Results: Since Tg and FVB/Nj mice displayed a similar sleep-wake pattern, we performed a TSD in young Tg mice. Total RNA was extracted from the GFP-positive and GFP-negative cells sorted from cerebral cortex. Quantitative RT-PCR analysis showed that levels of Glut1, a-2-Na/K pump, Glt1, and Ldha mRNAs were signifcantly increased following TSD in GFP-positive cells. In GFP-negative cells, a tendency to increase, although not signifcant, was observed for Ldha, Mct2, and α-3-Na/K pump mRNAs. Conclusions: This study shows that TSD induces the expression of genes associated with ANLS specifcally in astrocytes, underlying the important role of astrocytes in the maintenance of the neuro-metabolic coupling across the sleep-wake cycle.

  17. A comparative study of the systems for neutronics calculations used in Los Alamos Scientific Laboratory (LASL) and Argonne National Laboratory (ANL)

    International Nuclear Information System (INIS)

    A comparative study of the systems for neutronics calculations used in Los Alamos Scientific Laboratory (LASL) and Argonne National Laboratory (ANL) has been performed using benchmark results available in the literature, in order to analyse tghe convenience of using the respective codes MINX/NJOY and ETOE/MC2-2 for performing neutronics calculations in course at the Divisao de Estudos Avancados. (Author)

  18. The Application of Paret/ANL Code for Accident Analysis on Inadvertent Control Rod Withdrawal for RSG GAS Reactor

    International Nuclear Information System (INIS)

    The analysis is intended to take a look the condition of safety parameters such as fuel and clad temperature, and minimum safety margin against flow instability (S) in the occurrence of inadvertent control rod withdrawal at nominal power, which is performed by PARET/ANL Code. The accident is initiated when all control rods are simultaneously withdrawn with maximum speed of 0.0564 cm/s which consequently gives maximum reactivity insertion rate σρ/σt = 2.82 x 10-4/s, resulting in the Reactor Protection System (RPS) respond to scram the reactor by dropping the control rods into the core. The primary cooling system is assumed to be in normal operation. It is postulated that the first trip signal from over power is not effective to scram the reactor, but only the second signal from Floating Limit Value eventually causes a scram with 0.5 s delays. During the occurrence of inadvertent control rods withdrawal at 30 MW of initial power, the maximum fuel and clad temperature reach 181.29oC and 137.62oC, respectively and the peak power of 37.11 MW. Meanwhile the minimum value of S reaches 2.62. Therefore, during the occurrence of control rods withdrawal at initial power of 30 MW, the integrity of fuel and clad can be maintained secure since they do not exceed the maximum limit of fuel and clad temperature of 207oC and 145oC, respectively and the minimum value of S is still higher than the design limit of 1.48 for anticipated transient

  19. ANL Doppler flowmeter

    Science.gov (United States)

    Karplus, H. B.; Raptis, A. C.; Lee, S.; Simpson, T.

    1985-10-01

    A flowmeter has been developed for measuring flow velocity in hot slurries. The flowmeter works on an ultrasonic Doppler principle in which ultrasound is injected into the flowing fluid through the solid pipe wall. Isolating waveguides separate the hot pipe from conventional ultrasonic transducers. Special clamp-on high-temperature transducers also can be adapted to work well in this application. Typical flows in pilot plants were found to be laminar, giving rise to broad-band Doppler spectra. A special circuit based on a servomechanism sensor was devised to determine the frequency average of such a broad spectrum. The device was tested at different pilot plants. Slurries with particulates greater than 70 microns (0.003 in.) yielded good signals, but slurries with extremely fine particulates were unpredictable. Small bubbles can replace the coarse particles to provide a good signal if there are not too many. Successful operation with very fine particulate slurries may have been enhanced by the presence of microbubbles.

  20. Neutronics, steady-state, and transient analyses for the Poland MARIA reactor for irradiation testing of LEU lead test fuel assemblies from CERCA : ANL independent verification results.

    Energy Technology Data Exchange (ETDEWEB)

    Garner, P. L.; Hanan, N. A. (Nuclear Engineering Division)

    2011-06-07

    The MARIA reactor at the Institute of Atomic Energy (IAE) in Swierk (30 km SE of Warsaw) in the Republic of Poland is considering conversion from high-enriched uranium (HEU) to low-enriched uranium (LEU) fuel assemblies (FA). The FA design in MARIA is rather unique; a suitable LEU FA has never been designed or tested. IAE has contracted with CERCA (the fuel supply portion of AREVA in France) to supply 2 lead test assemblies (LTA). The LTAs will be irradiated in MARIA to burnup level of at least 40% for both LTAs and to 60% for one LTA. IAE may decide to purchase additional LEU FAs for a full core conversion after the test irradiation. The Reactor Safety Committee within IAE and the National Atomic Energy Agency in Poland (PAA) must approve the LTA irradiation process. The approval will be based, in part, on IAE submitting revisions to portions of the Safety Analysis Report (SAR) which are affected by the insertion of the LTAs. (A similar process will be required for the full core conversion to LEU fuel.) The analysis required was established during working meetings between Argonne National Laboratory (ANL) and IAE staff during August 2006, subsequent email correspondence, and subsequent staff visits. The analysis needs to consider the current high-enriched uranium (HEU) core and 4 core configurations containing 1 and 2 LEU LTAs in various core positions. Calculations have been performed at ANL in support of the LTA irradiation. These calculations are summarized in this report and include criticality, burn-up, neutronics parameters, steady-state thermal hydraulics, and postulated transients. These calculations have been performed at the request of the IAE staff, who are performing similar calculations to be used in their SAR amendment submittal to the PAA. The ANL analysis has been performed independently from that being performed by IAE and should only be used as one step in the verification process.

  1. Steady-state thermal-hydraulic analysis of the Moroccan TRIGA MARK II reactor by using PARET/ANL and COOLOD-N2 codes

    International Nuclear Information System (INIS)

    Research highlights: → The COOLOD/N2 and PARET/ANL codes were used for a steady-state thermal-hydraulic and safety analysis of the 2 MW TRIGA MARK II reactor located at the Nuclear Studies Center of Maamora (CENM), Morocco. → The main objective of this study is to ensure the safety margins of different safety related parameters by steady-state calculations at full power level (2 MW). → The most important conclusion is that all obtained values of DNBR, fuel center and surface temperature, cladding surface temperature and coolant temperature across the hottest channel are largely far to compromise safety of the reactor. - Abstract: The COOLOD/N2 and PARET/ANL codes were used for a steady-state thermal-hydraulic and safety analysis of the 2 MW TRIGA MARK II reactor located at the Nuclear Studies Center of Maamora (CENM), Morocco. In order to validate our PARET/ANL and COOLOD-N2 models, the fuel center temperature as function of core power was calculated and compared with the corresponding experimental values. The comparison indicates that the calculated values are in satisfactory agreement with the measurement. The main objective of this study is to ensure the safety margins of different safety related parameters by steady-state calculations at full power level (2 MW). Therefore, we have calculated the departure from nucleate boiling ratio (DNBR), fuel center and surface temperature, cladding surface temperature and coolant temperature profiles across the hottest channel. The most important conclusion is that all obtained values are largely far to compromise safety of the reactor.

  2. Steady-state thermal-hydraulic analysis of the Moroccan TRIGA MARK II reactor by using PARET/ANL and COOLOD-N2 codes

    Energy Technology Data Exchange (ETDEWEB)

    Boulaich, Y., E-mail: boulaich@cnesten.org.m [CEN-Maamora, CNESTEN, Rabat (Morocco); Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetuan (Morocco); Nacir, B. [CEN-Maamora, CNESTEN, Rabat (Morocco); El Bardouni, T.; Zoubair, M. [Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetuan (Morocco); El Bakkari, B. [CEN-Maamora, CNESTEN, Rabat (Morocco); Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetuan (Morocco); Merroun, O. [Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetuan (Morocco); El Younoussi, C. [CEN-Maamora, CNESTEN, Rabat (Morocco); Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetuan (Morocco); Htet, A. [CEN-Maamora, CNESTEN, Rabat (Morocco); Boukhal, H. [Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetuan (Morocco); Chakir, E. [LRM/EPTN, Department of Physics, Faculty of Sciences, Kenitra (Morocco)

    2011-01-15

    Research highlights: The COOLOD/N2 and PARET/ANL codes were used for a steady-state thermal-hydraulic and safety analysis of the 2 MW TRIGA MARK II reactor located at the Nuclear Studies Center of Maamora (CENM), Morocco. The main objective of this study is to ensure the safety margins of different safety related parameters by steady-state calculations at full power level (2 MW). The most important conclusion is that all obtained values of DNBR, fuel center and surface temperature, cladding surface temperature and coolant temperature across the hottest channel are largely far to compromise safety of the reactor. - Abstract: The COOLOD/N2 and PARET/ANL codes were used for a steady-state thermal-hydraulic and safety analysis of the 2 MW TRIGA MARK II reactor located at the Nuclear Studies Center of Maamora (CENM), Morocco. In order to validate our PARET/ANL and COOLOD-N2 models, the fuel center temperature as function of core power was calculated and compared with the corresponding experimental values. The comparison indicates that the calculated values are in satisfactory agreement with the measurement. The main objective of this study is to ensure the safety margins of different safety related parameters by steady-state calculations at full power level (2 MW). Therefore, we have calculated the departure from nucleate boiling ratio (DNBR), fuel center and surface temperature, cladding surface temperature and coolant temperature profiles across the hottest channel. The most important conclusion is that all obtained values are largely far to compromise safety of the reactor.

  3. Neutronics, steady-state, and transient analyses for the Poland MARIA reactor for irradiation testing of LEU lead test fuel assemblies from CERCA: ANL independent verification results

    International Nuclear Information System (INIS)

    The MARIA reactor at the Institute of Atomic Energy (IAE) in Swierk (30 km SE of Warsaw) in the Republic of Poland is considering conversion from high-enriched uranium (HEU) to low-enriched uranium (LEU) fuel assemblies (FA). The FA design in MARIA is rather unique; a suitable LEU FA has never been designed or tested. IAE has contracted with CERCA (the fuel supply portion of AREVA in France) to supply 2 lead test assemblies (LTA). The LTAs will be irradiated in MARIA to burnup level of at least 40% for both LTAs and to 60% for one LTA. IAE may decide to purchase additional LEU FAs for a full core conversion after the test irradiation. The Reactor Safety Committee within IAE and the National Atomic Energy Agency in Poland (PAA) must approve the LTA irradiation process. The approval will be based, in part, on IAE submitting revisions to portions of the Safety Analysis Report (SAR) which are affected by the insertion of the LTAs. (A similar process will be required for the full core conversion to LEU fuel.) The analysis required was established during working meetings between Argonne National Laboratory (ANL) and IAE staff during August 2006, subsequent email correspondence, and subsequent staff visits. The analysis needs to consider the current high-enriched uranium (HEU) core and 4 core configurations containing 1 and 2 LEU LTAs in various core positions. Calculations have been performed at ANL in support of the LTA irradiation. These calculations are summarized in this report and include criticality, burn-up, neutronics parameters, steady-state thermal hydraulics, and postulated transients. These calculations have been performed at the request of the IAE staff, who are performing similar calculations to be used in their SAR amendment submittal to the PAA. The ANL analysis has been performed independently from that being performed by IAE and should only be used as one step in the verification process.

  4. Future coordinated researches by ANL (USA), INP AS RUz and INP NNC RKaz on the nuclear reactions and astrophysics

    International Nuclear Information System (INIS)

    should be peripheral and one-step mechanism of the particle transfer should dominate. In addition, the first excited states of outgoing 12C or 16O particles lie rather high (4.44 and 6.05 MeV respectively), so the interference of their excited states with the low lying states of final nuclei B will not take place. The reactions A(3He,d)B (ε3He→d+p=5.49 MeV) and A(t,d)B (ε3H→d+n=6.257 MeV) can be used also, but the energy of proton separation is somewhat more. The alpha transfer reactions A(6Li,d)B, A(7Li,t)B and A(7Be,3He)B is supposed to be used for obtaining ANCs B→ A+α because the projectiles are nuclei with weakly bound α - cluster. The possibility of implementation such experiments on ATLAS (ANL, USA) and U-150M (INP, Kazakhstan) accelerators is discussed

  5. Eastern Han Tombs at Ma'anling in Guigang City, Guangxi%广西贵港市马鞍岭东汉墓

    Institute of Scientific and Technical Information of China (English)

    广西壮族自治区文物工作队

    2002-01-01

    In December 1996-January 1997, three Eastern Han tombs at Ma'anling in Guigang City were excavated by the Guangxi Zhuang Autonomous Region Archaeological Team. Tomb M1 is a wooden-chambered rectangular earth shaft, M2 has a similar pit but no chamber, M3 is paved with bricks on the bottom, and each of them has a slanting tomb-passage. Among the funeral objects pottery vessels come first in number, bronzes next, and then some irons, silver articles and other artifacts. The pottery belongs mainly to the ding tripod, jar, pot, vase, gui food container, lian toilet box, bowl, hill incense burner, lamp, and house, well, granary and kitchen range molds; and the bronzes, to the bowl, dish, mirror and belt hook.

  6. Neutronic, steady-state, and transient analyses for the Kazakhstan VVR-K reactor with LEU fuel: ANL independent verification results

    Energy Technology Data Exchange (ETDEWEB)

    Hanan, Nelson A. [Argonne National Lab. (ANL), Argonne, IL (United States); Garner, Patrick L. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2015-08-01

    Calculations have been performed for steady state and postulated transients in the VVR-K reactor at the Institute of Nuclear Physics (INP), Kazakhstan. (The reactor designation in Cyrillic is BBP-K; transliterating characters to English gives VVR-K but translating words gives WWR-K.) These calculations have been performed at the request of staff of the INP who are performing similar calculations. The selection of the transients considered started during working meetings and email correspondence between Argonne National Laboratory (ANL) and INP staff. In the end the transient were defined by the INP staff. Calculations were performed for the fresh low-enriched uranium (LEU) core and for four subsequent cores as beryllium is added to maintain critically during the first 15 cycles. These calculations have been performed independently from those being performed by INP and serve as one step in the verification process.

  7. ANL的2Q-LEBT装置的进展报告%Status of the 2Q-LEBT Facility at ANL

    Institute of Scientific and Technical Information of China (English)

    R.H.Scott; V.N.Asseev; T.V.Kulevoy; P.N.0stroumov; E.A.Poklonskaya; M.Sengupta; N.E.Vinogradov

    2007-01-01

    The concept for a 2 charge state injector for a "RIA type" accelerator has been presented.Progress toward an operational prototype 2Q-LEBT system at Argonne National Laboratory(ANL)is under way.The existing BIE 100 all permanent magnet ECR has been placed on a high voltage platform capable of a combined>100kV with q/m separation at ground level.Remote control of the devices on the platform has been implemented.Other components of the facility are currently being tested.The components of an achromatic bending system are currently being procured.This paper will present recent work at the facility as well as preliminary development of solid materials using the BIE 100.

  8. Transient analyses for the Uzbekistan VVR-SM reactor with IRT-3M HEU fuel and IRT-4M LEU fuel : ANL independent verification results.

    Energy Technology Data Exchange (ETDEWEB)

    Garner, P. L.; Hanan, N. A.; Nuclear Engineering Division

    2007-09-24

    Calculations have been performed for postulated transients in the VVR-SM Reactor at the Institute of Nuclear Physics (INP) of the Academy of Sciences in the Republic of Uzbekistan. (The reactor designation in Cyrillic is BBP-CM; transliterating characters to English gives VVRSM but translating words gives WWR-SM.) These calculations have been performed at the request of staff of the INP who are performing similar calculations. The transients considered were established during working meetings between Argonne National Laboratory (ANL) and INP staff during summer 2006 [Ref. 1], subsequent email correspondence, and subsequent staff visits. Calculations were performed for the current high-enriched uranium (HEU) core, the proposed low-enriched uranium (LEU) core, and one mixed HEU-LEU core during the transition. These calculations have been performed independently from those being performed by INP and serve as one step in the verification process.

  9. Transient analyses for the Uzbekistan VVR-SM reactor with IRT-3M HEU fuel and IRT-4M LEU fuel : ANL independent verification results

    International Nuclear Information System (INIS)

    Calculations have been performed for postulated transients in the VVR-SM Reactor at the Institute of Nuclear Physics (INP) of the Academy of Sciences in the Republic of Uzbekistan. (The reactor designation in Cyrillic is BBP-CM; transliterating characters to English gives VVRSM but translating words gives WWR-SM.) These calculations have been performed at the request of staff of the INP who are performing similar calculations. The transients considered were established during working meetings between Argonne National Laboratory (ANL) and INP staff during summer 2006 [Ref. 1], subsequent email correspondence, and subsequent staff visits. Calculations were performed for the current high-enriched uranium (HEU) core, the proposed low-enriched uranium (LEU) core, and one mixed HEU-LEU core during the transition. These calculations have been performed independently from those being performed by INP and serve as one step in the verification process

  10. Status of Undergrowth Economy and Relevant Measures in Daxing'anling%大兴安岭发展林下经济现状与措施

    Institute of Scientific and Technical Information of China (English)

    宋文军; 陈静

    2012-01-01

    大兴安岭地区林下经济前景广阔,潜力巨大,并关系到该区能否成功的实现林业经济转型。因而,如何整合林下资源,因势利导的推进全区林下经济的协调发展,成为发展林下经济的关键所在。目前适合于大兴安岭地区林下发展的产业较多,可以概括为六大类:食用菌、浆果、坚果、北药、林下养殖、森林野菜等。根据该区基本情况,发展林下经济应遵守一些基本原则:坚持保护优先、持续发展的原则,坚持因地制宜、合理布局的原则,坚持科技引导、集约化经营的原则,坚持分类指导、分区施策的原则,坚持经营利用、产业化开发的原则,坚持规范管理、有序经营的原则等。根据大兴安岭地区的实际情况,提出了发展林下经济的若干建议,以期促进该区林下经济得到良性、健康、可持续的发展。%Daxing'anling has a broad undergrowth economy prospect, with huge potential, which concerns whether Daxing'anling area can successfully realize forestry economic transformation. Thus, how to integrate undergrowth resources and promote the coordinated development of undergrowth economy of the whole area by properly guiding the trend have become the key to developing undergrowth economy. Currently, there are numerous industries that are suitable for undergrowth development in l)axing'anling area, and they can be summarized as six major categories, edible mushrooms, berries, nuts, north medicine, under-tree breeding and wild forest vegetables. According to the basic situation, it is necessary to comply with some basic principles to develop undergrowtheconomy such as sticking to the principle of protection first and sustainable development, sticking to the principle of full use of local conditions and rational layout, sticking to the principle of scientific and technological guidance and intensive management, sticking to the principle of classified

  11. Accretion, underplating and exhumation along a subduction interface: From subduction initiation to continental subduction (Tavşanlı zone, W. Turkey)

    Science.gov (United States)

    Plunder, Alexis; Agard, Philippe; Chopin, Christian; Pourteau, Amaury; Okay, Aral I.

    2015-06-01

    We herein reappraise the pressure-temperature (PT) evolution of the high-pressure and low-temperature (HP-LT) Tavşanlı zone (western Turkey) in order to (i) better characterize rock units exhumed along a cooling subduction interface, from birth to steady state and (ii) constrain exhumation and detachment dynamics, as well as mechanical coupling between plates. Based on PT estimates and field observations three oceanic complexes are recognized between the HP-LT continental margin and the obducted ophiolite, with PT estimates ranging from incipient metamorphism to blueschist-facies conditions. PT conditions for the continental unit are reappraised to 24 kbar and ~ 500 °C on the basis of pseudosection modelling and Raman spectroscopy on carbonaceous material. A tentative reconstruction of the subduction zone evolution is proposed using available radiometric and palaeogeographic data and recent thermomechanical modelling. Both PT conditions and field observations point out to the slicing of km-sized units at different preferred depths along the subduction interface, thus providing constraints on the dynamics of accretion and underplating. In particular, the comparison of PT estimates for the Tavşanlı zone and for other broadly similar fossil subduction settings (i.e., Oman, Corsica, New Caledonia, Franciscan, Schistes Lustrés) suggests that units are detached preferentially from the slab at specific depths of 30-40 km (i.e., downdip of the seismogenic zone) and ~ 80 km. We propose that these depths are controlled by major changes in mechanical coupling along the plate interface, whereas exhumation through time would rather be controlled by large-scale geodynamic boundary conditions.

  12. Argonne National Laboratory (ANL) Progress in Minimizing Effects of LEU conversion on calcination of fission product 99Mo acid waste solution

    International Nuclear Information System (INIS)

    A partnership between Argonne National Laboratory (ANL), MDS Nordion (MDSN), Atomic Energy Canada Limited (AECL) and SGN (France) has addressed the conversion of the MAPLE Reactor 99Mo production process from high-enriched uranium (HEU) targets to low-enriched uranium (LEU) targets. One effect of the conversion would be to increase the amount of solid uranium waste five-fold; we have worked to minimize the effect of the additional waste on the overall production process and, in particular, solid waste storage. Two processes were investigated for the treatment of the uranium-rich acidic waste solution: direct calcination, and oxalate precipitation as a prelude to calcination. Direct calcination generates a dense UO3 solid that should allow a significantly greater amount of uranium in one waste container than is planned for the HEU process, but doing so results in undesirable sputtering. These results suggest that direct calcination could be adapted for use with LEU targets without a large effect on the uranium waste treatment procedures. The oxalate-calcination generates a lower-density granular U3O8 product; sputtering is not significant during calcination of the uranyl oxalate precipitate. A physical means to densify the product would need to be developed to increase the amount of uranium in each waste container. Future work will focus on the specific chemical reactions that occur during the direct and oxalate calcination processes. (author)

  13. Structure of the D-alanylgriseoluteic acid biosynthetic protein EhpF, an atypical member of the ANL superfamily of adenylating enzymes

    Energy Technology Data Exchange (ETDEWEB)

    Bera, A.K.; Robinson, H.; Atanasova, V.; Gamage, S.; Parsons, J. F.

    2010-06-01

    The structure of EhpF, a 41 kDa protein that functions in the biosynthetic pathway leading to the broad-spectrum antimicrobial compound D-alanylgriseoluteic acid (AGA), is reported. A cluster of approximately 16 genes, including ehpF, located on a 200 kbp plasmid native to certain strains of Pantoea agglomerans encodes the proteins that are required for the conversion of chorismic acid to AGA. Phenazine-1,6-dicarboxylate has been identified as an intermediate in AGA biosynthesis and deletion of ehpF results in accumulation of this compound in vivo. The crystallographic data presented here reveal that EhpF is an atypical member of the acyl-CoA synthase or ANL superfamily of adenylating enzymes. These enzymes typically catalyze two-step reactions involving adenylation of a carboxylate substrate followed by transfer of the substrate from AMP to coenzyme A or another phosphopantetheine. EhpF is distinguished by the absence of the C-terminal domain that is characteristic of enzymes from this family and is involved in phosphopantetheine binding and in the second half of the canonical two-step reaction that is typically observed. Based on the structure of EhpF and a bioinformatic analysis, it is proposed that EhpF and EhpG convert phenazine-1,6-dicarboxylate to 6-formylphenazine-1-carboxylate via an adenylyl intermediate.

  14. Argonne National Laboratory – IAEA Coordinated Research Project on Developing Techniques for Small-Scale Indigenous 99Mo Production Using LEU Fission or Neutron Activation [Country report: United States of America - ANL

    International Nuclear Information System (INIS)

    Argonne National Laboratory (ANL) in the United States was active in the Consultancy Meeting that defined the scope of this CRP and has been involved from the beginning as an Agreement Holder. ANL’s major role in the CRP was providing two technologies free of charge, namely: (1) the annular LEU-foil target and, (2) the LEU-Modified Cintichem process. In addition to providing a range of documents describing the fabrication, irradiation history, and disassembly of the LEU-foil target; procedures and QC for the LEU-Modified Cintichem process; and guides describing handling of radioactive materials and gamma and alpha counting of radioactive samples, ANL also worked with Indonesia to hold a workshop demonstrating all aspects of the technology for the two technologies

  15. Relation of Market Where Gold Supply And Demand is Intensive With Finance Sector and Analyze Of Present Market Structure in Terms Of Socio-Economic: A Study Based On Survey in Şanlıurfa and in the Region

    Directory of Open Access Journals (Sweden)

    Mehmet Cihangir

    2010-03-01

    Full Text Available One of the provinces where gold is purchased and sold mostly is Şanlıurfa. Especially trading of gold mostly in some special days following İstanbul and Ankara has made necessary that jewelry sector in this province where gold is purchased and sold is put under the scope and thereby examination of the contribution of gold to region economy as well as its other aspects. Within this scope a detailed questionnaire study to search gold and jewelry sector in Şanlıurfa in point of social, cultural and economical effects have been carried out and it has been aimed to explain these effectsdirectly from explanations of parties of incident. Considering the inevitability of emergence of some problems in a region where such extensive sale and purchase is made, the problems seen mostly have been determined and proposals regarding the solution of these have been made. In addition it has also been aimed to observe perception manner of gold and its contribution to region economy as a investment vehicle in the region. Especially the damage of misleading of credit card in sector has been tried to determine and made solution recommendations to the problem. It has been pointed out on the benefits in case the gold called mattress and considered its effect to economy is little is gained to Şanlıurfa economy.

  16. Structure of the d-alanylgriseoluteic acid biosynthetic protein EhpF, an atypical member of the ANL superfamily of adenylating enzymes

    Energy Technology Data Exchange (ETDEWEB)

    Bera, Asim K.; Atanasova, Vesna [Center for Advanced Research in Biotechnology, The University of Maryland Biotechnology Institute, 9600 Gudelsky Drive, Rockville, MD 20850 (United States); Gamage, Swarna [Auckland Cancer Society Research Centre, School of Medicine, Faculty of Medical and Health Sciences, University of Auckland, Auckland (New Zealand); Robinson, Howard [Biology Department, Brookhaven National Laboratory, Upton, NY 11973 (United States); Parsons, James F., E-mail: parsonsj@umbi.umd.edu [Center for Advanced Research in Biotechnology, The University of Maryland Biotechnology Institute, 9600 Gudelsky Drive, Rockville, MD 20850 (United States)

    2010-06-01

    The structure of EhpF from P. agglomerans has been solved alone and in complex with phenazine-1,6-dicarboxylate. Apo EhpF was solved and refined in two different space groups at 1.95 and 2.3 Å resolution and the EhpF–phenazine-1,6-dicarboxylate complex structure was determined at 2.8 Å resolution. The structure of EhpF, a 41 kDa protein that functions in the biosynthetic pathway leading to the broad-spectrum antimicrobial compound d-alanylgriseoluteic acid (AGA), is reported. A cluster of approximately 16 genes, including ehpF, located on a 200 kbp plasmid native to certain strains of Pantoea agglomerans encodes the proteins that are required for the conversion of chorismic acid to AGA. Phenazine-1,6-dicarboxylate has been identified as an intermediate in AGA biosynthesis and deletion of ehpF results in accumulation of this compound in vivo. The crystallographic data presented here reveal that EhpF is an atypical member of the acyl-CoA synthase or ANL superfamily of adenylating enzymes. These enzymes typically catalyze two-step reactions involving adenylation of a carboxylate substrate followed by transfer of the substrate from AMP to coenzyme A or another phosphopantetheine. EhpF is distinguished by the absence of the C-terminal domain that is characteristic of enzymes from this family and is involved in phosphopantetheine binding and in the second half of the canonical two-step reaction that is typically observed. Based on the structure of EhpF and a bioinformatic analysis, it is proposed that EhpF and EhpG convert phenazine-1,6-dicarboxylate to 6-formylphenazine-1-carboxylate via an adenylyl intermediate.

  17. Structure of the d-alanylgriseoluteic acid biosynthetic protein EhpF, an atypical member of the ANL superfamily of adenylating enzymes

    International Nuclear Information System (INIS)

    The structure of EhpF from P. agglomerans has been solved alone and in complex with phenazine-1,6-dicarboxylate. Apo EhpF was solved and refined in two different space groups at 1.95 and 2.3 Å resolution and the EhpF–phenazine-1,6-dicarboxylate complex structure was determined at 2.8 Å resolution. The structure of EhpF, a 41 kDa protein that functions in the biosynthetic pathway leading to the broad-spectrum antimicrobial compound d-alanylgriseoluteic acid (AGA), is reported. A cluster of approximately 16 genes, including ehpF, located on a 200 kbp plasmid native to certain strains of Pantoea agglomerans encodes the proteins that are required for the conversion of chorismic acid to AGA. Phenazine-1,6-dicarboxylate has been identified as an intermediate in AGA biosynthesis and deletion of ehpF results in accumulation of this compound in vivo. The crystallographic data presented here reveal that EhpF is an atypical member of the acyl-CoA synthase or ANL superfamily of adenylating enzymes. These enzymes typically catalyze two-step reactions involving adenylation of a carboxylate substrate followed by transfer of the substrate from AMP to coenzyme A or another phosphopantetheine. EhpF is distinguished by the absence of the C-terminal domain that is characteristic of enzymes from this family and is involved in phosphopantetheine binding and in the second half of the canonical two-step reaction that is typically observed. Based on the structure of EhpF and a bioinformatic analysis, it is proposed that EhpF and EhpG convert phenazine-1,6-dicarboxylate to 6-formylphenazine-1-carboxylate via an adenylyl intermediate

  18. Revised ANL-reported tensile data for unirradiated and irradiated (FFTF, HFIR) V-Ti and V-Cr-Ti alloys

    Energy Technology Data Exchange (ETDEWEB)

    Billone, M.C. [Argonne National Lab., IL (United States)

    1998-03-01

    The tensile data for all unirradiated and irradiated vanadium alloys samples tested at Argonne National Laboratory (ANL) have been critically reviewed and, when necessary, revised. The review and revision are based on reanalyzing the original load-displacement strip chart recordings by a methodology consistent with current ASTM standards. For unirradiated alloys (162 samples), the revised values differ from the previous values as follows: {minus}11{+-}19 MPa ({minus}4{+-}6%) for yield strength (YS), {minus}3{+-}15 MPa ({minus}1{+-}3%) for ultimate tensile strength (UTS), {minus}5{+-}2% strain for uniform elongation (UE), and {minus}4{+-}2% strain for total elongation (TE). Of these changes, the decrease in {minus}1{+-}6 MPa (0{+-}1%) for UTS, {minus}5{+-}2% for UE, and {minus}4{+-}2% for TE. Of these changes, the decrease in UE values for alloys irradiated and tested at 400--435 C is the most significant. This decrease results from the proper subtraction of nongauge-length deformation from measured crosshead deformation. In previous analysis of the tensile curves, the nongauge-length deformation was not correctly determined and subtracted from the crosshead displacement. The previously reported and revised tensile values for unirradiated alloys (20--700 C) are tabulated in Appendix A. The revised tensile values for the FFTF-irradiated (400--600 C) and HFIR-irradiated (400 C) alloys are tabulated in Appendix B, along with the neutron damage and helium levels. Appendix C compares the revised values to the previously reported values for irradiated alloys. Appendix D contains previous and revised values for the tensile properties of unirradiated V-5Cr-5Ti (BL-63) alloy exposed to oxygen.

  19. Guide to computing at ANL

    Energy Technology Data Exchange (ETDEWEB)

    Peavler, J. (ed.)

    1979-06-01

    This publication gives details about hardware, software, procedures, and services of the Central Computing Facility, as well as information about how to become an authorized user. Languages, compilers' libraries, and applications packages available are described. 17 tables. (RWR)

  20. 小兴安岭野生药用植物资源调查与评价%Investigation and Evaluation of Wild Medicinal Plants Resources in Xiaoxing' anling Mountains

    Institute of Scientific and Technical Information of China (English)

    程海涛; 贝雷; 梁启超; 刘德江; 罗志文; 周清波; 刘娟

    2012-01-01

    In order to find out the basic situation of the wild resources of medicinal plants in Xiaoxing' anling Mountains, literature survey, field survey and interviews were used, and the results were put into the database.The analysis showed there were wild medicinal vascular plants of 98 families 326 genera and 574 species in Xiaoxing' anling Mountains, of which 6 families 7 genera 16 species belonged to fern, 2 families 4 genera 6 species belonged to gymnosperms, and 90 families 315 genera 552 species belonged to angiosperm; and from the species composition of plant families and genera composition, biological learning and flora distribution, all showed different resource value.Finally people should pay attention to scientific development and utilization and protection of the medicinal vascular plants resources in Xiaoxing' anling Mountains.%为摸清小兴安岭地区野生药用植物资源的基本情况,采用文献查阅、现场调查及访问等手段进行调查,将结果录入数据库进行分析评价.结果表明:小兴安岭地区共有野生药用维管植物98科326属574种,其中蕨类植物6科7属16种,裸子植物2科4属6种,被子植物90科315属552种;且在植物的种类组成、科属构成、生物学习性及植物的区系分布等方面均表现出不同的资源价值.今后要注意科学开发利用与保护.

  1. 大兴安岭不同植被火后NDVI恢复过程%NDVI Recovery Process for Post-Fire Vegetation in Daxing’anling

    Institute of Scientific and Technical Information of China (English)

    苗庆林; 田晓瑞; 赵凤君

    2015-01-01

    和火烧强度对火烧迹地 NDVI恢复特征的影响显著,且火烧强度对火后植被恢复的影响更关键,但二者交互影响不显著。未过火区NDVI平均值为0.8012,波动范围为-3.3%~3.4%,过火区dNDVI的变化约25%是由气象因子引起的,其他主要源于植被变化。dNDVI指标可以很好地反映火烧前后植被指数变化,有较好的时序性和空间可获取性,对火烧迹地恢复过程有指示作用。%Objective]The remote sensing technology was used to monitor the vegetation restoration after fire,providing a scientific base for carrying out restoration measures in burned areas. The normalized difference vegetation index ( NDVI) is an important index to reflect the growth condition and distribution of vegetation. It has been proved in previous studies that this index has a significant correlation with vegetation coverage. Thus the increasing biomass and the vegetation coverage in burned areas can be monitored through the satellite remote sensing images.[Method]The Songling burned area,which was burned in spring of 2006,in Daxing’anling was selected as a case study. A series of NDVI data before and after the fire,which were extracted from the MODIS data,and the field investigation data were used to analyze the relationships between vegetation characteristics after fire,burned severity and vegetation types. Data of NDVI in the burned area were extracted before and just after the fire, and the fire severity was classified using the supervised classification method. The maximum NDVI in the same date of August in 2003 -2005 was used as the contrast to analyze the vegetation index changes on the time series. [Result]Low,moderate and high burning severities were accounted for 28. 93%,40. 1% and 30. 97% burned area,respectively. The dominated vegetation types with high-burning severity were evergreen coniferous forest,broadleaf and conifer mixed forest,and brushwood,which were accounted for 50. 37%, 52

  2. 小兴安岭不同林型的昆虫多样性%Insect Diversity of Different Forest Types in Xiaoxing’anling Mountains

    Institute of Scientific and Technical Information of China (English)

    马玲; 问荣荣; 焦玥; 刘雪英; 张静; 刘哲强; 顾伟; 满子源; 张曼胤

    2016-01-01

    Objective]This research aims at providing theory and scientific evidence for the forest sustainable development,management and biodiversity conservation in Liangshui Nature Reserve,Xiaoxing ’anling Mountains,by surveying the responsion of the insect community to the ecological environment of six forest types. [Method]To systematically study the diversity and structure of insect community in Liangshui Nature Reserve, the structure, characteristic indexes of diversity,temporal dynamics,stability,principal components and similarity were investigated by the sweep-net,shaking-off and observation methods from May 2013 to September 2013,in the present study. Sample locations included spruce plantations ( YR ) ,natural secondary birches forest ( B ) ,Korean pine plantation ( HR ) , linden-Korean pine (DY),picea-Korean pine (YY) and maple birch-Korean pine forest(FY). [Result]A total of 4, 599 insects belonging to 188 species,67 families and 9 orders,were collected in the six forest types,among which Hymenoptera and Diptera were the dominant groups. The insect diversity indexes in the six forest types were relatively high. The diversity index and evenness index in YR and YY were higher,while the dominant concentration were lower than that in other forest type. In all sample locations,the diversity index ( H') of the insect community had significantly consistent seasonal variation trend was with the evenness index ( J ) ( r =0. 708 ~0. 955 ,P YR > B > FY > DY > HR,while,the Sn/Sp ratio showed YR=HR > FY > B > YY > DY. The above results showed that the insect community stability was higher in YR and YY,but lower in HR and DY. In forest insect communities of every forest type,defoliator insect community was always the most divers. In YR,the individual number of neutral insects was most divers. While,in YR,the individual number of phytophagous insects was the most. In other four forest types,the individual number of predatory insects was always the most. The principal

  3. The supply and demand functions for Turkey’s manufacturing industry: Simultaneous equation systemsTürkiye’nin imalat sanayi ihracat ve ithalatının talep ve arz fonksiyonu: Eşanlı denklem modeli

    Directory of Open Access Journals (Sweden)

    Kübra Önder

    2016-01-01

    Full Text Available Foreign trade policies applied to achieve economic growth and structural changes in the economies have an important role. The applications of these policies to determination of the direction, composition, and volume of exports and imports have affected on the price and income elasticities of exported and imported goods. Therefore, the export and the import policies must be analyzed with regards to the price and income elasticities. Considering the studies done so far, econometric analysis of supply and demand functions of export and import are generally seen analyzed based on a single equation model. Also simultaneous relationship between the supply and demand is mostly ignored. For this reason, the major aim of this study is to examine the simultaneous relationship between the supply and demand functions of export and import of manufacturing industry by using Two Stage Least Squares Method. According to results of estimation income and price elasticities for supply and demand of import are found compatible with the theory. Both in export and import demand equation of manufacturing, income and price elasticities are found positive and negative respectively. And also export and import supply elasticities for manufacturing are compatible with the theoretical expectations.   Özet Ekonominin büyümesi ve yapısal değişiminde, dış ticaret politikalarının önemli bir yeri vardır. İhracat ve ithalatın yönü, hacmi ve kompozisyonunu belirlemek amacıyla alınan kararlar, malların fiyat ve gelir esnekliklerine etkide bulunmaktadır. Bu nedenle bir ülkenin ihracat ve ithalat rejimi incelenirken, fiyat ve gelir esneklikleri de dikkate alınmalıdır. Bugüne kadar yapılan çalışmalar gözden geçirildiğinde, genellikle ihracat ve ithalat arz ve talep fonksiyonlarının ekonometrik analizinin tek denklemli model temel alınarak incelendiği görülmektedir. İhracat arz ve talep fonksiyonları arasındaki eşanlı gelir ve fiyat ili

  4. 大兴安岭低质林改造后土壤肥力综合评价%Comprehensive Evaluation of Soil Fertility after Transformation of the Low-Quality Forest in the Daxing' anling Mountains

    Institute of Scientific and Technical Information of China (English)

    纪浩; 董希斌

    2012-01-01

    This study studied the changes of soil physical and chemical properties and carbon flux of broadleaved mixed secondary growth stands and birch coppice low-quality forests after clearcutting with various bandwidths in the Daxing' anling Mountains. Pinus sibirica, Pinus sylvestris var. mongolica and Larix gmelinii were planted after cutting. An improved AHP method was used for comprehensively evaluating the sites' fertility after the treatments. Results showed that the soil fertility quality index was higher than the control site for all treated sites except the broadleaved secondary P. sibirica stands in the 6 m cutting strip, where the soil fertility index was slightly less than the control site. In all the low-yield broadleaved secondary stand improvement treated sites, the soil fertility quality index of the site with the L. gmelinii stand planted in the 14 meter cutting strip showed the highest value of 0. 744. In the sites after clearcutting birch coppice low-quality forests, P. sylvestris var. mongolica stands in the 14 meter cutting strip had the highest soil quality index of 0.617. According to the Spearman correlation analysis, major factors affecting soil fertility include soil organic matter, total nitrogen and hydrolysis phosphorus content.

  5. The Forest Fire Prevention Infrastructre Construction and Countermeasures in the North Daxing′anling Mountains%大兴安岭北部林区森林防火基础设施建设成效及对策

    Institute of Scientific and Technical Information of China (English)

    谢振光

    2014-01-01

    The forest fire control infrastructure project in the forest region of the north Daxing′anling mountains is the biggest forest fire control in frastructure development project invested by the state in the state-owned forest areas since the founding of the P.R.China.This paper introduces the basic situation of the project construction,summarizes the main construction achievements,analyzes the existing issues and puts forward some countermeasures and suggestions.%大兴安岭北部林区森林防火基础设施建设项目是建国后国家一次性用于国有林区森林防火投资最大的基础设施建设工程。介绍了该项目建设的基本情况,总结了主要建设成效,分析了存在问题,提出了相关对策建议。

  6. Major results on the development of high density U-Mo fuel and pin-type fuel elements executed under the Russian RERTR program and in cooperation with ANL (USA)

    International Nuclear Information System (INIS)

    VNIINM is active participant of 'Russian program on Reduced Enrichment for Research and Test Reactors'. Institute Works in two main directions: 1) development of new high-density fuels (HDF) and 2) development of new design of fuel elements with LEU. The development of the new type fuel element is carried out both for existing reactors, and for developing new advanced reactors. The 'TVEL' concern is coordinator of works of this program. The majority enterprises of branch (NIIAR, PIYaF, RRC KI, NZChK) take part in this work. Since 2000 these works are being conducted in cooperation with Argonne National Laboratory (USA) within the RERTR program under VNIINM with ANL contract. At the present, a large set of pre-pile investigations has been completed. All necessary fabrication procedures have been developed for utilization of U-Mo dispersion fuel in Russian-designed research reactors. For irradiation tests the pin-type mini-fuel elements with HDF dispersion fuel with LEU and the uranium density equaled to 4,0 and 6,0 g/cm3 (up to 40 vol.%) have been manufactured. Their irradiation began in August 2003 in the MIR reactor (NIIAR, Dimitrovgrad). A large set of works for preparation of lifetime tests (WWR-M reactor in Gatchina) of two full-scale fuel assemblies with new pin-type fuel elements on basis LEU UO2-Al and UMo-Al fuels has been completed. The in-pile tests of fuel assemblies began in September 2003. The summary of important results of performed works and their near-term future are presented in paper. (author)

  7. The EPRI Laboratory experiments at ANL

    International Nuclear Information System (INIS)

    The vaporization of core-concrete mixtures is being measured using a transpiration method. Mixtures of stainless steel, concrete (limestone or basaltic) and urania (doped with La2O3, SrO, BaO, and ZrO2) are vaporized at 2150 - 2400 K from a zirconia crucible into flowing He - 6% H2 gas. Up to 600 ppM H2O is added to the gas to fix the partial molar free energy of oxygen in the range -420 kJ to -550 kJ. The fraction of the sample that is vaporized is determined by weight change and by chemical analyses on the condensates that are collected in an Mo condenser tube. The results are being used to test the thermodynemic data base and the underlying assumptions of computer codes used for prediction of release during the severe accident. 13 refs., 2 tabs

  8. Upgrades to the WIMS-ANL code

    International Nuclear Information System (INIS)

    The dusty old source code in WIMS-D4M has been completely rewritten to conform more closely with current FORTRAN coding practices. The revised code contains many improvements in appearance, error checking and in control of the output. The output is now tabulated to fit the typical 80 column window or terminal screen. The Segev method for resonance integral interpolation is now an option. Most of the dimension limitations have been removed and replaced with variable dimensions within a compile-time fixed container. The library is no longer restricted to the 69 energy group structure, and two new libraries have been generated for use with the code. The new libraries are both based on ENDF/B-VI data with one having the original 69 energy group structure and the second with a 172 group structure. The common source code can be used with PCs using both Windows 95 and NT, with a Linux based operating system and with UNIX based workstations. Comparisons of this version of the code to earlier evaluations with ENDF/B-V are provided, as well as, comparisons with the new libraries

  9. Upgrades to the WIMS-ANL code

    International Nuclear Information System (INIS)

    The dusty old source code in WIMS-D4M has been completely rewritten to conform more closely with current FORTRAN coding practices. The revised code contains many improvements in appearance, error checking and in control of the output. The output is now tabulated to fit the typical 80 column window or terminal screen. The Segev method for resonance integral interpolation is now an option. Most of the dimension limitations have been removed and replaced with variable dimensions within a compile-time fixed container. The library is no longer restricted to the 69 energy group structure, and two new libraries have been generated for use with the code. The new libraries are both based on ENDF/B-VI data with one having the original 69 energy group structure and the second with a 172 group structure. The common source code can be used with PCs using both Windows 95 and NT, with a Linux based operating system and with UNIX based workstations. Comparisons of this version of the code to earlier evaluations with ENDF/B-V are provided, as well as, comparisons with the new libraries. (author)

  10. Community Structure And Composing Characteristics Of Spruce Forest In Tahe Forestry Bureau Of Daxing'anling District%大兴安岭塔河林业局云杉林群落结构及组成特点分析

    Institute of Scientific and Technical Information of China (English)

    李晓平; 许铁军; 魏力

    2011-01-01

    This paper studies the community structure and composing characteristics of Spruce forest in Tahe forestry bureau of Daxing'anling district,provide scientific theory basis for the recovery of spruce forest.%研究了大兴安岭塔河林业局云杉林的群落结构及其组成特点,以其为探索云杉林的恢复途径及扩大这一树种资源提供科学的理论依据。

  11. 大兴安岭呼中区2010年森林火灾碳排放的计量估算%Estimation of Carbon Emissions from Forest Fires in 2010 in Huzhong of Daxing'anling Mountain

    Institute of Scientific and Technical Information of China (English)

    胡海清; 魏书精; 孙龙

    2012-01-01

    Biomass burning has long been recognized to release a number of important trace gas species and particulate matter to the atmosphere. Forest fire is a main disturbance factor in forest ecosystems, and an important pathway decreasing vegetation and soil carbon storage. Large amount of carbonaceous gases in forest fire can release into atmosphere, giving remarkable impacts on the atmospheric carbon balance and global climate change. Scientific and effective measurements of the carbonaceous gase emission from forest fire are important in understanding the significance of forest fire in the carbon balance and climate change. In this paper, based on Daxing'anling forest fire statistics in 2010 and various forest types of fuel load data, we conducted field surveys and indoor control-burned experiments to determine a variety of measurement parameters, and estimated emissions of the total carbon and the main carbon-containing gas of the Daxing'anling Mountain forest fire in 2010 at the stand level, by applying forest fire emissions model. Results showed that the total carbon emission from the forest fires was about 117 870. 62 t, and carbonaceous gases emissions of CO2, CO, CH4 and non-methane hydrocarbons( NMHC) were 379 606. 01 t, 23 425. 74 t, 1 081. 46 t and 758. 61 t, respectively. Our study indicated that burned area of coniferous and broad-leaved mixed forest accounted for 26. 35% , however the carbon emissions accounted for only 13. 79% of total emissions. The burned area of two Pinus pumila forests accounted for 29. 92% , and the carbon emissions accounted for 50. 35% of total emissions. We proposed the corresponding forest fire management strategy. Our studies indicated that the carbon emissions had an important impact on the regional carbon balance.%林火是森林生态系统中特殊而重要的生态因子,亦是导致植被和土壤碳储量动态变化的重要干扰因子.森林火灾的碳排放对气候变化及大气碳循环具有重要影响,科学

  12. LLNL contributions to ANL Report ANL/NE-16/6 "Sharp User Manual"

    Energy Technology Data Exchange (ETDEWEB)

    Solberg, J. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-05-06

    Diablo is a Multiphysics implicit finite element code with an emphasis on coupled structural/thermal analysis. In the SHARP framework, it is used as the structural solver, and may also be used as the mesh smoother.

  13. Development of the ANL plant dynamics code and control strategies for the supercritical carbon dioxide Brayton cycle and code validation with data from the Sandia small-scale supercritical carbon dioxide Brayton cycle test loop

    International Nuclear Information System (INIS)

    Significant progress has been made in the ongoing development of the Argonne National Laboratory (ANL) Plant Dynamics Code (PDC), the ongoing investigation and development of control strategies, and the analysis of system transient behavior for supercritical carbon dioxide (S-CO2) Brayton cycles. Several code modifications have been introduced during FY2011 to extend the range of applicability of the PDC and to improve its calculational stability and speed. A new and innovative approach was developed to couple the Plant Dynamics Code for S-CO2 cycle calculations with SAS4A/SASSYS-1 Liquid Metal Reactor Code System calculations for the transient system level behavior on the reactor side of a Sodium-Cooled Fast Reactor (SFR) or Lead-Cooled Fast Reactor (LFR). The new code system allows use of the full capabilities of both codes such that whole-plant transients can now be simulated without additional user interaction. Several other code modifications, including the introduction of compressor surge control, a new approach for determining the solution time step for efficient computational speed, an updated treatment of S-CO2 cycle flow mergers and splits, a modified enthalpy equation to improve the treatment of negative flow, and a revised solution of the reactor heat exchanger (RHX) equations coupling the S-CO2 cycle to the reactor, were introduced to the PDC in FY2011. All of these modifications have improved the code computational stability and computational speed, while not significantly affecting the results of transient calculations. The improved PDC was used to continue the investigation of S-CO2 cycle control and transient behavior. The coupled PDC-SAS4A/SASSYS-1 code capability was used to study the dynamic characteristics of a S-CO2 cycle coupled to a SFR plant. Cycle control was investigated in terms of the ability of the cycle to respond to a linear reduction in the electrical grid demand from 100% to 0% at a rate of 5%/minute. It was determined that

  14. Development of the ANL plant dynamics code and control strategies for the supercritical carbon dioxide Brayton cycle and code validation with data from the Sandia small-scale supercritical carbon dioxide Brayton cycle test loop.

    Energy Technology Data Exchange (ETDEWEB)

    Moisseytsev, A.; Sienicki, J. J. (Nuclear Engineering Division)

    2011-11-07

    Significant progress has been made in the ongoing development of the Argonne National Laboratory (ANL) Plant Dynamics Code (PDC), the ongoing investigation and development of control strategies, and the analysis of system transient behavior for supercritical carbon dioxide (S-CO{sub 2}) Brayton cycles. Several code modifications have been introduced during FY2011 to extend the range of applicability of the PDC and to improve its calculational stability and speed. A new and innovative approach was developed to couple the Plant Dynamics Code for S-CO{sub 2} cycle calculations with SAS4A/SASSYS-1 Liquid Metal Reactor Code System calculations for the transient system level behavior on the reactor side of a Sodium-Cooled Fast Reactor (SFR) or Lead-Cooled Fast Reactor (LFR). The new code system allows use of the full capabilities of both codes such that whole-plant transients can now be simulated without additional user interaction. Several other code modifications, including the introduction of compressor surge control, a new approach for determining the solution time step for efficient computational speed, an updated treatment of S-CO{sub 2} cycle flow mergers and splits, a modified enthalpy equation to improve the treatment of negative flow, and a revised solution of the reactor heat exchanger (RHX) equations coupling the S-CO{sub 2} cycle to the reactor, were introduced to the PDC in FY2011. All of these modifications have improved the code computational stability and computational speed, while not significantly affecting the results of transient calculations. The improved PDC was used to continue the investigation of S-CO{sub 2} cycle control and transient behavior. The coupled PDC-SAS4A/SASSYS-1 code capability was used to study the dynamic characteristics of a S-CO{sub 2} cycle coupled to a SFR plant. Cycle control was investigated in terms of the ability of the cycle to respond to a linear reduction in the electrical grid demand from 100% to 0% at a rate of 5

  15. Superconducting magnet systems for the ANL EPR design

    International Nuclear Information System (INIS)

    The magnet systems for the current Argonne experimental power reactor (EPR) design build on the earlier designs but incorporate a number of improvements. The toroidal field (TF) coil system consists of 16 coils of the constant tension shape, with NbTi, copper, and stainless steel as superconductor, stabilizer, and support material respectively. They are designed for 10 T operation at 3.7 K or 9 T operation at 4.2 K. Two changes from earlier designs permit a saving in material requirements. The coils are wound with the conductor in precompression and the support material in pretension so that when the coils are energized, the stainless steel experiences a stress of 60,000 psi while the copper stress does not exceed 15,000 psi. Both the copper and NbTi are graded, with higher current densities where magnetic and radiation effects are smaller. The ohmic heating (OH) coil system consists of a central solenoid plus ten other coils, all located outside the TF coils for ease of maintenance. The NbTi-copper coils are cryostable and operate at 4.2 K. The solenoid is segmented, with rings of insulation between segments to transfer the centering force from the TF coils to an insulating cylinder inside the OH solenoid. Locating the OH solenoid inside the support cylinder plus raising the central field to 8 T, enables the OH system to develop more volt-seconds than the earlier designs, even though the plasma major radius is smaller. The superconducting equilibrium field coils, also outside the TF coils, provide the field pattern required for a D-shaped plasma

  16. Pyrolysis of MSW: the current ANL/DOE program

    Energy Technology Data Exchange (ETDEWEB)

    Helt, J.E.; Henry, R.F.; Young, J.E.

    1984-01-01

    Pyrolysis of MSW is a promising method of producing useful fuels. However, several large-scale pyrolysis plants have not performed as expected, producing low yields of inferior products. Reasons for these shortcomings include a lack of understanding of the fundamental mechanisms and kinetics. Current DOE-sponsored research is directed at improved understanding of the basic thermokinetic mechanisms associated with pyrolytic converison of MSW. This work is directed not only at conventional pyrolysis, but also at the potential for product upgrading and advanced liquefaction concepts.

  17. DOE/ANL/HTRI heat exchanger tube vibration data bank

    International Nuclear Information System (INIS)

    Development of a new heat exchanger tube vibration data bank at Argonne National Laboratory is described. Comprehensive case histories on heat exchangers that have experienced tube-vibration problems and units that have been trouble-free are accumulated and this information is rendered available for evaluation, improvement, and development of vibration-prediction methods and design guidelines. Discussions include difficulties in generating a data bank, data form development, and solicitation efforts. Also included are 15 case histories upon which the data bank will be built. As new case histories are received, they will be assembled and published as addenda to this report

  18. ANL computer controlled target storage system: Status report

    International Nuclear Information System (INIS)

    Design and operation of an isotopic target storage system is described. Due to the cost and effort associated with nuclear target production, it is necessary to protect them. The storage system described was designed to protect up to 90 hydroscopic and readily oxidizing targets under vacuum of 10-6 torr. The computer controller maintains system integrity during normal use and emergency situations

  19. ANL four-meter calorimeter design and operation manual

    International Nuclear Information System (INIS)

    The four-meter fuel rod calorimetric system measures the thermal power produced by radioactive decay of fuel rods containing Pu. The Pu mass is related to the measured power through the weighted average of the product of the isotopic decay energies and the decay constants of the Pu isotopes present. U content has no effect since the thermal power produced by the U nuclides is insignificant when compared to Pu. Radiations from Pu are alpha particles and low-energy photons. This calorimeter will measure samples producing power up to 1.5 watts at a rate of one sample every 120 min. The instrument consists of a data-acquisition module made up of a microprocessor, with an 8K-byte nonvolatile memory, a control cabinet and the calorimeter chamber

  20. ANL four-meter calorimeter design and operation manual

    Energy Technology Data Exchange (ETDEWEB)

    Perry, R.B.; Lewis, R.N.; Youngdahl, G.A.; Jung, E.A.; Roche, C.T.

    1980-02-01

    The four-meter fuel rod calorimetric system measures the thermal power produced by radioactive decay of fuel rods containing Pu. The Pu mass is related to the measured power through the weighted average of the product of the isotopic decay energies and the decay constants of the Pu isotopes present. U content has no effect since the thermal power produced by the U nuclides is insignificant when compared to Pu. Radiations from Pu are alpha particles and low-energy photons. This calorimeter will measure samples producing power up to 1.5 watts at a rate of one sample every 120 min. The instrument consists of a data-acquisition module made up of a microprocessor, with an 8K-byte nonvolatile memory, a control cabinet and the calorimeter chamber. (FS)

  1. ANL small-sample calorimeter system design and operation

    Energy Technology Data Exchange (ETDEWEB)

    Roche, C.T.; Perry, R.B.; Lewis, R.N.; Jung, E.A.; Haumann, J.R.

    1978-07-01

    The Small-Sample Calorimetric System is a portable instrument designed to measure the thermal power produced by radioactive decay of plutonium-containing fuels. The small-sample calorimeter is capable of measuring samples producing power up to 32 milliwatts at a rate of one sample every 20 min. The instrument is contained in two packages: a data-acquisition module consisting of a microprocessor with an 8K-byte nonvolatile memory, and a measurement module consisting of the calorimeter and a sample preheater. The total weight of the system is 18 kg.

  2. Recent results from the ANL polarized target group

    International Nuclear Information System (INIS)

    Results are presented from p vector p vector which includes spin-spin parameters measured at the ZGS at momenta between 1 and 12 GeV/c, and center-of-mass angles between 80 and 900. The LAMPF program is reviewed, with data from Δsigma/sub L/ and Δsigma/sub T/ discussed as well as recent n vector p spin transfer measurements. 30 references

  3. ANL--LASL workshop on advanced neutron detection systems

    International Nuclear Information System (INIS)

    A two-day workshop on advanced neutron detectors and associated electronics was held in Los Alamos on April 5--6, 1979, as a part of the Argonne National Laboratory--Los Alamos Scientific Laboratory Coordination on neutron scattering instrumentation. This report contains an account of the information presented and conclusions drawn at the workshop

  4. Users guide for the ANL IBM SP1

    Energy Technology Data Exchange (ETDEWEB)

    Gropp, W.; Lusk, E.; Pieper, S.C.

    1994-10-01

    This guide presents the features of the IBM SP1 installed in the Mathematics and Computer Science Division at Argonne National Laboratory. The guide describes the available hardware and software, access policies, and hints for using the system productively.

  5. Zircon U-Pb ages and geological significance of the granitoids in the Yi'ershi region,Daxing′anling%大兴安岭伊尔施地区花岗岩锆石U-Pb 年龄及其地质意义

    Institute of Scientific and Technical Information of China (English)

    郭峰; 白志达; 李路路

    2014-01-01

    伊尔施花岗岩位于大兴安岭中段,出露面积约260km2,由中细粒二长花岗岩、中粗粒斑状正长花岗岩和中粗粒正长花岗岩三期侵入体构成。岩体侵入于石炭-二叠系地层,被晚侏罗世火山岩不整合所覆。锆石LA-ICP-MS U-Pb年龄为(226.3±1.4) Ma ,表明为晚三叠世花岗岩。花岗岩具有高硅、富碱、低钙的特征,属于弱过铝质岩石。稀土元素总量较高,轻稀土相对富集,重稀土相对亏损,Eu负异常明显。强不相容元素富集,亏损Ba、S r、P和T i。总体属于高钾钙碱性系列向碱性系列过渡的花岗岩,具有后造山花岗岩类(POG )的特征,形成于挤压造山向拉张体制转变阶段的构造环境,暗示该区受西伯利亚板块和华北板块碰撞造山作用的影响持续到三叠纪。%Yi’ershi granite located in the middle of Daxing ’anling area ,about 260 km2 .It consists of three phase intrusions , the middle-fine grained adamellite ,coarse-grained grained porphyritic orthoclase granite and coarse-grained orthoclase granite ,respectively .Pluton intruded into the Carboniferous-Permian strata ,and the Late Jurassic volcanic rocks are unconformably overlying them .Zircon LA-ICP-MS U-Pb dating ages of the pluton is (226 .3 ± 1 .4) Ma ,indicates that the Late Triassic granite .The granitoid has the characteristics of high silica ,alkali-rich ,low calcium ,belongs to the weakly peraluminous rocks .Total REE abundance is variable ,rich of HREE ,and the fractionation of LREE is more than that of HREE relatively ,and by obivious Eu anomalies .Strong incompatible elements are enrichment ,lack of Ba ,Sr ,P and Ti .Overall belong to the transition series from high-K series to calc-alkaline series granite ,shows the characteristics of typical post-orogenic granite (POG ) .It mainly formed in the transition phase from the extrusion orogenic to extensional regime tectonic environment , which suggesting the

  6. 模拟氮沉降对云冷杉红松林土壤呼吸的影响%Effects of Simulated Nitrogen Deposition on Soil Respiration in Spruce-fir-Korean Pine Forest of Xiaoxing' anling Mountains in China

    Institute of Scientific and Technical Information of China (English)

    刘博奇; 牟长城; 邢亚娟; 王庆贵

    2012-01-01

    In order to investigate the effects of simulated nitrogen deposition on soil respiration in spruce-fir-Korean pine forests, a simulated nitrogen deposition experiment was conducted in Xiaoxing' anling Mountains area in Heilongjiang Province from May to October, 2011. The experiment included the Control (0, CK ) , low-N (50 kg · hm-2 · a-1, TL) , medial-N (100 kg · hm-2 · a-1 , TM) and high-N (150 kg · hm-2 · a-1 , TH) treatment level. The results showed that the nitrogen deposition did not change the daily and seasonal variation patterns of soil respiration. Compared to Control, the TL, TM, and TH treatments increased the soil daily average respiration rates by 13. 72% , 23. 22% and 5. 12% , and 13. 98% , 18. 26% and 1. 12% for soil annul average respiration rates. Significant exponential relationship was found between soil respiration rate and soil temperature, but no significant relationship was found between the soil moisture and soil respiration rates. The Q10(the respiratory flux at one temperature over the flux at a temperature 10℃ lower) were 4. 77, 5. 71 , 6. 62 and 5. 49 for soil respiration of the CK, TL, TM, and THtreatments respectively. The findings suggested that nitrogen deposition could promote soil respiration, and increase soil respiration temperature sensitivity in spruce-fir-Korean pine forests.%2011年5月至2011年10月在黑龙江省小兴安岭云冷杉红松林内进行模拟氮沉降试验,使用便携式土壤CO2通量观测仪LI-8100测定不同氮沉降浓度CK(0)、TL (50 kg·hm-2.a-1)、TM(100 kg· hm-2·a-1)和TH(150 kg·hm-2·a-1)对土壤呼吸的影响.结果表明,氮沉降未显著改变土壤呼吸的日变化和季节性变化规律;对比CK,TL、TM和TH处理,分别使土壤日呼吸速率提高了13.72%、23.22%和5.12%,年呼吸速率提高了13.98%、18.26%和1.12%;土壤呼吸与温度呈极显著的指数相关(P <0.001),与土壤湿度无显著相关;CK,TL、TM和TH处理下,土

  7. Characteristics of Lightning Fire in Daxing'anling Forest Region from 1972 to 2005 and Its Relationships with Drought Index%1972—2005年大兴安岭林区雷击火特征及其与干旱指数的关系水

    Institute of Scientific and Technical Information of China (English)

    贾丙瑞; 周广胜; 于文颖; 方东明

    2011-01-01

    was more suitable for simulating the characteristics of lightning fires in Daxing' anling forest region than PDSI.

  8. Beam measurements of the ANL-APS linac injector test stand

    International Nuclear Information System (INIS)

    The Argonne Advanced Photon Source (APS) injection S-band linac consists of a thermionic gun, a single gap prebuncher, a constant impedance buncher with υp = 0.75 c and a 3-meter long constant gradient traveling waveguide. Results of the electron beam measurements at 56 MeV and comparison with calculations and beam simulations are presented. (author). 3 tabs., 3 figs

  9. A fifth harmonic rf bunch monitor for the ANL-APS electron linac

    International Nuclear Information System (INIS)

    The function of a fifth harmonic (14.28 GHz) bunch monitor is to provide a signal which is proportional to the electron beam bunch size. The monitoring of the rf power signal at 14.28 GHz enables the operator to optimize the rf bunching of the beam at the end of the first accelerating section where the full bunching has been formed and remains mainly constant in size throughout the rest of the electron linac. A modified version of the SLAC original bunch monitor has been fabricated and its rf properties measured. This paper describes the design and the initial measurement results

  10. ANL technical support program for DOE Office of Environmental Management. Annual report, October 1994--September 1995

    International Nuclear Information System (INIS)

    A program was established for the DOE Office of Environmental Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site. This report covers progress in FY 1995 on the following tasks: (1) Tests are ongoing to evaluate and compare the reactivity of fully radioactive glasses with that of glasses having the same compositions except for the absence of radionuclides under conditions representative of a high-level waste repository environment. Data from these tests will be used to evaluate the effect of radionuclides on the glass corrosion behavior and to determine the disposition of the radionuclides as the glass corrodes. Static dissolution tests and unsaturated tests are being conducted with several Defense Waste Processing Facility (DWPF) and West Valley Demonstration Project (WVDP) glasses. (2) A series of static dissolution tests is being performed to compare the corrosion behavior of nuclear waste glasses made with SRL 131 and SRL 202 frits at different S/V ratios. The S/V ratio affects the extent to which dissolved glass species are diluted; the solution chemistry then affects continued glass dissolution. The solutions generated in tests at high S/V ratios are conducive to the formation of alteration phases that may be deleterious to the glass. After long time periods, the glass dissolution rates of both glasses increase coincidentally with the formation of analcime and other alteration phases. However, the release of radionuclides from the glasses into solution is controlled by their individual solubilities

  11. ANL technical support program for DOE Office of Environmental Management. Annual report, October 1994--September 1995

    Energy Technology Data Exchange (ETDEWEB)

    Bates, J.K.; Buck, E.C.; Dietz, N.L.; DiSanto, T.; Ebert, W.L. [and others

    1996-07-01

    A program was established for the DOE Office of Environmental Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site. This report covers progress in FY 1995 on the following tasks: (1) Tests are ongoing to evaluate and compare the reactivity of fully radioactive glasses with that of glasses having the same compositions except for the absence of radionuclides under conditions representative of a high-level waste repository environment. Data from these tests will be used to evaluate the effect of radionuclides on the glass corrosion behavior and to determine the disposition of the radionuclides as the glass corrodes. Static dissolution tests and unsaturated tests are being conducted with several Defense Waste Processing Facility (DWPF) and West Valley Demonstration Project (WVDP) glasses. (2) A series of static dissolution tests is being performed to compare the corrosion behavior of nuclear waste glasses made with SRL 131 and SRL 202 frits at different S/V ratios. The S/V ratio affects the extent to which dissolved glass species are diluted; the solution chemistry then affects continued glass dissolution. The solutions generated in tests at high S/V ratios are conducive to the formation of alteration phases that may be deleterious to the glass. After long time periods, the glass dissolution rates of both glasses increase coincidentally with the formation of analcime and other alteration phases. However, the release of radionuclides from the glasses into solution is controlled by their individual solubilities.

  12. Lovende resultater ved ultralydvejledt anlæggelse af nerveblokade hos børn

    DEFF Research Database (Denmark)

    Lefort, Michèle Reeslev; Henneberg, Steen; Bille, Anders Bastholm;

    2011-01-01

    Nerve blocks play an increasingly important role in pediatric regional anaesthesia. The benefits are numerous compared to standard pain regimens. The use of ultrasound (US) for nerve blocks lowers the volume of local anaesthetics applied, shortens the on-set time and results in higher success rat...

  13. ANL ITER high-heat-flux blanket-module heat transfer experiments

    Energy Technology Data Exchange (ETDEWEB)

    Kasza, K.E.

    1992-02-01

    An Argonne National Laboratory facility for conducting tests on multilayered slab models of fusion blanket designs is being developed; some of its features are described. This facility will allow testing under prototypic high heat fluxes, high temperatures, thermal gradients, and variable mechanical loadings in a helium gas environment. Steady and transient heat flux tests are possible. Electrical heating by a two-sided, thin stainless steel (SS) plate electrical resistance heater and SS water-cooled cold panels placed symmetrically on both sides of the heater allow achievement of global one-dimensional heat transfer across blanket specimen layers sandwiched between the hot and cold plates. The heat transfer characteristics at interfaces, as well as macroscale and microscale thermomechanical interactions between layers, can be studied in support of the ITER engineering design effort. The engineering design of the test apparatus has shown that it is important to use multidimensional thermomechanical analysis of sandwich-type composites to adequately analyze heat transfer. This fact will also be true for the engineering design of ITER.

  14. ANL ITER high-heat-flux blanket-module heat transfer experiments. Fusion Power Program

    Energy Technology Data Exchange (ETDEWEB)

    Kasza, K.E.

    1992-02-01

    An Argonne National Laboratory facility for conducting tests on multilayered slab models of fusion blanket designs is being developed; some of its features are described. This facility will allow testing under prototypic high heat fluxes, high temperatures, thermal gradients, and variable mechanical loadings in a helium gas environment. Steady and transient heat flux tests are possible. Electrical heating by a two-sided, thin stainless steel (SS) plate electrical resistance heater and SS water-cooled cold panels placed symmetrically on both sides of the heater allow achievement of global one-dimensional heat transfer across blanket specimen layers sandwiched between the hot and cold plates. The heat transfer characteristics at interfaces, as well as macroscale and microscale thermomechanical interactions between layers, can be studied in support of the ITER engineering design effort. The engineering design of the test apparatus has shown that it is important to use multidimensional thermomechanical analysis of sandwich-type composites to adequately analyze heat transfer. This fact will also be true for the engineering design of ITER.

  15. Design for ANL 7 GeV storage ring vacuum system

    International Nuclear Information System (INIS)

    The 7-GeV Advanced Photon Source (APS) design includes a storage ring having a 1060-m circumference with the capability of accommodating 34 insertion devices (ID) and their associated photon beam lines. An additional 35 photon lines can be provided from bending magnets. The vacuum system for the storage ring is designed to maintain a beam-on operating pressure of 1n Torr or less to achieve a positron beam lifetime of approximately 20 hours. The vacuum system and it's current developmental status are described

  16. Symposium on high spin phenomena in nuclei. [ANL, March 15-17, 1979

    Energy Technology Data Exchange (ETDEWEB)

    1979-10-01

    Separate abstracts were prepared for 44 of the papers given at this symposium. Six other papers have already been cited in ERA; these papers can be located by reference to the entry CONF-790323 - in the Report Number Index. (RWR)

  17. Physics Division annual review, 1 April 1975--31 March 1976. [ANL

    Energy Technology Data Exchange (ETDEWEB)

    Garvey, G. T.

    1976-01-01

    An overview is given of Physics Division activities in the following areas: the heavy-ion booster; medium-energy physics; heavy-ion physics; low-energy charged-particle physics; accelerator operations; neutron physics; theoretical nuclear physics, and atomic and molecular physics. A bibliography of publications amounts to 27 pages. (RWR)

  18. Using the Hydra Protocol Converter for IBM full screen terminal emulation at ANL

    Energy Technology Data Exchange (ETDEWEB)

    Hinds, A.R.; Leibfritz, D.W. Lurie, G.R.; Slocum, R.E. (ed.)

    1987-11-01

    The Hydra Protocol Converter is a dedicated microprocessor that allows selected ASCII terminals and personal computers emulating ASCII terminals to use IBM 3277-type terminal full screen capabilities. Connections to Hydra through the Argonne Private Branch Exchange (PBX) provide full-screen terminal access to all the central IBM computer interactive services (CMS, MVS Sylbur, CICS, and MVS TSO). These services are more flexible and easier to use if you have full screen terminal capabilities; the Hydra provides excellent emulation of most IBM 3277 terminal features, and it displays the effects of your keystrokes immediately on your terminal screen. In addition, the Hydra permits you to transfer files between CMS and personal computers running either the Kermit or RELAY Gold programs. The Hydra communicates asynchronously at communication speeds ranging from 300 baud to 19.2 kilobaud (a baud is one bit, or binary digit, per second). Generally, use the fastest speed (baud rate) that your ADI (Asynchronous Data Interface) or modem, and terminal or terminal emulation program can sustain; the Hydra will automatically adjust to the speed you have set. There are several methods of emulating full screen IBM terminals besides using the Hydra (such as software packages). However, the Hydra is the most efficient method at Argonne. Throughout this document, all mention of full screen emulation refers to emulating IBM 3277-type terminals with the Hydra. 1 fig., 9 tabs.

  19. Using the Hydra Protocol Converter for IBM full screen terminal emulation at ANL

    Energy Technology Data Exchange (ETDEWEB)

    Hinds, A.R.; Leibfritz, D.W.; Louie, K.K.; Lurie, G.R.

    1988-11-01

    The Hydra Protocol Converter is a dedicated microprocessor that allows selected ASCII terminals, and personal computers emulating ASCII terminals, to achieve full screen capabilities similar to IBM 3277 terminals. Through the Argonne Private Branch Exchange (PBX) at extension 2-3270, you can use the Hydra for full screen terminal access to all the central IBM computer interactive services (CMS, MVS Wylbur, CICS, and MVS TSO). These services are more flexible and easier to use if you have full screen terminal capabilities; the Hydra provides excellent emulation of most IBM 3277 terminal features, and it displays the effects of your keystrokes immediately on your terminal screen In addition, the Hydra permits you to transfer files between CMS and personal computers running either the Kermit or RELAY Gold programs. The Hydra communicates asynchronously at communication speeds ranging from 300 baud to 19.2 kilobaud (a baud is one bit, or binary digit, per second). Generally, use the fastest speed (baud rate) that your ADI (Asynchronous Data Interface) or modern and terminal or terminal emulation program can sustain; the Hydra will automatically adjust to the speed you have set. However, at high speeds, the Hydra may overrun your terminal, causing missing, misplaced (garbage) characters on your display. If such characters occur, specify automatic XON/XOFF flow control or try changing to a lower communication rate (see ''Setting Your Communication Rate'' in the section of Appendix B relevant to your terminal equipment, or the chapter on your terminal.) There are several methods of emulating full screen IBM terminals besides using the Hydra (such as software packages). However, the Hydra is the most efficient method at Argonne. Throughout this document, all mention of full screen emulation refers to emulating IBM 3277-type terminals with the Hydra. 1 fig., 7 tabs.

  20. Utilizing benchmark data from the ANL-ZPR diagnostic cores program

    International Nuclear Information System (INIS)

    The support of the criticality safety community is allowing the production of benchmark descriptions of several assemblies from the ZPR Diagnostic Cores Program. The assemblies have high sensitivities to nuclear data for a few isotopes. This can highlight limitations in nuclear data for selected nuclides or in standard methods used to treat these data. The present work extends the use of the simplified model of the U9 benchmark assembly beyond the validation of keff. Further simplifications have been made to produce a data testing benchmark in the style of the standard CSEWG benchmark specifications. Calculations for this data testing benchmark are compared to results obtained with more detailed models and methods to determine their biases. These biases or corrections factors can then be applied in the use of the less refined methods and models. Data testing results using Versions IV, V, and VI of the ENDF/B nuclear data are presented for keff, f28/f25, c28/f25, and βeff. These limited results demonstrate the importance of studying other integral parameters in addition to keff in trying to improve nuclear data and methods and the importance of accounting for methods and/or modeling biases when using data testing results to infer the quality of the nuclear data files

  1. Introduction statement at the panel discussion [contributed by James L. Snelgrove, ANL

    International Nuclear Information System (INIS)

    I just wanted to say a few words about the fuel demonstration part of the RERTR program, especially about our near-term activities. In the near-term we are considering three types of demonstrations. One of those is the irradiation of individual fuel elements in the ORR. These elements are to be essentially identical to the current ORR elements except that the enrichment will be 45% and the uranium density in the fuel meat will be somewhere in the neighborhood of 42 wt %. The exact loading hasn't been determined at this time, and preliminary work is underway to determine this. I think that I should point out that we really feel that the licensing basis is already available for what we are calling near-term fuel. That basis exists because of the extensive data obtained in the development of fuel for the ATR and for the HFIR. Those two reactors plus a few others are already making use of fuels loaded to this density at, of course, 93% enrichment. We don't see any real need from a metallurgical point of view to go through the complete demonstrations again. What we are doing though is loading this fuel with an enrichment and density which will be applicable in many cases in the near term, as it was mentioned yesterday, putting it in the ORR, burning it up, and doing a reasonable amount of post-irradiation examination. This data, we think, will be useful in licensing. Dr. Kanda mentioned in a comment earlier today that through the joint study with our program the Japanese are wanting to gain certain information from these experiments. We think that the experiments can satisfy those requirements. We would also be very interested to hear from any of the rest of you, the users, those of you who have to be concerned about gaining these licensing approvals, what sorts of information might really be needed here for any near-term work. We're planning to irradiate at least some elements to the order of, I would say, 90% burnup. Now, as it turns out in these elements at this enrichment and density, 90% burnup doesn't even surpass the burnup levels that have already been demonstrated as acceptable in the 93%-enriched fuels, and, therefore, one doesn't expect to find any swelling problems or any metallurgical-type problems at all. We will go through certain postirradiation examinations, however, but unless we see the need from some of the early parts of the examinations, we don't plan extensive metallurgical examinations. For these experiments, we would encourage participation by any fuel vendor who is interested in providing a few elements. We are not talking about many, maybe the order of two or three per vendor, which could be used in this program and would then, at least, provide a look to the rest of the world at elements made by particular vendors to particular enrichments and irradiated to good burnups. The other parts of our program in the near-term have to do with whole core demonstrations, and the one that is really planned at this time is the Ford Nuclear Reactor at the University of Michigan. The primary purpose of this demonstration is to have a core in which we can investigate the physics and safety characteristics of 20%-enriched fuel and compare them with those of the 93%-enriched cores. We will also use the data for verification of our analytical methods, so that when these methods are applied in evaluating the potential of other reactors for use of reduced-enrichment fuel, one will have increased confidence in the methods. I point out, of course, that there have been other reactors run with 20%-enriched fuel. However, that fuel was used quite awhile ago, and it's difficult today to obtain the sort of data in which we are really interested. The measurements in the FNR are planned to look at detailed flux distributions in the core and reflectors and at the ends of beam ports. It is also planned to measure the typical sorts of reactor characteristics which are always necessary to show that you're meeting your technical specifications and safety requirements.. The Ford Nuclear Reactor is an NRC licensed facility, and, as such, the University of Michigan will have to obtain licensing approval from NRC. We're hoping for the full cooperation of NRC, and we've been basically told that that will be forthcoming. We certainly don't anticipate that there are any new safety issues involved. We say te basis is there, and it's up to us, in cooperation with the University of Michigan, to demonstrate to the NRC that this is true. Out of this work will then come some documents that will be very useful as reference documents for any further near-term conversions using this type of fuel. I conclude my remarks here, and I will be happy to answer any questions

  2. Demographic features of children with cerebral palsy in Şanlıurfa and neighbor counties

    OpenAIRE

    ALTINDAĞ, Özlem; SORAN, Neslihan; akcan, sAİT

    2009-01-01

    Cerebral palsy is the most common cause of disability in childhood. There are several factors in etiopathogenesis of cerebral palsy. Evaluation of etiology, the type of disease, and associated clinical features are important for the result of rehabilitation program and the participation of family. This study was planned for the determination of demographical characteristics of 50 patients with cerebral palsy from Sanliurfa and its neighbor counties.

  3. Projektrisk : en studie av svenska bygg- och anläggningsföretag

    OpenAIRE

    Ekenman, Erik; Eriksson, Daniel

    2003-01-01

    Background: Today businesses are largely structured in projects and temporary organizations. In many companies, the ability to pursue projects is decisive for the business efficiency and competitiveness. The risk literature do not discuss identification and handling ofproject risk in building- and construction companies to a large extent, which has led us to investigate how project risk can be treated and handled in Swedish building- and construction companies. Purpose: The purpose of this t...

  4. ANL-1(A) - Development of nondestructive evaluation methods for structural ceramics

    International Nuclear Information System (INIS)

    This section includes the following papers: Development of Nondestructive Evaluation Methods for Structural Ceramics; Effects of Flaws on the Fracture Behavior of Structural Ceramics; Design, Fabrication, and Interface Characterization of Ceramic Fiber-Ceramic Matrix Composites; Development of Advanced Fiber-Reinforced Ceramics; Modeling of Fibrous Preforms for CVD Infiltration; NDT of Advanced Ceramic Composite Materials; Joining of Silicon Carbide Reinforced Ceramics; Superconducting Film Fabrication Research; Short Fiber Reinforced Structural Ceramics; Structural Reliability and Damage Tolerance of Ceramic Composites for High-Temperature Applications; Fabrication of Ceramic Fiber-Ceramic Matrix Composites by Chemical Vapor Infiltration; Characterization of Fiber-CVD Matrix interfacial Bonds; Microwave Sintering of Superconducting Ceramics; Improved Ceramic Composites Through Controlled Fiber-Matrix Interactions; Evaluation of Candidate Materials for Solid Oxide Fuel Cells; Ceramic Catalyst Materials: Hydrous Metal Oxide Ion-Exchange Supports for Coal Liquefaction; and Investigation of Properties and Performance of Ceramic Composite Components

  5. Komplikationer efter anlæggelse og tilbagelægning af loopileostomi

    DEFF Research Database (Denmark)

    El-Hussuna, Alaa; Bülow, Steffen; Lauritsen, Morten

    2011-01-01

    A protective loop ileostomy is used to reduce the incidence and consequences of anastomotic failure following colorectal resection. Closure of a loop ileostomy is associated with low mortality but many studies have demonstrated high morbidity rates. The aim of this review is to examine the existing...

  6. ANL proposal for investigaton of concepts for hydrogen control under LWR accident conditions

    International Nuclear Information System (INIS)

    A proposal for investigation of concepts for hydrogen control in degraded core LWR accidents which could release significant quantities of hydrogen to the containment building is presented. This proposed work includes studies on the combustion suppression mechanisms which would involve reaction kinetics experiments with addition of chemicals or ions to scavenge the intermediate (free-radical or other) combustion products. Several additives appear promising. Also several condensed-phase system concepts presently appear attractive for the longer-term hydrogen removal systems. The work would be complementary to other current programs on hydrogen control

  7. ANL technical support program for DOE Environmental Restoration and Waste Management

    International Nuclear Information System (INIS)

    A program was established for DOE Environmental Restoration and Waste Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site. This report covers progress in FY 1992 on the following tasks: 1. A compendium of the characteristics of high-level nuclear waste borosilicate glass has been written. 2. A critical review of important parameters that affect the reactivity of glass in an unsaturated environment is being prepared. 3. A series of tests has been started to evaluate the reactivity of fully radioactive glasses in a high-level waste repository environment and compare it to the reactivity of synthetic, nonradioactive glasses of similar composition. 4. The effect of radiation upon the durability of waste glasses at a high glass surface area-to-liquid volume (SA/V) ratio and a high gas-to-liquid volume ratio will be assessed. These tests address both vapor and high SA/V liquid conditions. 5. A series of tests is being performed to compare the extent of reaction of nuclear waste glasses at various SAN ratios. Such differences in the SAN ratio may significantly affect glass durability. 6. A series of natural analogue tests is being analyzed to demonstrate a meaningful relationship between experimental and natural alteration conditions. 7. Analytical electron microscopy (AEM), infrared spectroscopys and nuclear resonant profiling are being used to assess the glass/water reaction pathway by identifying intermediate phases that appear on the reacting glass. Additionally, colloids from the leach solutions are being studied using AEM. 8. A technical review of AEM results is being provided. 9. A study of water diffusion involving nuclear waste glasses is being performed. 10. A mechanistically based model is being developed to predict the performance of glass over repository-relevant time periods

  8. EPRI [Electric Power Research Institute]/ANL investigations of MCCI [molten core-concrete interactions] phenomena and aerosol release

    International Nuclear Information System (INIS)

    A program of laboratory investigations has been undertaken at Argonne National Laboratory, under sponsorship of the Electric Power Research Institute, in which the interaction between molten core materials and concrete is studied, with particular emphasis on measurements of the magnitude and chemical species present in the aerosol releases. The experiment technique used in these investigations is direct electrical heating in which a high electric current is passed through the core debris to sustain the high-temperature melt condition for potentially long periods of time. In the scoping experiments completed to date, this technique has been successfully used for corium masses of 5 and 20 kg, generating an internal heating rate of 1 kw/kg and achieving melt temperatures of 2000C. Experiments have been performed both with a concrete base and also with a cooled base with the addition of H2/CO sparging gas to represent chemical processes in a stratified layer. An aerosol and gas sampling system is being used to collect aerosol samples. Test results are now becoming available including masses of aerosols, x-ray diffraction, and scanning electron microscope analyses

  9. Kvalitetsmanual för brandtekniska analyser vid svenska kärntekniska anläggningar

    OpenAIRE

    Nystedt, Fredrik; Frantzich, Håkan

    2011-01-01

    The report provides guidance on how to assure quality in fire safety analysis reports. The primary focus is on analyses in nuclear power plants but the report can also be used for other applications as the information can be seen as generic. The report provides a procedure to follow and targets at analytical fire safety engineering analyses. The report assumes that the reader is familiar with the basic concepts of fire safety issues. The quality guide focuses on the use of Fire...

  10. High heat load performance of an inclined crystal monochromator with liquid gallium cooling on the CHESS-ANL undulator

    International Nuclear Information System (INIS)

    Recent results for the performance of a novel double crystal monochromator subjected to high heat loads on an APS prototype undulator at the Cornell High Energy Synchrotron Source (CHESS) are presented. The monochromator was designed to achieve symmetric diffraction from asymmetric planes to spread out the beam footprint thereby lowering the incident power density. Both crystals had (111) oriented surfaces and were arranged such that the beam was diffracted from the (11 bar 1) planes at 5 KeV. Rocking curves with minimal distortion were obtained at a ring electron current of 100 mA. This corresponded to 380 Watts total power and an average power density of 40 Watts/mm2 normal to the incident beam. These results are compared to data obtained from the same crystals in the standard geometry (diffracting planes parallel to surface). The footprint area in the inclined case was three times that of the standard case. We also obtained rocking curve data for the (333) reflection at 15 KeV for both standard and inclined cases, and these data also showed a minimal distortion only for the inclined case. In addition, thermal data were obtained via infrared pyrometry. Liquid gallium flow rates of up to 2 gallons per minute were investigated. The diffraction data revealed a dramatically improved performance for the inclined crystal case

  11. Convertidores anlógico-digitales de altas prestaciones: modelos y diseño microelectrónico

    OpenAIRE

    Díaz Madrid, José Ángel; Doménech Asensi, Ginés; López Alcantud, José Alejandro; Neubauer, Harald; Ruiz Merino, Ramón Jesús

    2006-01-01

    Vamos a presentar en este trabajo una de las líneas de investigación más prometedoras dentro de las que se vienen desarrollando en los grupos del Departamento de Electrónica, Tecnología de Computadoras y Proyectos, llevada a cabo en colaboración con el Instituto Fraunhofer IIS. Se trata del diseño y modelización de un tipo de sistemas complejos que están acaparando en los últimos años un gran interés dentro del campo del diseño microelectrónico: los convertidores analógico-digitales (ADC) de ...

  12. ANL-W MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement

    Energy Technology Data Exchange (ETDEWEB)

    O`Connor, D.G.; Fisher, S.E.; Holdaway, R. [and others

    1997-08-01

    The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement (EIS). This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO{sub 2} and UO{sub 2}), typically containing 95% or more UO{sub 2}. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. The paper describes the following: Site map and the LA facility; process descriptions; resource needs; employment requirements; wastes, emissions, and exposures; accident analysis; transportation; qualitative decontamination and decommissioning; post-irradiation examination; LA fuel bundle fabrication; LA EIS data report assumptions; and LA EIS data report supplement.

  13. ANL technical support program for DOE Environmental Restoration and Waste Management. Annual report, October 1991--September 1992

    Energy Technology Data Exchange (ETDEWEB)

    Bates, J.K.; Bradley, C.R.; Buck, E.C.; Cunnane, J.C.; Dietz, N.L.; Ebert, W.L.; Emery, J.W.; Feng, X.; Gerding, T.J.; Gong, M.; Hoh, J.C.; Mazer, J.J.; Wronkiewicz, D.J. [Argonne National Lab., IL (United States); Bourcier, W.L.; Morgan, L.E.; Newton, L.; Nielsen, J.K.; Phillips, B.L. [Lawrence Livermore National Lab., CA (United States); Ewing, R.C.; Wang, L. [Univ. of New Mexico, Albuquerque, NM (United States); Li, H.; Tomozawa, M. [Rensselaer Polytechnic Inst., Troy, NY (United States)

    1993-05-01

    A program was established for DOE Environmental Restoration and Waste Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site. This report covers progress in FY 1992 on the following tasks: 1. A compendium of the characteristics of high-level nuclear waste borosilicate glass has been written. 2. A critical review of important parameters that affect the reactivity of glass in an unsaturated environment is being prepared. 3. A series of tests has been started to evaluate the reactivity of fully radioactive glasses in a high-level waste repository environment and compare it to the reactivity of synthetic, nonradioactive glasses of similar composition. 4. The effect of radiation upon the durability of waste glasses at a high glass surface area-to-liquid volume (SA/V) ratio and a high gas-to-liquid volume ratio will be assessed. These tests address both vapor and high SA/V liquid conditions. 5. A series of tests is being performed to compare the extent of reaction of nuclear waste glasses at various SAN ratios. Such differences in the SAN ratio may significantly affect glass durability. 6. A series of natural analogue tests is being analyzed to demonstrate a meaningful relationship between experimental and natural alteration conditions. 7. Analytical electron microscopy (AEM), infrared spectroscopys and nuclear resonant profiling are being used to assess the glass/water reaction pathway by identifying intermediate phases that appear on the reacting glass. Additionally, colloids from the leach solutions are being studied using AEM. 8. A technical review of AEM results is being provided. 9. A study of water diffusion involving nuclear waste glasses is being performed. 10. A mechanistically based model is being developed to predict the performance of glass over repository-relevant time periods.

  14. Assessment of Physico-chemical Water Quality of Birecik Dam, Şanlıurfa, West East Region, Turkey

    Directory of Open Access Journals (Sweden)

    Banu Kutlu

    2015-07-01

    Full Text Available In year 2013, onsite seasonal measurements have been carried out in 4 different points of Birecik Reservoir, and water samples have been taken from surface and different depths. Physical and chemical parameters have been investigated in taken water samples. The result of analysis were obtained in the following range pH (6.98-9, temperature (9.9-26 °C, electrical conductivity (275-373 µs/cm, sodium ( 19.93-22.06 mg/L, potassium (1.-2.2 mg/L, chloride/11.68-21.4, hardness (179-210 mg/L, calcium (41.66-52.9 mg/L, magnesium ((17-18.35 mg/L, sulphate (27.92-43.48 mg/L, dissolved oxygen (7.92-8.83 mg/L, chemical oxygen (0.25-8.70 mg/L, nitrate (0.62-2.48 mg/L, nitrate (0.001-0.008, ammonium (0.01-0.07, phosphate (0.001-0.031 mg/L. The samples were compared with standard values recommended by world health (WHO. The study finalize that Birecik reservoir which was declared to be a threat to the water quality should be arrested at denitrification and nutrient control to halt the degradation of the water.

  15. ANL technical support program for DOE environmental restoration and waste management. Annual report, October 1993--September 1994

    International Nuclear Information System (INIS)

    A program was established for DOE Environmental Restoration and Waste Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site. This report covers progress in FY 1994 on the following tasks: (1) Critical Reviews of important parameters that affect the reactivity of glass in an unsaturated environment are being prepared. (2) A series of tests is ongoing to evaluate the reactivity of fully radioactive glasses in a high-level waste repository environment and compare it to the reactivity of synthetic, nonradioactive glasses of similar composition. (3) The effect of radiation upon the durability of waste glasses at a high SA/V ratio and a high gas-to-liquid volume ratio has been assessed. (4) A series of tests is being performed to compare the extent of reaction of nuclear waste glasses at various SA/V ratios. Such differences in the SA/V ratio may significantly affect glass durability. At long-term periods and high SA/V ratios, acceleration in glass reaction has been observed. (5) Tests were initiated on West Valley Reference 6 (WV6) glass and on the Environmental Assessment (EA) glass. (6) Tests with the actinide-doped West Valley glass ATM-10 have been in progress for over seven years as a part of work for the Yucca Mountain Site Characterization Project (YMP). (7) Analytical electron microscopy (AEM) is being used to assess the glass/water reaction pathway by identifying intermediate phases that appear on the reacting glass. Also, colloids from the leach solutions are being studied using AEM

  16. ANL-W MOX fuel lead assemblies data report for the surplus plutonium disposition environmental impact statement

    International Nuclear Information System (INIS)

    The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program's preparation of the draft surplus plutonium disposition environmental impact statement (EIS). This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO2 and UO2), typically containing 95% or more UO2. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. The paper describes the following: Site map and the LA facility; process descriptions; resource needs; employment requirements; wastes, emissions, and exposures; accident analysis; transportation; qualitative decontamination and decommissioning; post-irradiation examination; LA fuel bundle fabrication; LA EIS data report assumptions; and LA EIS data report supplement

  17. Fremtidens biogasfællesanlæg – nye anlægskoncepter og økonomisk potentiale

    DEFF Research Database (Denmark)

    Christensen, Johannes; Hjort-Gregersen, K.; Uellendahl, Hinrich;

    The main objective of the project was the identification and analysis of new technical concepts for centralized biogas plants, which would make them less dependant on organic waste supplies, and thus be economically self sustained mainly on manure supplies. The analyses have been carried out as...... system analyses, where plant concepts have been evaluated in connection with agricultural areas. 8 scenarios where analyzed, of which 2 were reference scenarios. One without a biogas plant, but with on-farm separation in order to reach phosphorous balance in the area by exporting fiber fraction (Scenario...... 0) to other regions, and one with a conventional centralized biogas plant with a post separation facility, likewise to enable the export of surplus phosphorous (Scenario 1). The remaining 6 scenarios are: 1a. Serial digestion in two digesters, and partial post separation of digested manure so...

  18. Anlægsbærere for fragilt X-syndrom kan udvise et bredt spektrum af kliniske manifestationer

    DEFF Research Database (Denmark)

    Jønch, Aia Elise; Grønskov, Karen; Carlsen Lunding, Jytte Merete; Nielsen, Jørgen E; Brøndum-Nielsen, Karen

    2014-01-01

    Carriers of fragile X syndrome can present with a broad spectrum of clinical disorders Fragile X syndrome, fragile X-associated tremor/ataxia syndrome (FXTAS) and fragile X-associated primary ovarian insufficiency (FXPOI) are three clinically distinct disorders caused by expansions of a CGG repeat...

  19. Effect of Water Harvesting with Runoff Strip Method on Lentil Yield in Şanlıurfa Province

    OpenAIRE

    SÜRÜCÜ, Abdulkadir; GÜNEŞ, Meryem; Yüksel, Alaaddin; DEMİRKIRAN, Ali Rıza; KAYA, Selami

    2014-01-01

    Water harvesting is crucially important for arid regions where the deficits in rainfall are irregular and a greatamount of this water is rapidly lost due to surface runoff. In the arid areas, water harvesting is directly related to process ofplant growth and conservation of soil and water. Water harvesting is based on the principle of preventing a part of the land,which is usually small and non-productive, from getting the share of rain and adding it to the share of another part. Thismakes th...

  20. Dem Gründer des Roten Kreuzes Henry Dunant anlässlich seines 100. Todestages

    OpenAIRE

    Brankamp, Hauke; Dieter, Anne; Ludewig, Manuela

    2010-01-01

    Der Beitrag erinnert an das wechselvolle Leben des Friedensnobelpreisträgers Henry Dunant, sucht nach biografischen Wurzeln seines von Menschlichkeit und Würde getragenen Verhaltens und macht auf seine Leistungen aufmerksam. Er will aber auch die Frage nach der Bedeutung des humanitären Völkerrechts im Verhältnis von Krieg und Frieden nicht außer Acht lassen.

  1. Anláisis de estrategias lingiiǐsticas en los medios de comunicación

    Institute of Scientific and Technical Information of China (English)

    Yan Shengfing

    2015-01-01

    Como todos sabemos, el lenguaje es una herramienta utilizando a la gente para eonmniearse. Entonees, aómo reeibimos los mejores resultados a través de utilizar esta herramienta euando estamos eomunicándonos? Eso tiene que prestar ateneión a utilizar algunas téenieas o estrategias de la lengua. Como dice el refrén : " Hay- diez formas al ha- blar de una frase. " A1 eseuehar, pareee eomo siesta frase sea un poeo exagerado, pero se lo deleita euidadosamente, puede sentir algunos de verdad dentro. Esto es lo que quiero hablar de esta tesis.

  2. ANL progress in minimizing effects of LEU conversion on calcination of fission-product 99Mo acid waste solution

    International Nuclear Information System (INIS)

    The goal of the Reduced Enrichment for Research and Test Reactors (RERTR) Program is to limit the use of high-enriched uranium (HEU) in research and test reactors by substituting low-enriched uranium (LEU) wherever possible. The work reported here documents technical progress in our partnership with MDS Nordion (MSDN), Atomic Energy Canada Limited (AECL) and SGN of France to convert the 99Mo production in the MAPLE reactors and the New Processing Facility at AECL Chalk River Laboratories from the use of HEU targets to LEU targets. The role of Argonne National Laboratory and the Chemical Engineering Division in the program is to work with MDSN to minimize the impact of conversion on the efficiency and reliability of their production effort. The primary concern with the conversion to LEU from HEU targets is that it would result in a five fold increase in the total uranium. This increase is likely to result in more liquid waste from the process. We have been working with MDSN/AECL/SGN to minimize liquid waste volume and the effects of 5 times more uranium on waste treatment and storage. The planned process for solidifying high level fissile waste from the processing of HEU targets in the New Processing Facility will use calcination of the uranium waste solution. This method generates NO2 gas and UO3 solid. We have studied two processes for treating the uranium-rich liquid waste from a LEU-based process for MDSN: (1) an optimized direct calcination process that is similar to the planned process, and (2), a calcination of uranyl oxalate precipitate. The specific goal of the work reported here was to characterize the chemical reactions that occur during these two processes. In particular, the compositions of the gaseous and solid products were of interest. A series of experiments was carried out to show the effects of temperature and the redox potential of the reaction atmosphere. The primary products of the direct calcination process were mixtures of U3O8 and UO3 solids and NO2 gas. The primary products of the uranyl oxalate precipitate process were mixtures of U3O8 and UO2 solid and CO2 gas. Higher temperature and a reducing atmosphere tended to favor quadravalent uranium over hexavalent uranium in the solid product. These data will help to plan for pilot plant testing. In addition, the data provides information for the design of the off gas systems for pilot and production facilities. (author)

  3. LNS users primer for accessing government sites on the ARPA network. [MIT. -->. ANL, BNL, LBL, and New York Univ. Courant Inst

    Energy Technology Data Exchange (ETDEWEB)

    Kannel, M.

    1979-06-01

    This primer was developed as part of the study conducted by the Laboratory for Nuclear Science (LNS) on the feasibility of networks for computer resource sharing. The primer is an instructinal guide for the LNS user who would like to access and use computers at other government sites on the ARPA network. The format is a series of scenarios of actual recorded on-line terminal sessions' showing the novice user how to access the foreign site, obtain help documentation, run a simple program, and transfer files to and from the foreign site. Access to the ARPA network in these scenarios is via Multics or the Massachusetts Institute of Technology Terminal Interface Processor. The foreign government sites accessed are the computing facilities at Argonne National Laboratory, Brookhaven National Laboratory, Lawrence Livermore Laboratory, and New York University Courant Institute. This technique of auditing actual terminal sessions as a teaching aid can be extended to include other computing facilities as well as other networks.

  4. GAC--ANL TNS scoping studies. Status report for FY-77, October 1, 1976--September 30, 1977. Volume IV. Reactor engineering

    International Nuclear Information System (INIS)

    Conceptual designs have been developed for a 3.8 m Ignition Test Reactor (ITR) and a 4.2 m Upgradable Ignition Test Reactor (UITR). Both reactors are based on a doublet plasma cross section which enables them to achieve high β. The 3.8 m ITR is designed to achieve D-T ignition and maintain 30-second burns at a low duty factor of 0.1. The 4.2 m UITR is designed to be operated initially as an ITR and later be upgraded for net power Experimental Power Reactor (EPR) operation at a duty factor of 0.78. Both reactors utilize a water-cooled Inconel 625 plasma chamber with graphite tiles lining the inboard walls and movable limiters at the top and bottom of the chambers. The exposed walls of the chamber are coated with a carbon deposit. Water-cooled tungsten blocks, stacked in annular stainless steel tanks together with the inboard field-shaping coils, are used as the inboard shield. Water-cooled steel with lead cover layers is used for the bottom shield, while the other outboard shields are built up of stainless steel, boronated water, and lead. Both designs employ 12 superconducting NbTi toroidal field coils built up in pancake windings with stainless steel interleaving the conductor windings

  5. ANL CP-5 decontamination and decommissioning project necessary and sufficient pilot. Report of the standards identification team on the selection of the necessary and sufficient standards set

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-01

    The CP-5 reactor was a heavy-water moderated and cooled, highly-enriched uranium-fueled thermal reactor designed for supplying neutrons for research. The reactor was operated almost continuously for 25 years until its final shutdown in 1979. It is situated on approximately three acres in the southwestern section of Argonne National Laboratory. In 1980, all nuclear fuel and the heavy water that could be drained from the process systems were shipped off-site, and the CP-5 facility was placed into lay-up pending funding for decommissioning. It was maintained in the lay-up condition with a minimum of maintenance until 1990, when the decontamination and decommissioning (D and D) project began. This D and D project provides for the disassembly and removal of all radioactive components, equipment, and structures that are associated with the CP-5 facility. The experimental area around the CP-5 reactor has been prepared for D and D, and the area outside the facility has been remediated. The reactor primary coolant and support systems have been removed and packaged as waste. The significant remaining tasks are (1) removal of the reactor internals and the biological shield structure; (2) decontamination of the rod storage area; (3) decontamination of the various radioactive material storage and handling facilities, including the fuel pool; and (4) decontamination and dismantlement of the building. This report describes the scope of the project, identification of standards for various aspects of the project, the lessons learned, and consideration for implementation.

  6. TSO at AMD: the Applied Mathematics Division's implementation of the Time Sharing Option. [IBM 360/75 at ANL

    Energy Technology Data Exchange (ETDEWEB)

    Burger, A.J.

    1975-05-26

    This memorandum describes some of the ways in which the Time Sharing Option (TSO) is implemented on the 360/75 in the Applied Mathematics Division of Argonne National Laboratory differs from IBM standard TSO under OS/MVT. Differences pertaining to internal modifications to improve performance, reliability, and efficient use of direct access storage, not resulting in any changes to the syntax of any command, are not discussed. This document assumes a basic familiarity with TSO, as may be gained from TSO Terminal User's Guide. (RWR)

  7. Suzanne Mubarak : Reden anlässlich der Ernennung zur Ehrenbürgerin der Universität Stuttgart am 26. November 2004

    OpenAIRE

    Fritsch, Dieter; Müller, Ulrich; Mohn, Liz; Mubarak, Suzanne; Mansour, Ashraf

    2005-01-01

    Inhalt: Programm / Program (S. 7); Fritsch, Dieter (Rektor der Universität Stuttgart): Welcome address on the occasion of the conferment of Honorary Citizenship of the Universität Stuttgart upon Her Excellency Suzanne Mubarak (S. 9); Müller, Ulrich (Minister im Staatsministerium und für europäische Angelegenheiten des Landes Baden-Württemberg): Grußwort / Welcoming address (S. 19); Mohn, Liz (Geschäftsführerin der Bertelsmann Verwaltungsgesellschaft mbH, Mitglied des Aufsichtsrates der Bertel...

  8. Differences between LASL- and ANL-processed cross sections. [MINX/1DX vs ETOE-2/MC/sup 2/-2

    Energy Technology Data Exchange (ETDEWEB)

    Kidman, R.B.; MacFarlane, R.E.; Becker, M.

    1978-03-01

    As part of the Los Alamos Scientific Laboratory (LASL) cross-section processing development, LASL cross sections and results from MINX/1DX system are compared to the Argonne National Laboratory cross sections and results from the ETOE-2/MC/sup 2/-2 system for a simple reactor problem. Exact perturbation theory is used to establish the eigenvalue effect of every isotope group cross-section difference. Cross sections, cross-section differences, and their eigenvalue effects are clearly and conveniently displayed and compared on a group-by-group basis.

  9. ANL CP-5 decontamination and decommissioning project necessary and sufficient pilot. Report of the standards identification team on the selection of the necessary and sufficient standards set

    International Nuclear Information System (INIS)

    The CP-5 reactor was a heavy-water moderated and cooled, highly-enriched uranium-fueled thermal reactor designed for supplying neutrons for research. The reactor was operated almost continuously for 25 years until its final shutdown in 1979. It is situated on approximately three acres in the southwestern section of Argonne National Laboratory. In 1980, all nuclear fuel and the heavy water that could be drained from the process systems were shipped off-site, and the CP-5 facility was placed into lay-up pending funding for decommissioning. It was maintained in the lay-up condition with a minimum of maintenance until 1990, when the decontamination and decommissioning (D and D) project began. This D and D project provides for the disassembly and removal of all radioactive components, equipment, and structures that are associated with the CP-5 facility. The experimental area around the CP-5 reactor has been prepared for D and D, and the area outside the facility has been remediated. The reactor primary coolant and support systems have been removed and packaged as waste. The significant remaining tasks are (1) removal of the reactor internals and the biological shield structure; (2) decontamination of the rod storage area; (3) decontamination of the various radioactive material storage and handling facilities, including the fuel pool; and (4) decontamination and dismantlement of the building. This report describes the scope of the project, identification of standards for various aspects of the project, the lessons learned, and consideration for implementation

  10. Safety-related events at US Gaseous Diffusion plants. DOE/ANL training course on prevention of significant nuclear events. Revision 1

    International Nuclear Information System (INIS)

    A brief description of the gaseous diffusion process is presented, then two significant, non-critical operating incidents are discussed. Handling of liquid and gaseous uranium hexafluoride (UF6) is discussed and two significant incidents involving UF6 handling are described

  11. Tverrfaglig innfallsvinkel til verneprognoser og vernestrategi for maritime kulturminner knyttet til anløpsplasser og leder fra jernalder og middelalder

    OpenAIRE

    Elvestad, Endre; Nitter, Marianne; Selsing, Lotte

    2009-01-01

    When the maritime cultural heritage is being protected, little emphasis is placed on problems concerning erosion and destruction of remains at landing places and navigable channels on the Norwegian coast. In recent years, an extensive survey has been carried out along the coast of the county of Rogaland and many new cultural monuments and sites related to landing places and navigable channels have been found, many of them dating from the Iron Age and the Middle Ages. A new method has...

  12. Satellitengeodäsie und Langbasis-Interferometrie auf der Fundamentalstation Wettzell. Kolloquiumsvorträge anläßlich des 60sten Geburtstages von Prof. Manfred Schneider.

    Science.gov (United States)

    Ilk, K.-H.

    Contents: Die krumme Geodäte (H. Ruder, M. Ruder). Zur Geschichte der Fundamentalstation Wettzell (H. Seeger et al.). Newtons Philosophiae naturalis principia mathematica (M. Schramm). Von Newton zu Einstein (M. H. Soffel). Geodäsie und Physik (S. Heitz). Erdbebenvorhersage mit SEISMOLAP (J. Zschau).

  13. Necessity Of Guli National Wetland Park Construction In Daxing'anling District%浅议大兴安岭古里国家湿地公园建设的必要性

    Institute of Scientific and Technical Information of China (English)

    朱家威

    2011-01-01

    According to the statement of geographic location,wetland resources of Guli national wetland park,protection,recovery,propaganda education and reasonable use of the wetland park,this paper states the necessity of construct the national wetland park.%通过对古里国家湿地公园地理位置、湿地资源以及国家湿地公园建成后对湿地生态系统保护、湿地恢复、湿地宣传教育和合理利用等方面影响的论述,阐明了建设大兴安岭古里国家湿地公园的必要性。

  14. 小兴安岭红松种群天然更新及影响因子的探讨%The Natural Regeneration and Its Impact Factors of Korean Pine Population in Xiaoxing'anling Mountain

    Institute of Scientific and Technical Information of China (English)

    张海军; 张淑兰; 王长宝

    2015-01-01

    The natural regeneration of Korean pine species has always been an important issue concerned by vegetation ecologists.To study further on the natural regeneration process of Korean pine,its natural update status and influencing factors are summarized and discussed from the Korean pine seeds,seedlings bank,population structure and dynamic and community structure and diversity.Now,the reservation of Korean pine seed and seedling bank amount are falling due to nut picking,and the natural regeneration of Korean pine population is mainly influenced by ecological factors,such as birds and animals,forest canopy density,forest gap and deforestation.To protect and maintain the development and stable update of Korean pine community,the measures of controlling to pick pine nuts,protecting wildlife,moderately cutting or selective cutting,planting conifers and protecting broad-leaved trees,and so on are recommended.%红松种群的天然更新一直是植被生态学家关注的重要问题,为了深刻了解红松天然更新过程,从红松土壤种子库、幼苗库、种群结构和动态以及群落结构和多样性等方面,对其天然更新状况及影响因子进行了综述和探讨,认为:红松的种子库和幼苗库可能由于松果采摘,其储藏量在减少;红松种群天然更新主要受鸟兽、林分郁闭度、林窗、森林采伐等生态因子的影响。建议采取控制松果采摘,保护野生动物,适度采伐或择伐,栽针保阔等措施来保护和维持红松林群落的发展和稳定更新。

  15. Kadın cinselliğinin söylemsel inşası ve namus cinayetleri: Şanlıurfa örneği

    OpenAIRE

    YILDIZ, A. Nevin

    2009-01-01

    Bu tez çalışmasında namus olgusu ve namus cinayetleri, nihai hedefi kadınhazzının denetimi olan cinsellik ideolojisinin bir uzantısı, özgün bir örneği olarakincelenmektedir. Tezde farklı ataerkil yapılar içinde dönüşen anlamlarına veişlevlerine rağmen varlığını koruyan namus olgusunun ve namus cinayetlerininTürkiye’de cinsiyet/toplumsal cinsiyet eşitsizliklerinin altında yatan dinamiklerindenbiri olduğu savunulmaktadır. Namus olgusunun farklı sosyo-ekonomik koşullarçerçevesinde içeri...

  16. 海南岛马鞍岭火山口地区翼手目物种多样性%Species Diversity of Chiroptera in Ma'anling Volcano Area, Hainan Island

    Institute of Scientific and Technical Information of China (English)

    李玉春; 陈忠; 龙育儒; 周锋; 钟友仁

    2006-01-01

    马鞍岭火山口为海南岛的重要农业区和旅游地,为了解该地区的动物资源,2004年我们对该地区的翼手目种类进行了调查.结果显示,马鞍岭火山口地区共有翼手目动物10种,隶属4科7属,占海南岛已知翼手目种类(31种)的32.3%,具有较高的翼手目物种多样性,其香农-维纳指数为2.734、均匀性指数为0.823、辛普森指数为0.817.本文还分析了马鞍岭火山口地区翼手目的区系特点,并对其物种的多样性和分布特征进行了讨论.

  17. „This is just a fucking movie. Also fahrt ab damit!“ Eine Rezensionsreise durch Abel Ferraras Film ‚Pasolini‘, anlässlich des 40. Todestages von Pier Paolo Pasolini

    Directory of Open Access Journals (Sweden)

    Angela Oster

    2015-06-01

    Full Text Available Das Leben Pasolinis ist bereits zu wiederholten Malen der Gegenstand von Texten und Filmen gewesen. Aufgrund des skandalträchtigen Todes des Linksintellektuellen – er wurde unter nie genau geklärten Umständen 1975 ermordet – ranken sich viele Mythen um den letzten Tag Pasolinis. Genau diesen 'ultimo giorno' verfilmt Abel Ferrara (1914 und setzt dabei eigene Akzente. Mit literar- und dokumentargenauer Perspektive bietet Ferrara gleichwohl innovative Interpretationen in Hinblick auf einen der wichtigsten Künstler Italiens.

  18. „This is just a fucking movie. Also fahrt ab damit!“ Eine Rezensionsreise durch Abel Ferraras Film ‚Pasolini‘, anlässlich des 40. Todestages von Pier Paolo Pasolini

    OpenAIRE

    Angela Oster

    2015-01-01

    Das Leben Pasolinis ist bereits zu wiederholten Malen der Gegenstand von Texten und Filmen gewesen. Aufgrund des skandalträchtigen Todes des Linksintellektuellen – er wurde unter nie genau geklärten Umständen 1975 ermordet – ranken sich viele Mythen um den letzten Tag Pasolinis. Genau diesen 'ultimo giorno' verfilmt Abel Ferrara (1914) und setzt dabei eigene Akzente. Mit literar- und dokumentargenauer Perspektive bietet Ferrara gleichwohl innovative Interpretationen in Hinblick auf einen der ...

  19. CNEA/ANL collaboration program to develop an optimized version of DART validation and assessment by means of U3 Six and U3 O8-Al dispersed CNEA mini plate irradiation behavior

    International Nuclear Information System (INIS)

    The DART code is based upon a thermochemical model that can predict swelling, recrystallization, fuel-meat interdiffusion and other issues related with MTR dispersed FE behavior under irradiation. As a part of a common effort to develop an optimized version of DART, a comparison between DART predictions and CNEA miniplates irradiation experimental data was made. The irradiation took place during 1981-82 for U3O8 miniplates and 1985-86 for U3 Six at Oak Ridge Research Reactor. (author)

  20. Testing WIMS-D4M cross sections and the ANL ENDF/B-V 69 group library. Results from global diffusion and Monte Carlo calculations compared with measurements in the Romanian 14-MW TRIGA reactor

    Energy Technology Data Exchange (ETDEWEB)

    Bretscher, M.M.

    1993-12-31

    The WIMS-D4 code has been modified (WIMS-D4M) to produce microscopic isotopic cross sections in ISOTXS format for use in diffusion and transport calculations. Beginning with 69-group libraries based on ENDF/B-V data, numerous cell calculations have been made to prepare a set of broad group cross sections for use in diffusion calculations. Global calculations have been made for two control rod states of the Romanian steady state TRIGA reactor with 29 fresh HEU fuel clusters. Detailed Monte Carlo calculations also have been performed for the same reactor configurations using data based on ENDF/B-V. Results from these global calculations are compared with each other and with the measured excess reactivities. Although region-averaged macroscopic principal cross sections obtained from WIMS-D4M are in good agreement with the corresponding Monte Carlo values, problems exist with the high energy (E > 10 keV) microscopic hydrogen transport cross sections.

  1. Argonne National Laboratory 1986 publications

    International Nuclear Information System (INIS)

    This report is a bibliography of scientific and technical 1986 publications of Argonne National Laboratory. Some are ANL contributions to outside organizations' reports published in 1986. This compilation, prepared by the Technical Information Services Technical Publications Section (TPS), lists all nonrestricted 1986 publications submitted to TPS by the Laboratory's Divisions. Author indexes list ANL authors only. If a first author is not an ANL employee, an asterisk in the bibliographic citation indicates the first ANL author. The report is divided into seven parts: Journal Articles -- Listed by first author; ANL Reports -- Listed by report number; ANL and non-ANL Unnumbered Reports -- Listed by report number; Non-ANL Numbered Reports -- Listed by report number; Books and Book Chapters -- Listed by first author; Conference Papers -- Listed by first author; and Complete Author Index

  2. Argonne National Laboratory 1986 publications

    Energy Technology Data Exchange (ETDEWEB)

    Kopta, J.A.; Springer, C.J.

    1987-12-01

    This report is a bibliography of scientific and technical 1986 publications of Argonne National Laboratory. Some are ANL contributions to outside organizations' reports published in 1986. This compilation, prepared by the Technical Information Services Technical Publications Section (TPS), lists all nonrestricted 1986 publications submitted to TPS by the Laboratory's Divisions. Author indexes list ANL authors only. If a first author is not an ANL employee, an asterisk in the bibliographic citation indicates the first ANL author. The report is divided into seven parts: Journal Articles -- Listed by first author; ANL Reports -- Listed by report number; ANL and non-ANL Unnumbered Reports -- Listed by report number; Non-ANL Numbered Reports -- Listed by report number; Books and Book Chapters -- Listed by first author; Conference Papers -- Listed by first author; and Complete Author Index.

  3. Measurement of Acceptable Noise Level with Background Music

    OpenAIRE

    Ahn, Hyun-Jung; Bahng, Junghwa; Lee, Jae Hee

    2015-01-01

    Background and Objectives Acceptable noise level (ANL) is a measure of the maximum background noise level (BNL) that a person is willing to tolerate while following a target story. Although researchers have used various sources of target sound in ANL measures, a limited type of background noise has been used. Extending the previous study of Gordon-Hickey & Moore (2007), the current study determined the effect of music genre and tempo on ANLs as possible factors affecting ANLs. We also investi...

  4. Argonne National Laboratory's photooxidation organic mixed-waste treatment system

    International Nuclear Information System (INIS)

    This paper describes the installation and startup testing of the Argonne National Laboratory-East (ANL-E) photo-oxidation organic mixed-waste treatment system. This system will treat organic mixed (i.e., radioactive and hazardous) waste by oxidizing the organics to carbon dioxide and inorganic salts in an aqueous media. The residue will be treated in the existing radwaste evaporators. The system is installed in the waste management facility at the ANL-E site in Argonne, Illinois

  5. Argonne National Laboratory-East site environmental report for calendar year 1998.

    Energy Technology Data Exchange (ETDEWEB)

    Golchert, N.W.; Kolzow, R.G.

    1999-08-26

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL-E) for 1998. To evaluate the effects of ANL-E operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL-E site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL-E effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, fallout, ANL-E, and other) and are compared with applicable environmental quality standards. A US Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the US Environmental Protection Agency's CAP-88 (Clean Air Act Assessment Package-1988) computer code, was used in preparing this report. The status of ANL-E environmental protection activities with respect to the various laws and regulations that govern waste handling and disposal is discussed, along with the progress of environmental corrective actions and restoration projects.

  6. Immobilization of fission products in phosphate ceramic waste forms

    International Nuclear Information System (INIS)

    Argonne National Laboratory (ANL) is developing chemically bonded phosphate ceramics (CBPCs) to treat low-level mixed wastes, particularly those containing volatiles and pyrophorics that cannot be treated by conventional thermal processes. This work was begun under ANL''s Laboratory Directed Research and Development funds, followed by further development with support from EM-50''s Mixed Waste Focus Area

  7. Argonne National Laboratory-East site environmental report for calendar year 1996

    International Nuclear Information System (INIS)

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL-E) for 1996. To evaluate the effects of ANL-E operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL-E site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL-E effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL-E, and other) and are compared with applicable environmental quality standards. A US Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL-E environmental protection activities with respect to the various laws and regulations that govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects

  8. Argonne National Laboratory-East site environmental report for calendar year 1998

    International Nuclear Information System (INIS)

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL-E) for 1998. To evaluate the effects of ANL-E operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL-E site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL-E effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, fallout, ANL-E, and other) and are compared with applicable environmental quality standards. A US Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the US Environmental Protection Agency's CAP-88 (Clean Air Act Assessment Package-1988) computer code, was used in preparing this report. The status of ANL-E environmental protection activities with respect to the various laws and regulations that govern waste handling and disposal is discussed, along with the progress of environmental corrective actions and restoration projects

  9. Argonne National Laboratory-East site environmental report for calendar year 1996

    Energy Technology Data Exchange (ETDEWEB)

    Golchert, N.W.; Kolzow, R.G.

    1997-09-01

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL-E) for 1996. To evaluate the effects of ANL-E operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL-E site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL-E effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL-E, and other) and are compared with applicable environmental quality standards. A US Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL-E environmental protection activities with respect to the various laws and regulations that govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects.

  10. Argonne National Laboratory 1985 publications

    International Nuclear Information System (INIS)

    This report is a bibliography of scientific and technical 1985 publications of Argonne National Laboratory. Some are ANL contributions to outside organizations' reports published in 1985. This compilation, prepared by the Technical Information Services Technical Publications Section (TPB), lists all nonrestricted 1985 publications submitted to TPS by Laboratory's Divisions. The report is divided into seven parts: Journal Articles - Listed by first author, ANL Reports - Listed by report number, ANL and non-ANL Unnumbered Reports - Listed by report number, Non-ANL Numbered Reports - Listed by report number, Books and Book Chapters - Listed by first author, Conference Papers - Listed by first author, Complete Author Index

  11. Argonne National Laboratory 1985 publications

    Energy Technology Data Exchange (ETDEWEB)

    Kopta, J.A. (ED.); Hale, M.R. (comp.)

    1987-08-01

    This report is a bibliography of scientific and technical 1985 publications of Argonne National Laboratory. Some are ANL contributions to outside organizations' reports published in 1985. This compilation, prepared by the Technical Information Services Technical Publications Section (TPB), lists all nonrestricted 1985 publications submitted to TPS by Laboratory's Divisions. The report is divided into seven parts: Journal Articles - Listed by first author, ANL Reports - Listed by report number, ANL and non-ANL Unnumbered Reports - Listed by report number, Non-ANL Numbered Reports - Listed by report number, Books and Book Chapters - Listed by first author, Conference Papers - Listed by first author, Complete Author Index.

  12. Cytotoxic and genotoxic activities of an aqueous extract from Thai Noni leaves in human lymphocytes in Vitro

    Directory of Open Access Journals (Sweden)

    Treetip Ratanavalachai

    2010-03-01

    Full Text Available The aims of this study were to investigate the cytotoxic and genotoxic activities of an aqueous extract from ThaiNoni’s leaf (ANL in human lymphocytes in vitro. Chromosome aberration and sister chromatid exchange (SCE assays were performed. Treatment of ANL (0.8-25 mg/ml for 3 h did not significantly induce chromosomal aberration nor SCEs(p<0.05. Nevertheless, ANL could induce cytotoxic activities as shown by their toxic level of mitotic index in a dose dependent manner. Only toxicity induced at lower doses of ANL (< 3.1 mg/ml could be recovered as shown by their normal level of the proliferation index. ANL at higher dose of 50 mg/ml induced potent cytotoxicity as no mitotic cell was found. Interestingly, metaphase chromosomes undergoing tetraploidization were found from ANL treatment at 12.5 and 25 mg/ml. These indicate that ANL treatment could interrupt cell cycle that progressed after S phase. Therefore, the optimum dose of ANL as food supplement needs to be considered carefully for human safety. Nevertheless, ANL at doses lower than 3.1 mg/ml mightbe useful for treatment of human hyperproliferative disorder at appropriate dose since ANL could induce temporary cytotoxicitywithout genotoxicity. Scientific study is also needed to verify the usefulness of an aqueous extract of Noni’s leaf.

  13. Argonne National Laboratory, east hazardous waste shipment data validation

    International Nuclear Information System (INIS)

    At the request of EM-331, the Radioactive Waste Technical Support Program (TSP) is conducting an evaluation of data regarding past hazardous waste shipments from DOE sites to commercial TSDFs. The intent of the evaluation is to find out if, from 1984 to 1991, DOE sites could have shipped hazardous waste contaminated with DOE-added radioactivity to commercial TSDFs not licensed to receive radioactive material. A team visited Argonne National Laboratory, East (ANL-E) to find out if any data existed that would help to make such a determination at ANL-E. The team was unable to find any relevant data. The team interviewed personnel who worked in waste management at the time. All stated that ANL-E did not sample and analyze hazardous waste shipments for radioactivity. Waste generators at ANL-E relied on process knowledge to decide that their waste was not radioactive. Also, any item leaving a building where radioisotopes were used was surveyed using hand-held instrumentation. If radioactivity above the criteria in DOE Order 5400.5 was found, the item was considered radioactive. The only documentation still available is the paperwork filled out by the waste generator and initialed by a health physics technician to show no contamination was found. The team concludes that, since all waste shipped offsite was subjected at least once to health physics instrumentation scans, the waste shipped from ANL-E from 1984 to 1991 may be considered clean

  14. Türkiye'de uygulanan toprak toplulaştırma yöntemlerinin karşılaştırılması. İzmir ve Şanlıurfa örneği

    OpenAIRE

    GÜN, Arife Sema

    1996-01-01


       For developing agricultural structure in Turkey and for removing fragmented land, for uniting the fragmented and distributed lands, in 1961, it was started the land consolidation projects. According to the law, 3083, in execution, the obligatory consolidation in agricultural reform lands are carried on Agricultural Reform General Directorate. Outside the agricultural reform areas, the voluntary consolidation projects are applied by Ru...

  15. "Ist das Rätsel um die äußere Form der Pyramiden gelöst? oder Der Klang der Pyramiden - Wirklichkeit oder Wunschdenken?" - Vortrag am 18. Juli 2009 anlässlich der 41. Ständigen Ägyptologenkonferenz in Münster

    OpenAIRE

    Müller-Römer, Frank

    2009-01-01

    2008 wurde in der Presse ausgiebig und voller Begeisterung über das Buch von F.W. Korff „Der Klang der Pyramiden“ berichtet. In dem Vortrag werden die – größtenteils nur mühsam nachzuvollziehenden – Annahmen, Berechnungen und Schlussfolgerungen Korff´s erläutert und daran anschließend analysiert, mit den archäologischen und historischen Befunden insbesondere des Alten Reiches verglichen und abschließend bewertet. Als Ergebnis ist festzustellen, dass Korff den Versuch unternimmt, von Tonklänge...

  16. Başarılı bir ortaokulda okul müdürünün çok faktörlü liderlik vasıflarının araştırılması (Şanlıurfa / Siverek örneği)

    OpenAIRE

    Hıdıroğlu, Yeliz Özkan; Hıdıroğlu, Çağlar Naci

    2014-01-01

    Çalışmanın amacı, başarılı bir okulun kültüründe okul müdürünün çok faktörlü liderlik stillerinin incelenmesidir. Bu çalışma, başarılı bir okuldaki okul müdürünün liderlik vasıflarının ortaya koyulması açısından tarama çalışmasıdır. Araştırmada öncelikle araştırma kolaylığı dikkate alınmış, sonrasında ise uygun bölgedeki okullar belirlenerek okul seçiminde ölçüt olarak SBS sınavındaki başarı ve öğretmen isteklilikleri önemsenmiştir. Araştırmada, söz konusu ortaokuldaki 24 kadın ve 21 erkek to...

  17. Yakıt Pili ile Çalışan Elektrikli Bir Aracın Güç, Sıcaklık, Bağıl Nem ve Hızının Anlık Olarak İzlenmesi ve Kontrolü

    OpenAIRE

    Aydın, Serkan; Ramazan GÜMÜŞ; Akçay, İsmail Hakkı

    2013-01-01

    Recent years,innovations on alternative energy resourges, electronics and software, started to affect huge part of automative industry. First uses of electronics and software on automative industry and it’s positive results triggered the automative manufacturers to produce electronics based systems. Especially, nowadays many car manufacturer prefer microcomputer based systems on their products to improve driving safety, fuel consumption, and reducing the environmental affects. To the parallel...

  18. Rede vom Bundeskanzler Gerhard Schr(o)der anl(a)sslich der Verleihung der Ehrendoktorw(u)rde der Tongji-Universit(a)t%德国总理格哈德·施罗德在被授予同济大学名誉博士学位时的讲话

    Institute of Scientific and Technical Information of China (English)

    俞宙明

    2003-01-01

    @@ 尊敬的校长女士、 校务委员会主任先生、 尊敬的教授们、 亲爱的同学们、 女士们、先生们: 我为今天诸位给予我的崇高荣誉致以衷心的感谢.我将这一表彰视为首先是对中德两国之间以及我们两国人民之间极好关系的高度评价.这种关系是我们共同合作的成果,也是我们将来所必须继续为之努力的.这种关系不仅对两国的政治家来说是重要的,尤为重要的则是它可以促进我们两国人民携手共进.大批中国学生在德国学习,这一点使我非常高兴,我认为这对于我们两国之间的关系是至关重要的.

  19. 深生态学:探寻摆脱环境危机的生存智慧——纪念阿恩·奈斯诞辰100周年%Deep Ecology: Exploring Living Wisdom of Breaking away from the. Environmental Crisis--- Corn- memorating Anle Naess' 100th Birth Anniversary

    Institute of Scientific and Technical Information of China (English)

    夏承伯; 包庆德

    2012-01-01

    阿恩.奈斯因创立深生态学理论体系,引领深生态学实践运动而被学界尊为“深生态学之父”。奈斯融东西方文化资源,特别是生态智慧干一体,自觉吸收现代生态学、系统科学和心理学等最新成果,积极扬弃斯宾诺莎和甘地的哲学思想,深度追溯环境危机的哲学根源,认为主流世界观假设单体与环境之间的人为区别.导致生态灾难,并由此证明这种形而上学的危险性。深生态学秉承并倡导“生物圈完全平等”的生态主义立场.拒斥人类中心主义价值观,从形上思维层面反思形下环境问题,旨在探寻摆脱环境危机的生存智慧,也由此引来包括反人类面目、神秘主义倾向和生态法西斯主义等在内的相关质疑。但因其理论本身的与时俱进品格和包容开放姿态,仍焕发出勃勃生机和活力并展示了广阔的发展前景。%In academia Ame Naess is called the Father of "deep ecology" as he has created the theory system of deep ecology and led the deep ecological movement. Naess has searched in depth philosophical origin of the environmental crisis on the base of merging the cuhural resources especially eco-wisdom of the East and the Wesl. consciously absorbing the latest achievements of modern ecology, systemic seience and psychology and dialectically absorbing philosophical thoughts of Spinoza and Gandhi. He assumed the origin of the coo-disaster is the artificial distinction between the monomer and the environment of the dominant worldview and proved the danger of such metaphysics. Deep eeology has adhered and advicating the eeo-stance of "full equality in bio- sphere", has rejected /he values of anthropocentrism and reflected the environmental issues of physics with metaphysical thinking, in order to explore living wisdom of breaking away from the environmental crisis. These have sparked questions including mysticism tendencies and eco-fascism and so on. But the theory glows with vitality and vigor and enjoys promising prospects because of its character of advancing with the times and its inclusive and open attitude.

  20. Reel Efektif Döviz Kurunun Durağanlığının Yapısal Kırılmalı Panel Birim Kök Testleri Kullanılarak Sınanması = Analyzing the Stationarity of Reel Effective Exchange Rates Using Panel Unit Root Tests with Structural Breaks

    Directory of Open Access Journals (Sweden)

    Ferda YERDELEN TATOĞLU

    2009-06-01

    Full Text Available In the last years, many studies have analyzed the stationarity of reel exchange rates which gives important knowledge about economic stability of countries. The panel unit root tests which include both pooled and individual unit root tests are used frequently to analyze the stationarity of real exchange rates. Generally, structural breaks issue have taken place in macroeconomic time series for some years. If unit root tests are used without taking account these structural breaks, stationarity hypothesis can be rejected mistakenly. In this study, panel unit root tests with and without structural breaks were used to analyze the validity of Purchasing Power Parity hypothesis in 25 OECD countries. According to the results, while in panel unit root tests with no break, PPP theory is valid for only 10 countries; it is valid for all countries in panel unit root tests with structural breaks.

  1. Advantages of Binaural Amplification to Acceptable Noise Level of Directional Hearing Aid Users

    OpenAIRE

    Kim, Ja-Hee; Lee, Jae Hee; Lee, Ho-Ki

    2014-01-01

    Objectives The goal of the present study was to examine whether Acceptable Noise Levels (ANLs) would be lower (greater acceptance of noise) in binaural listening than in monaural listening condition and also whether meaningfulness of background speech noise would affect ANLs for directional microphone hearing aid users. In addition, any relationships between the individual binaural benefits on ANLs and the individuals' demographic information were investigated. Methods Fourteen hearing aid us...

  2. Acceptable noise level with Danish, Swedish, and non-semantic speech materials.

    OpenAIRE

    Brännström, Jonas; Lantz, Johannes; Nielsen, Lars Holme; Olsen, Steen Østergaard

    2012-01-01

    Objective: Acceptable noise level (ANL) has been established as a method to quantify the acceptance of background noise while listening to speech presented at the most comfortable level. The aim of the present study was to generate Danish, Swedish, and a non-semantic version of the ANL test and investigate normal-hearing Danish and Swedish subjects' performance on these tests. Design: ANL was measured using Danish and Swedish running speech with two different noises: Speech-weighted ampli...

  3. Development and pilot demonstration program of a waste minimization plan at Argonne National Laboratory

    International Nuclear Information System (INIS)

    In response to US Department of Energy directives, Argonne National Laboratory (ANL) has developed a waste minimization plan aimed at reducing the amount of wastes at this national research and development laboratory. Activities at ANL are primarily research- oriented and as such affect the amount and type of source reduction that can be achieved at this facility. The objective of ANL's waste minimization program is to cost-effectively reduce all types of wastes, including hazardous, mixed, radioactive, and nonhazardous wastes. The ANL Waste Minimization Plan uses a waste minimization audit as a systematic procedure to determine opportunities to reduce or eliminate waste. To facilitate these audits, a computerized bar-coding procedure is being implemented at ANL to track hazardous wastes from where they are generated to their ultimate disposal. This paper describes the development of the ANL Waste Minimization Plan and a pilot demonstration of the how the ANL Plan audited the hazardous waste generated within a selected divisions of ANL. It includes quantitative data on the generation and disposal of hazardous waste at ANL and describes potential ways to minimize hazardous wastes. 2 refs., 5 figs., 8 tabs

  4. A Mechanical Musculo-Skeletal System for a Human-Shaped Robot Arm

    OpenAIRE

    Koichi Koganezawa

    2014-01-01

    This paper presents a mechanical system with a similar configuration to a human musculo-skeletal system for use in anthropomorphic robots or as artificial limbs for disabled persons. First, a mechanical module called ANLES (Actuator with Non-Linear Elasticity System) is introduced. There are two types of ANLES: the linear-type ANLES and rotary-type ANLES. They can be used as a voluntary muscle in a wide-range of musculo-skeletal structures in which at least double actuators work in an antagon...

  5. Low-level radioactive waste management at Argonne National Laboratory-East

    International Nuclear Information System (INIS)

    This paper is an overview of the low-level radioactive waste management practices and treatment systems at Argonne National Laboratory - East (ANL-E). It addresses the systems, processes, types of waste treated, and the status and performance of the systems. ANL-E is a Department of Energy laboratory that is engaged in a variety of research projects, some of which generate radioactive waste, in addition a significant amount of radioactive waste remains from previous projects and decontamination and decommissioning of facilities where this work was performed

  6. Plutonium working group report on environmental, safety and health vulnerabilities associated with the Department's plutonium storage. Volume II, part 8: Argonne National Laboratory - East and New Brunswick Laboratory working group assessment team report

    International Nuclear Information System (INIS)

    The Plutonium Vulnerability Working Group Assessment Team No. 1 (WGAT-1) visited Argonne National Laboratory-East (ANL-E) and New Brunswick Laboratory (NBL), located at the ANL-Illinois site, from May 23 through May 27 and June 6 through June 10, 1994. The objective of the WGAT-1, the ANL-E Site Assessment Team (SAT), and the NBL SAT was to conduct a comprehensive assessment of the environment, safety, and health (ES ampersand H) vulnerabilities arising at ANL-E and NBL from the storage and handling of the Department's current plutonium holdings. During the first visit to the site (May 23-27), WGAT-1 toured various site facilities and, after each tour, met with SAT members to conduct 'table-top' discussions. In addition, various briefings were given to ANL-E management, NBL management, and DOE management. During the second visit (June 6-10), WGAT-1 completed their assessment report, and met with various site technical representatives

  7. Tiger team assessment of the Argonne Illinois site

    Energy Technology Data Exchange (ETDEWEB)

    1990-10-19

    This report documents the results of the Department of Energy's (DOE) Tiger Team Assessment of the Argonne Illinois Site (AIS) (including the DOE Chicago Operations Office, DOE Argonne Area Office, Argonne National Laboratory-East, and New Brunswick Laboratory) and Site A and Plot M, Argonne, Illinois, conducted from September 17 through October 19, 1990. The Tiger Team Assessment was conducted by a team comprised of professionals from DOE, contractors, consultants. The purpose of the assessment was to provide the Secretary of Energy with the status of Environment, Safety, and Health (ES H) Programs at AIS. Argonne National Laboratory-East (ANL-E) is the principal tenant at AIS. ANL-E is a multiprogram laboratory operated by the University of Chicago for DOE. The mission of ANL-E is to perform basic and applied research that supports the development of energy-related technologies. There are a significant number of ES H findings and concerns identified in the report that require prompt management attention. A significant change in culture is required before ANL-E can attain consistent and verifiable compliance with statutes, regulations and DOE Orders. ES H activities are informal, fragmented, and inconsistently implemented. Communication is seriously lacking, both vertically and horizontally. Management expectations are not known or commondated adequately, support is not consistent, and oversight is not effective.

  8. Argonne Code Center: compilation of program abstracts

    Energy Technology Data Exchange (ETDEWEB)

    Butler, M.K.; DeBruler, M.; Edwards, H.S.; Harrison, C. Jr.; Hughes, C.E.; Jorgensen, R.; Legan, M.; Menozzi, T.; Ranzini, L.; Strecok, A.J.

    1977-08-01

    This publication is the eleventh supplement to, and revision of, ANL-7411. It contains additional abstracts and revisions to some earlier abstracts and other pages. Sections of the complete document ANL-7411 are as follows: preface, history and acknowledgements, abstract format, recommended program package contents, program classification guide and thesaurus, and the abstract collection. (RWR)

  9. Interaction between astrocytes and neurons studied using a mathematical model of compartmentalized energy metabolism.

    Science.gov (United States)

    Aubert, Agnès; Costalat, Robert

    2005-11-01

    Understanding cerebral energy metabolism in neurons and astrocytes is necessary for the interpretation of functional brain imaging data. It has been suggested that astrocytes can provide lactate as an energy fuel to neurons, a process referred to as astrocyte-neuron lactate shuttle (ANLS). Some authors challenged this hypothesis, defending the classical view that glucose is the major energy substrate of neurons, at rest as well as in response to a stimulation. To test the ANLS hypothesis from a theoretical point of view, we developed a mathematical model of compartmentalized energy metabolism between neurons and astrocytes, adopting hypotheses highly unfavorable to ANLS. Simulation results can be divided between two groups, depending on the relative neuron versus astrocyte stimulation. If this ratio is low, ANLS is observed during all the stimulus and poststimulus periods (continuous ANLS), but a high ratio induces ANLS only at the beginning of the stimulus and during the poststimulus period (triphasic behavior). Finally, our results show that current experimental data on lactate kinetics are compatible with the ANLS hypothesis, and that it is essential to assess the neuronal and astrocytic NADH/NAD+ ratio changes to test the ANLS hypothesis. PMID:15931164

  10. Acceptable noise level with Danish, Swedish, and non-semantic speech materials

    DEFF Research Database (Denmark)

    Brännström, K Jonas; Lantz, Johannes; Nielsen, Lars Holme;

    2012-01-01

    ambas poblaciones. Muestra: Cuarenta sujetos daneses y 40 sujetos suecos normoyentes. Resultados: en ambas poblaciones los resultados de ANL fueron muy similares a los reportado previamente en estudios americanos. Generalmente, se vieron diferencias signifi cativas para el ANL entre poblaciones, también...

  11. Analytical Chemistry Laboratory progress report for FY 1998

    International Nuclear Information System (INIS)

    This report summarizes the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year (FY) 1998 (October 1997 through September 1998). This annual progress report, which is the fifteenth in this series for the ACL, describes effort on continuing projects, work on new projects, and contributions of the ACL staff to various programs at ANL

  12. Kongernes Jelling

    DEFF Research Database (Denmark)

    Høyer, Steen

    2001-01-01

    Nyt udstillingsbyggeri opført vest for kirken i Jelling. Anlægget rummet udover udstillingslokaler kontorer, bibliotek, multimediesal og cafe.......Nyt udstillingsbyggeri opført vest for kirken i Jelling. Anlægget rummet udover udstillingslokaler kontorer, bibliotek, multimediesal og cafe....

  13. Acceptable noise level

    DEFF Research Database (Denmark)

    Olsen, Steen Østergaard; Nielsen, Lars Holme; Lantz, Johannes;

    2012-01-01

    The acceptable noise level (ANL) is used to quantify the amount of background noise that subjects can accept while listening to speech, and is suggested for prediction of individual hearing-aid use. The aim of this study was to assess the repeatability of the ANL measured in normal-hearing subjects...

  14. The Effects of Speech Presentation Level on Acceptance of Noise in Listeners with Normal and Impaired Hearing

    Science.gov (United States)

    Freyaldenhoven, Melinda C.; Plyler, Patrick N.; Thelin, James W.; Hedrick, Mark S.

    2007-01-01

    Purpose: To compare the effects of speech presentation level on acceptance of noise in listeners with normal and impaired hearing. Method: Participants were listeners with normal (n = 24) and impaired (n = 46) hearing who were matched for conventional acceptable noise level (ANL). ANL was then measured at 8 fixed speech presentation levels (40,…

  15. Acceptance Noise Level: Effects of the Speech Signal, Babble, and Listener Language

    Science.gov (United States)

    Shi, Lu-Feng; Azcona, Gabrielly; Buten, Lupe

    2015-01-01

    Purpose: The acceptable noise level (ANL) measure has gained much research/clinical interest in recent years. The present study examined how the characteristics of the speech signal and the babble used in the measure may affect the ANL in listeners with different native languages. Method: Fifteen English monolingual, 16 Russian-English bilingual,…

  16. Argonne Code Center: compilation of program abstracts

    International Nuclear Information System (INIS)

    This publication is the eleventh supplement to, and revision of, ANL-7411. It contains additional abstracts and revisions to some earlier abstracts and other pages. Sections of the complete document ANL-7411 are as follows: preface, history and acknowledgements, abstract format, recommended program package contents, program classification guide and thesaurus, and the abstract collection

  17. Tiger team assessment of the Argonne Illinois site

    International Nuclear Information System (INIS)

    This report documents the results of the Department of Energy's (DOE) Tiger Team Assessment of the Argonne Illinois Site (AIS) (including the DOE Chicago Operations Office, DOE Argonne Area Office, Argonne National Laboratory-East, and New Brunswick Laboratory) and Site A and Plot M, Argonne, Illinois, conducted from September 17 through October 19, 1990. The Tiger Team Assessment was conducted by a team comprised of professionals from DOE, contractors, consultants. The purpose of the assessment was to provide the Secretary of Energy with the status of Environment, Safety, and Health (ES ampersand H) Programs at AIS. Argonne National Laboratory-East (ANL-E) is the principal tenant at AIS. ANL-E is a multiprogram laboratory operated by the University of Chicago for DOE. The mission of ANL-E is to perform basic and applied research that supports the development of energy-related technologies. There are a significant number of ES ampersand H findings and concerns identified in the report that require prompt management attention. A significant change in culture is required before ANL-E can attain consistent and verifiable compliance with statutes, regulations and DOE Orders. ES ampersand H activities are informal, fragmented, and inconsistently implemented. Communication is seriously lacking, both vertically and horizontally. Management expectations are not known or commondated adequately, support is not consistent, and oversight is not effective

  18. Klimaregnskab og Carbon Footprint beregning for Kommunekemi a/s

    DEFF Research Database (Denmark)

    Leinikka Dall, Ole; Wenzel, Henrik

    2009-01-01

    Klimaregnskab for anlægget i Nyborg og carbon footprint for: -forbrænding -uorganisk behandling -halmaskeanlæg Afrapporteret på tryk og indtastet i Simapro......Klimaregnskab for anlægget i Nyborg og carbon footprint for: -forbrænding -uorganisk behandling -halmaskeanlæg Afrapporteret på tryk og indtastet i Simapro...

  19. Analytical Chemistry Laboratory progress report for FY 1998.

    Energy Technology Data Exchange (ETDEWEB)

    Boparai, A. S.; Bowers, D. L.; Graczyk, D. G.; Green, D. W.; Lindahl, P. C.

    1999-03-29

    This report summarizes the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year (FY) 1998 (October 1997 through September 1998). This annual progress report, which is the fifteenth in this series for the ACL, describes effort on continuing projects, work on new projects, and contributions of the ACL staff to various programs at ANL.

  20. A Mechanical Musculo-Skeletal System for a Human-Shaped Robot Arm

    Directory of Open Access Journals (Sweden)

    Koichi Koganezawa

    2014-06-01

    Full Text Available This paper presents a mechanical system with a similar configuration to a human musculo-skeletal system for use in anthropomorphic robots or as artificial limbs for disabled persons. First, a mechanical module called ANLES (Actuator with Non-Linear Elasticity System is introduced. There are two types of ANLES: the linear-type ANLES and rotary-type ANLES. They can be used as a voluntary muscle in a wide-range of musculo-skeletal structures in which at least double actuators work in an antagonistic setup via some elastic elements. Next, an application of the two types of ANLES to a two-degree-of-freedom (DOF manipulator that has a similar configuration to the human elbow joint is shown. The experimental results of the joint stiffness and joint angle control elucidate that the developed mechanism effectively regulates joint stiffness in the same way as a musculo-skeletal system.

  1. Erhard Weigel - 1625 to 1699. Baroque patriarch of the early German Enlightenment. Proceedings of the colloquium held in Jena on March 20, 1999, on the occasion of the 300th anniversary of his death (German Title: Erhard Weigel - 1625 bis 1699. Barocker Erzvater der deutschen Frühaufklärung. Beiträge des Kolloquium anlässlich seines 300. Todestages am 20. März 1999 in Jena)

    Science.gov (United States)

    Schielicke, Reinhard E.; Herbst, Klaus-Dieter; Kratchowil, Stefan

    Erhard Weigel was Professor of Mathematics at Jena University between 1653 and 1699. He has got a place in the history of science thanks to his mathematical and astronomical knowledge, which he was able to demonstrate also in popular forms, his numerous inventions, his pedagogical enterprises, as well as his engagement for the Gregorian reform of the calender in the protestantic states, connected with the foundation of a scientific academy. This volumes contains a review article, followed by seven contributions with latest results of investigations about Weigel, presented at a colloquium held in Jena on the occasion of the 300th anniversary of his death.

  2. 同舟共济德国联邦总统霍斯特·克勒2007年5月26日出席同济大学百年校庆的演讲%Rede des Bundespr(a)sidenten Horst K(o)hler anl(a)sslich der Feiern zum 100.Jahrestag der Gründung der Tongji-Universit(a)t am 26.Mai 2007 "Die in einem Boot sitzen,sollen sich helfen"

    Institute of Scientific and Technical Information of China (English)

    张瑞

    2007-01-01

    @@ 尊敬的万部长, 尊敬的女士们、先生们: 很高兴能到这里来、在这个大厅里面对着全会说德语的人讲话.不用翻译直接交流,是一种美好的感觉. 值此同济大学百年校庆之际到贵校作客,我感到很荣幸,也非常高兴.同济大学是我们两国人民之间友谊最美好的见证之一.我向所有在这里教书、学习和工作的人为了这个美好而值得骄傲的庆典表示祝贺.借此出席百年校庆的良机,我也祝贺万教授就任部长.

  3. Conversion of the EBWR into a radioactive waste storage facility

    International Nuclear Information System (INIS)

    This paper describes the environmental and engineering issues of interest during the conversion of the experimental boiling water reactor (EBWR) into the radioactive waste storage facility (RWSF) at Argonne National Laboratory-East (ANL-E), Argonne, Illinois. The existing EBWR at ANL-E was constructed in the late 1950s. The decontamination and decommissioning of the EBWR is in progress and nearing completion. This facility will be used to provide sufficient radioactive waste storage to meet ANL-E's needs until the Waste Isolation Pilot Plant near Carlsbad, New Mexico, will accept the waste. During the conceptual design phase of the project, the cost for the construction of a new RWSF was estimated at approximately $6.25 million as compared to a $2.7 million estimate for the conversion of the EBWR into the RWSF. These estimates include costs for engineering, permits, and construction. In anticipation of budget recision, ANL took a proactive role to further reduce the project cost by approximately $0.5 million using a value engineering process and redefining the storage requirements

  4. The relationship between acceptable noise level and electrophysiologic auditory brainstem and cortical signal to noise ratios

    Directory of Open Access Journals (Sweden)

    Hemanth N. Shetty

    2014-03-01

    Full Text Available The following objectives of the study were formulated: i to investigate differences in measured signal to noise ratios while recording speech-evoked auditory brainstem response (cABR and cortical late latency response (LLR in low and high acceptable noise level (ANL groups; and ii to compare peak to peak amplitude of cABR (V-A and LLR (N1-P2 in low and high ANL groups. A total of 23 normal hearing participants was included in the study. One shot replicative and partly exploratory research design was utilized to study the effect of signal to noise ratio in a recorded waveform on afferent mechanism, assessed by cABR and LLR on participants having values of ANL of ≤7 (low ANL group and ≥13 (high ANL group. There were no differences in signal to noise ratio in the recorded waveforms of cABR and LLR between low and high ANL groups at both brainstem and cortical levels. However, the peak to peak amplitude of V-A of cABR and N1-P2 of LLR were both statistically larger in the high ANL group compared to their counterpart. The signal to noise ratio in recorded waveforms did not differentiated cABR (V-A or LLR (N1-P2 in low and high ANL groups. However, Larger peak to peak amplitudes in the high ANL group suggests differences higher processing centers in the upper brainstem to the auditory cortex. The findings of the study may be useful in determining the patient acceptability of noise.

  5. Institutional plan. Fiscal year, 1997--2002

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    The Institutional Plan is the culmination of Argonne`s annual planning cycle. The document outlines what Argonne National Laboratory (ANL) regards as the optimal development of programs and resources in the context of national research and development needs, the missions of the Department of Energy and Argonne National Laboratory, and pertinent resource constraints. It is the product of ANL`s internal planning process and extensive discussions with DOE managers. Strategic planning is important for all of Argonne`s programs, and coordination of planning for the entire institution is crucial. This Institutional Plan will increasingly reflect the planning initiatives that have recently been implemented.

  6. An evaluation of alternative reactor vessel cutting technologies for the experimental boiling water reactor at Argonne National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Boing, L.E.; Henley, D.R. (Argonne National Lab., IL (USA)); Manion, W.J.; Gordon, J.W. (Nuclear Energy Services, Inc., Danbury, CT (USA))

    1989-12-01

    Metal cutting techniques that can be used to segment the reactor pressure vessel of the Experimental Boiling Water Reactor (EBWR) at Argonne National Laboratory (ANL) have been evaluated by Nuclear Energy Services. Twelve cutting technologies are described in terms of their ability to perform the required task, their performance characteristics, environmental and radiological impacts, and cost and schedule considerations. Specific recommendations regarding which technology should ultimately be used by ANL are included. The selection of a cutting method was the responsibility of the decommissioning staff at ANL, who included a relative weighting of the parameters described in this document in their evaluation process. 73 refs., 26 figs., 69 tabs.

  7. An evaluation of alternative reactor vessel cutting technologies for the experimental boiling water reactor at Argonne National Laboratory

    International Nuclear Information System (INIS)

    Metal cutting techniques that can be used to segment the reactor pressure vessel of the Experimental Boiling Water Reactor (EBWR) at Argonne National Laboratory (ANL) have been evaluated by Nuclear Energy Services. Twelve cutting technologies are described in terms of their ability to perform the required task, their performance characteristics, environmental and radiological impacts, and cost and schedule considerations. Specific recommendations regarding which technology should ultimately be used by ANL are included. The selection of a cutting method was the responsibility of the decommissioning staff at ANL, who included a relative weighting of the parameters described in this document in their evaluation process. 73 refs., 26 figs., 69 tabs

  8. A hard x-ray micro-analytical beamline at the CAMD synchrotron

    International Nuclear Information System (INIS)

    Argonne National Laboratory (ANL) is collaborating with Louisiana State University (LSU) in constructing a synchrotron x-ray micro-analytical beamline at the Center for Advanced Microstructures and Devices (CAMD) in Baton Rouge. This project grew from earlier work at the National Synchrotron Light source (NSLS), where a team of ANL researchers developed techniques to examine small-scale structures in diffusion zones of a variety of materials. The ANL/CAMD beamline will use x-ray fluorescence, diffraction, and absorption spectroscopy techniques to reveal both compositional and structural information on a microscopic scale

  9. Spent fuel treatment and mineral waste form development at Argonne National Laboratory-West

    International Nuclear Information System (INIS)

    At Argonne National Laboratory-West (ANL-West) there are several thousand kilograms of metallic spent nuclear fuel containing bond sodium. This fuel will be treated in the Fuel Conditioning Facility (FCF) at ANL-West to produce stable waste forms for storage and disposal. Both mineral and metal high-level waste forms will be produced. The mineral waste form will contain the active metal fission products and the transuranics. Cold small-scale waste form testing has been on-going at Argonne in Illinois. Large-scale testing is commencing at ANL-West

  10. Effects of Mandarin Speech Rate on Mandarin AcceptabIe Noise LeveI Test in NormaI Hearing AduIts%语速对正常青年人可接受噪声级的影响

    Institute of Scientific and Technical Information of China (English)

    苏俊; 李文靖; 张云美; 周慧

    2014-01-01

    Objective To investigate the effects of Mandarin speech rate on Mandarin acceptable noise level test in normal hearing adults.Methods Using the national Putonghua proficiency test material to produce 0.8 times,1.0 times and 1.2 times speed rate of ANL test materials.ANL tests were measured for 58 normal hearing a-dults using different peed matetrials.For each case,the most comfortable loudness(MCL)and background noise lev-el(BNL)were found.The ANL was then computed by subtracting the mean BNL from MCL.ResuIts Statistic anal-ysis indicated that there were no significant differences of the ANL(P>0.05)among the differenct speed materials, there were no correlation between MCL-ANL (P>0.05),negatively correlation between BNL-ANL(P<0.05)a-mong the differenct speed materials.ConcIusion Mandarin speech speed does not effect ANL test,the more the in-dividual’s ability to accept the background noise,the smaller the value of ANL.%目的:研究语速是否对可接受噪声级(acceptable noise level,ANL)测试产生影响。方法选取国家普通话水平测试用朗读作品的音频材料,制作出0.8、1和1.2倍语速的 ANL 测试材料,对58名听力正常的青年人进行3种语速测试材料的 ANL 测试,分别获得最舒适响度级(most comfortable loudness,MCL),最大背景噪声级(background noise level,BNL),并根据 ANL=MCL—BNL 计算出 ANL 值,进行统计学分析。结果0.8、1和1.2倍语速条件下 ANL 值分别为2.88±3.81、2.76±3.76、3.16±3.72 dB HL,三种语速下的 MCL、BNL、ANL 值差异无统计学意义(P>0.05),0.8、1和1.2倍语速条件下 MCL 与 ANL 均无相关关系(P>0.05),BNL 与 ANL均呈负相关(P<0.01)。结论本研究发现三种语速 ANL 测试材料的语速并不影响 ANL 值;个体接受背景噪声的能力越强,其 ANL 值越小。

  11. Finite-element treatment of concrete cracking and thermal structural analysis

    International Nuclear Information System (INIS)

    The objective of this presentation is to describe the work on analytical modeling of concrete behavior at the Argonne National Laboratory (ANL) stressing in particular the approaches that are found to be most promising

  12. Risk assessment of seeps from the 317 Area of Argonne National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-17

    Chlorinated hydrocarbon contaminants have recently been detected in groundwater seeps on forest preserve property south of the 317 Area at ANL. The 317 Area is near ANL`s southern boundary and is considered the source of the contamination. Five seeps are about 200 m south of the ANL property line and about same distance from the nearest developed trails in the forest preserve. Conservative assumptions were used to assess the possibility of adverse health effects associated with forest preserve seeps impacted by the 317 Area. Results indicate that neither cancer risks nor noncarcinogenic effects associated with exposures to seep contaminants are a concern; thus, the area is safe for all visitors. The ecological impact study found that the presence of the three contaminants (CCl{sub 4}, CHCl{sub 3}, tetrachloroethylene) in the seep water does not pose a risk to biota in the area.

  13. Decontamination and Decommissioning activities photobriefing book FY 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    The Decontamination and Decommissioning (D and D) Program at Argonne National Laboratory-East (ANL-E) is dedicated to the safe and cost effective D{ampersand}D of surplus nuclear facilities. There is currently a backlog of more than 7,000 contaminated US Department of Energy facilities nationwide. Added to this are 110 licensed commercial nuclear power reactors operated by utilities learning to cope with deregulation and an aging infrastructure that supports the commercial nuclear power industry, as well as medical and other uses of radioactive materials. With this volume it becomes easy to understand the importance of addressing the unique issues and objectives associated with the D{ampersand}D of surplus nuclear facilities. This photobriefing book summarizes the decontamination and decommissioning projects and activities either completed or continuing at the ANL-E site during the year.

  14. High Energy Physics Division semiannual report of research activities, January 1, 1990--June 30, 1990

    International Nuclear Information System (INIS)

    This report discusses research programs at ANL in High Energy Physics. The major categories of this research are: experimental programs; theoretical program; experimental facilities research; accelerator research and development; and SSC detector research and development

  15. Decontamination and dismantlement of the JANUS Reactor at Argonne National Laboratory-East. Project final report

    International Nuclear Information System (INIS)

    The decontamination and dismantlement of the JANUS Reactor at Argonne National Laboratory-East (ANL-E) was completed in October 1997. Descriptions and evaluations of the activities performed and analyses of the results obtained during the JANUS D and D Project are provided in this Final Report. The following information is included: objective of the JANUS D and D Project; history of the JANUS Reactor facility; description of the ANL-E site and the JANUS Reactor facility; overview of the D and D activities performed; description of the project planning and engineering; description of the D and D operations; summary of the final status of the JANUS Reactor facility based upon the final survey results; description of the health and safety aspects of the project, including personnel exposure and OSHA reporting; summary of the waste minimization techniques utilized and total waste generated by the project; and summary of the final cost and schedule for the JANUS D and D Project

  16. Type of speech material affects Acceptable Noise Level test outcome

    Directory of Open Access Journals (Sweden)

    Xaver eKoch

    2016-02-01

    Full Text Available The Acceptable Noise Level (ANL test, in which individuals indicate what level of noise they are willing to put up with while following speech, has been used to guide hearing aid fitting decisions and has been found to relate to prospective hearing aid use. Unlike objective measures of speech perception ability, ANL outcome is not related to individual hearing loss or age, but rather reflects an individual's inherent acceptance of competing noise while listening to speech. As such, the measure may predict aspects of hearing aid success. Crucially, however, recent studies have questioned its repeatability (test-retest reliability. The first question for this study was whether the inconsistent results regarding the repeatability of the ANL test may be due to differences in speech material types used in previous studies. Second, it is unclear whether meaningfulness and semantic coherence of the speech modify ANL outcome. To investigate these questions, we compared ANLs obtained with three types of materials: the International Speech Test Signal (ISTS, which is non-meaningful and semantically non-coherent by definition, passages consisting of concatenated meaningful standard audiology sentences, and longer fragments taken from conversational speech. We included conversational speech as this type of speech material is most representative of everyday listening. Additionally, we investigated whether ANL outcomes, obtained with these three different speech materials, were associated with self-reported limitations due to hearing problems and listening effort in everyday life, as assessed by a questionnaire. ANL data were collected for 57 relatively good-hearing adult participants with an age range representative for hearing aid users. Results showed that meaningfulness, but not semantic coherence of the speech material affected ANL. Less noise was accepted for the non-meaningful ISTS signal than for the meaningful speech materials. ANL repeatability was

  17. Type of Speech Material Affects Acceptable Noise Level Test Outcome.

    Science.gov (United States)

    Koch, Xaver; Dingemanse, Gertjan; Goedegebure, André; Janse, Esther

    2016-01-01

    The acceptable noise level (ANL) test, in which individuals indicate what level of noise they are willing to put up with while following speech, has been used to guide hearing aid fitting decisions and has been found to relate to prospective hearing aid use. Unlike objective measures of speech perception ability, ANL outcome is not related to individual hearing loss or age, but rather reflects an individual's inherent acceptance of competing noise while listening to speech. As such, the measure may predict aspects of hearing aid success. Crucially, however, recent studies have questioned its repeatability (test-retest reliability). The first question for this study was whether the inconsistent results regarding the repeatability of the ANL test may be due to differences in speech material types used in previous studies. Second, it is unclear whether meaningfulness and semantic coherence of the speech modify ANL outcome. To investigate these questions, we compared ANLs obtained with three types of materials: the International Speech Test Signal (ISTS), which is non-meaningful and semantically non-coherent by definition, passages consisting of concatenated meaningful standard audiology sentences, and longer fragments taken from conversational speech. We included conversational speech as this type of speech material is most representative of everyday listening. Additionally, we investigated whether ANL outcomes, obtained with these three different speech materials, were associated with self-reported limitations due to hearing problems and listening effort in everyday life, as assessed by a questionnaire. ANL data were collected for 57 relatively good-hearing adult participants with an age range representative for hearing aid users. Results showed that meaningfulness, but not semantic coherence of the speech material affected ANL. Less noise was accepted for the non-meaningful ISTS signal than for the meaningful speech materials. ANL repeatability was comparable across

  18. Fuel conditioning facility electrorefiner start-up results

    International Nuclear Information System (INIS)

    At ANL-West, there are several thousand kilograms of metallic spent nuclear fuel containing bond sodium. This fuel will be treated in the Fuel Conditioning Facility (FCF) at ANL-West to produce stable waste forms for storage and disposal. The treatment operations will make use of an electrometallurgical process employing molten salts and liquid metals. The treatment equipment is presently undergoing testing with depleted uranium. Operations with irradiated fuel will commence when the environmental evaluation for FCF is complete

  19. Memory of a myth

    DEFF Research Database (Denmark)

    Odgaard, Ulla

    I 1954 fandt arkæolog fra Nationalmuseet i Danmark, Jørgen Meldgaard, et unikt anlæg fra den sene dorset kultur (ca. 500-1200 e.Kr.) på bopladsen Alarnerk i Igloolik området ved Foxe Basin i det nordøstlige Canada. Anlægget indeholdt menneskeknogler (fra et barn), og Meldgaard mente, at der var t...

  20. Evidence of a treatment dose response in acute nonlymphocytic leukemias which occur after therapy of non-Hodgkin's lymphoma

    International Nuclear Information System (INIS)

    We evaluated the occurrence of second cancers among 517 patients with non-Hodgkin's lymphoma (NHL) treated at the National Cancer Institute. Nine cases of acute nonlymphocytic leukemia (ANL) were observed compared to 0.08 cases expected (ratio of observed to expected cases, 105; 95% confidence limits, 48; 199). The excess risk of ANL was 4.1 cases per 1000 patients per year; the cumulative risk of ANL at 10 years was 7.9 +/- 3.2% (S.E.). A case-control study within the NHL cohort revealed that patients treated with both radiation and chemotherapy were at greater risk of ANL than were patients who received single-modality therapy (relative risk, 6.0; p less than 0.05), especially if the therapy included total-body or hemibody radiation. A positive correlation between cumulative radiation dose to the bone marrow and risk of ANL was demonstrated, independent of chemotherapy duration. A similar correlation between chemotherapy dose and risk of ANL was suggested but could not be proven with the available data. An apparent association between ANL risk and indolent NHL histological subtypes was due to the significantly larger amounts of potentially leukemogenic therapy to which these patients were repeatedly exposed. Only one case of ANL occurred among NHL patients whose initial therapy produced a durable complete remission. Our data are compatible with a multistep model of leukemogenesis and also underscore the need for curative NHL treatment regimens which minimize the duration and quantity of therapy required for optimum patient management

  1. Acceptable noise level with Danish, Swedish, and non-semantic speech materials

    DEFF Research Database (Denmark)

    Brännström, K Jonas; Lantz, Johannes; Nielsen, Lars Holme;

    2012-01-01

    confortable. El objetivo de este estudio fue generar las versiones sueca, danesa y una no-semántica de la prueba ANL e investigar el desempeño de sujetos normoyentes daneses y suecos en estas pruebas. Diseño: Se midió el ANL utilizando un discurso continuo en danés y sueco con dos diferentes ruidos: ruido con...

  2. Wave Star

    DEFF Research Database (Denmark)

    Kramer, Morten; Frigaard, Peter

    Nærværende rapport beskriver modelforsøg udført på Aalborg Universitet, Institut for Byggeri og Anlæg med bølgeenergianlæget Wave Star.......Nærværende rapport beskriver modelforsøg udført på Aalborg Universitet, Institut for Byggeri og Anlæg med bølgeenergianlæget Wave Star....

  3. Analytical chemistry laboratory. Progress report for FY 1997

    Energy Technology Data Exchange (ETDEWEB)

    Green, D.W.; Boparai, A.S.; Bowers, D.L. [and others

    1997-12-01

    The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year (FY) 1997 (October 1996 through September 1997). This annual progress report is the fourteenth in this series for the ACL, and it describes continuing effort on projects, work on new projects, and contributions of the ACL staff to various programs at ANL.

  4. Reactor D and D at Argonne National Laboratory - lessons learned

    International Nuclear Information System (INIS)

    This paper focuses on the lessons learned during the decontamination and decommissioning (D and D) of two reactors at Argonne National Laboratory-East (ANL-E). The Experimental Boiling Water Reactor (EBWR) was a 100 MW(t), 5 MSV(e) proof-of-concept facility. The Janus Reactor was a 200 kW(t) reactor located at the Biological Irradiation Facility and was used to study the effects of neutron radiation on animals

  5. Type of Speech Material Affects Acceptable Noise Level Test Outcome

    OpenAIRE

    Koch, Xaver; Dingemanse, Gertjan; Goedegebure, André; Janse, Esther

    2016-01-01

    The acceptable noise level (ANL) test, in which individuals indicate what level of noise they are willing to put up with while following speech, has been used to guide hearing aid fitting decisions and has been found to relate to prospective hearing aid use. Unlike objective measures of speech perception ability, ANL outcome is not related to individual hearing loss or age, but rather reflects an individual’s inherent acceptance of competing noise while listening to speech. As such, the measu...

  6. Type of speech material affects Acceptable Noise Level test outcome

    OpenAIRE

    Xaver eKoch; Gertjan eDingemanse; André eGoedegebure; Esther eJanse

    2016-01-01

    The Acceptable Noise Level (ANL) test, in which individuals indicate what level of noise they are willing to put up with while following speech, has been used to guide hearing aid fitting decisions and has been found to relate to prospective hearing aid use. Unlike objective measures of speech perception ability, ANL outcome is not related to individual hearing loss or age, but rather reflects an individual's inherent acceptance of competing noise while listening to speech. As such, the measu...

  7. Acceptable noise level

    DEFF Research Database (Denmark)

    Olsen, Steen Østergaard; Nielsen, Lars Holme; Lantz, Johannes;

    2012-01-01

    The acceptable noise level (ANL) is used to quantify the amount of background noise that subjects can accept while listening to speech, and is suggested for prediction of individual hearing-aid use. The aim of this study was to assess the repeatability of the ANL measured in normal-hearing subjects...... using running Danish and non-semantic speech materials as stimuli and modulated speech-spectrum and multi-talker babble noises as competing stimuli....

  8. Ureteroscopy-Assisted Retrograde Nephrostomy (UARN) after Anatrophic Nephrolithotomy

    OpenAIRE

    Takashi Kawahara; Hiroki Ito; Hideyuki Terao; Yoshitake Kato; Takehiko Ogawa; Hiroji Uemura; Yoshinobu Kubota; Junichi Matsuzaki

    2012-01-01

    Introduction. Open surgical anatrophic nephrolithotomy (ANL) had been the standard treatment for large renal calculi prior to the development of endoscopic devices and endoscopic techniques. A previous report described the efficacy of ureteroscopy-assisted retrograde nephrostomy (UARN) and presented a case of renal calculi successfully treated with UARN during percutaneous nephrolithotomy (PCNL) in a patient after ANL. Case Presentation. A 61-year-old male with left renal calculi was referred...

  9. Southern Great Plains Safety Orientation

    Energy Technology Data Exchange (ETDEWEB)

    Schatz, John

    2014-05-01

    Welcome to the Atmospheric Radiation Measurement (ARM) Climate Research Facility (ARM) Southern Great Plains (SGP) site. This U.S. Department of Energy (DOE) site is managed by Argonne National Laboratory (ANL). It is very important that all visitors comply with all DOE and ANL safety requirements, as well as those of the Occupational Safety and Health Administration (OSHA), the National Fire Protection Association, and the U.S. Environmental Protection Agency, and with other requirements as applicable.

  10. ELRA: The exposure limiting robotic apparatus

    International Nuclear Information System (INIS)

    A problem situation involving the handling of radioactive material at Argonne National Laboratory -- West (ANL-W) was solved through the use of remote handling techniques, providing significant exposure reduction to personnel. Robotic devices can be useful, but the cost of a robot is often prohibitive for many jobs. A low cost, disposable robot was built which successfully removed a highly radioactive and potentially explosive system from a hot cell at ANL-W

  11. Vitrification of low-level radioactive mixed waste at Argonne National Laboratory

    International Nuclear Information System (INIS)

    Argonne National Laboratory-East (ANL-E) is proceeding with plans to use vitrification to treat low-level radioactive mixed wastes (LLMW) generated on-site. The objective is to install a full-scale vitrification system at ANL-E capable of processing the entire annual generation of selected LLMW streams. Crucible glass studies with actual mixed waste streams have produced sodium borosilicate glasses under conditions achievable in commercially available melters. These same glass compositions, spiked with toxic metals above the expected levels in actual wastes, pass the Toxicity Characteristic Leaching Procedure (TCLP) test. Earlier evaluations of the likely off-gases that will result from vitrification indicated that the primary off-gases will include compounds of SOx, NOx, and CO2. These evaluations are being experimentally confirmed with a mass spectrometer analysis of the gases evolved from samples of the ANL-E wastes. The composition of the melter feed can be adjusted to minimize volatilization of some components, if necessary. The full-scale melter will be designed to handle the annual generation of at least three LLMW waste streams: evaporator concentrator bottoms sludge (ECB), storage tank sludge (STS), and HEPA filter media. Each waste stream is mixed waste by virtue of its failure to pass the TCLP test with respect to toxic metal leaching. Additional LLMW streams under consideration for vitrification include historical mixed waste glass from past operations and spent abrasive from a planned decontamination facility

  12. Argonne National Laboratory--East site environmental report for calendar year 1990

    International Nuclear Information System (INIS)

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1990. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, bottom sediment, and milk samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects from past activities

  13. Argonne National Laboratory-East site environmental report for calendar year 1992

    International Nuclear Information System (INIS)

    This report discusses the results of the Environmental Protection Program at Argonne National Laboratory-East (ANL) for 1992. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed

  14. Argonne National Laboratory-East site environmental report for calendar year 1991

    International Nuclear Information System (INIS)

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1991. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. Chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects from past activities

  15. Argonne National Laboratory site environmental report for calendar year 2004.

    Energy Technology Data Exchange (ETDEWEB)

    Golchert, N. W.; Kolzow, R. G.

    2005-09-02

    This report discusses the accomplishments of the environmental protection program at Argonne National Laboratory (ANL) for calendar year 2004. The status of ANL environmental protection activities with respect to compliance with the various laws and regulations is discussed, along with the progress of environmental corrective actions and restoration projects. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared with applicable guidelines and standards. A variety of radionuclides were measured in air, surface water, on-site groundwater, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured, and the potential for radiation exposure to off-site population groups was estimated. Results are interpreted in terms of the origin of the radioactive and chemical substances (i.e., natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A U.S. Department of Energy dose calculation methodology, based on International Commission on Radiological Protection recommendations and the U.S. Environmental Protection Agency's CAP-88 (Clean Air Act Assessment Package-1988) computer code, was used in preparing this report.

  16. Argonne National Laboratory-East site environmental report for calendar year 1994

    Energy Technology Data Exchange (ETDEWEB)

    Golchert, N.W.; Kolzow, R.G.

    1995-05-01

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1994. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK COMPUTER CODE, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects.

  17. Argonne National Laboratory-East site environmental report for calendar year 1993

    International Nuclear Information System (INIS)

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1993. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects from past activities

  18. Argonne National Laboratory--East site environmental report for calendar year 1990

    Energy Technology Data Exchange (ETDEWEB)

    Golchert, N.W.; Duffy, T.L.; Moos, L.P.

    1991-07-01

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1990. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, bottom sediment, and milk samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects from past activities.

  19. Argonne National Laboratory-East site environmental report for calendar year 1993

    Energy Technology Data Exchange (ETDEWEB)

    Golchert, N.W.; Kolzow, R.G. [Argonne National Lab., IL (United States). Environment and Waste Management Program

    1994-05-01

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1993. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK computer code, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects from past activities.

  20. Argonne National Laboratory-East site environmental report for calendar year 1994

    International Nuclear Information System (INIS)

    This report discusses the results of the environmental protection program at Argonne National Laboratory-East (ANL) for 1994. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared to applicable guidelines and standards. A variety of radionuclides was measured in air, surface water, groundwater, soil, grass, and bottom sediment samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the surveillance program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations and the CAP-88 version of the EPA-AIRDOSE/RADRISK COMPUTER CODE, is used in this report. The status of ANL environmental protection activities with respect to the various laws and regulations which govern waste handling and disposal is discussed. This report also discusses progress being made on environmental corrective actions and restoration projects

  1. Wetlands of Argonne National Laboratory-East DuPage County, Illinois

    Energy Technology Data Exchange (ETDEWEB)

    Van Lonkhuyzen, R.A.; LaGory, K.E.

    1994-03-01

    Jurisdictional wetlands of the Argonne National Laboratory-East (ANL-E) site in DuPage County, Illinois, were delineated in the summer and autumn of 1993 in accordance with the 1987 US Army Corps of Engineers methodology. Potential wetland sites with an area greater than 500 m{sup 2} (0.05 ha [0.124 acre]) were identified for delineation on the basis of aerial photographs, the DuPage County soil survey, and reconnaissance-level field studies. To qualify as a jurisdictional wetland, an area had to support a predominance of hydrophytic vegetation as well as have hydric soil and wetland hydrology. Thirty-five individual jurisdictional wetlands were delineated at ANL-E, totaling 180,604 m{sup 2} (18.1 ha [44.6 acres]). These wetlands were digitized onto the ANL-E site map for use in project planning. Characteristics of each wetland are presented -- including size, dominant plant species and their indicator status, hydrologic characteristics (including water source), and soil characteristics.

  2. Decontamination and decommissioning of 61 plutonium gloveboxes in D-Wing, Building 212 Argonne National Laboratory-East: Final project report

    International Nuclear Information System (INIS)

    Argonne National Laboratory-East (ANL-E) is a government-owned, contractor operated, multipurpose research facility located 25 miles southwest of downtown Chicago on 689 hectares (1,700 acres) in DuPage County, Illinois, as shown in Figure 1.1. Building 212 is located in the central area of ANL-E, as shown in Figure 1.2. The purpose of this project was to eliminate the risk of radioactive material release from the contaminated glovebox systems and to make the laboratories available for unrestricted use. The following work objectives were established: (1) Identify and remove radioactive materials for return to ANL-E Special Materials control. (2) Remove and package the radioactively contaminated materials and equipment from the gloveboxes. (3) Decontaminate the gloveboxes to nontransuranic (non-TRU) levels. (4) Size-reduce and package the gloveboxes and support systems. (5) Document and dispose of the radioactive and mixed waste. (6) Decontaminate, survey, and release the nine laboratories and corridor areas for unrestricted use

  3. JANUS reactor d and d project

    International Nuclear Information System (INIS)

    Argonne National Laboratory (ANL-E) has recently completed the decontamination and decommissioning (D and D) of the JANUS Reactor Facility located in Building 202. The 200 KW reactor operated from August 1963 to March 1992. The facility was used to study the effects of both high and low doses of fission neutrons in animals. There were two exposure rooms on opposite sides of the reactor and the reactor was therefore named after the two-faced Roman god. The High Dose Room was capable of specimen exposure at a dose rate of 3,600 rads per hour. During calendar year 1996 a detailed characterization of the facility was performed by ANL-E Health Physics personnel. ANL-E Analytical Services performed the required sample analysis. An Auditable Safety Analysis and an Environmental Assessment were completed. D and D plans, procedures and procurement documents were prepared and approved. A D and D subcontractor was selected and a firm, fixed price contract awarded for the field work and final survey effort. The D and D subcontractor was mobilized to ANL-E in January 1997. Electrical isolation of all reactor equipment and control panels was accomplished and the equipment removed. A total of 207,230 pounds (94,082 Kg) of lead shielding was removed, surveyed and sampled, and free-released for recycle. All primary and secondary piping was removed, size reduced and packaged for disposal or recycled as appropriate. The reactor vessel was removed, sized reduced and packaged as radioactive waste in April. The activated graphite block reflector was removed next, followed by the bioshield concrete and steel. All of this material was packaged as low level waste. Total low level radioactive waste generation was 4002.1 cubic feet (113.3 cubic meters). Mixed waste generation was 538 cubic feet (15.2 cubic meters). The Final Release Survey was completed in September. The project field work was completed in 38 weeks without any lost-time accidents, personnel contaminations or unplanned

  4. Preliminary Engineering Report contaminated groundwater seeps 317/319/ENE area

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-10-01

    When the Resource Conservation and Recovery Act Facility Investigation (RFI) in the 317/319/ENE Area of Argonne National Laboratory-East (ANL-E) was being completed, groundwater was discovered moving to the surface through a series of seeps. The seeps are located approximately 600 ft south of the ANL fence line in Waterfall Glen Forest Preserve. Samples of this water were collected and analyzed for selected parameters. Two of five seeps sampled were found to contain detectable levels of organic contaminants. Three chemical species were identified: chloroform (14-25 {mu}g/L), carbon tetrachloride (56-340 {mu}g/L), and tetrachloroethylene (3-6 {mu}g/L). The other seeps did not contain detectable levels of volatile organic compounds (VOCs). The water issuing from these two contaminated seeps flows into a narrow ravine, where it is visible as a trickle of water flowing through sand and gravel deposits on the floor of the ravine. Approximately 100-ft downstream of the seep area, the contaminated water is no longer visible, having drained back into the soil in the bed of the ravine. Figure 1 shows the location of the 317/319/ENE Area in relation to the ANL-E site and the Waterfall Glen Forest Preserve.

  5. Are the noise levels acceptable in a built environment like Hong Kong?

    Directory of Open Access Journals (Sweden)

    Wai Ming To

    2015-01-01

    Full Text Available Governments all over the world have enacted environmental noise directives and noise control ordinances/acts to protect tranquility in residential areas. However, there is a lack of literature on the evaluation of whether the Acceptable Noise Levels (ANLs stipulated in the directive/ordinance/act are actually achievable. The study aimed at measuring outdoor environmental noise levels in Hong Kong and identifying whether the measured noise levels are lower than the stipulated ANLs at 20 categories of residential areas. Data were gathered from a territory-wide noise survey. Outdoor noise measurements were conducted at 203 residential premises in urban areas, low-density residential areas, rural areas, and other areas. In total, 366 daytime hourly Leq outdoor noise levels, 362 nighttime hourly Leq outdoor noise levels, and 20 sets of daily, that is, 24 Leq,1-h outdoor noise levels were recorded. The mean daytime Leq,1-h values ranged 54.4-70.8 dBA, while the mean nighttime Leq,1-h values ranged 52.6-67.9 dBA. When the measured noise levels were compared with the stipulated ANLs, only three out of the 20 categories of areas had outdoor noise levels below ANLs during daytime. All other areas (and all areas during nighttime were found to have outdoor noise levels at or above ANLs.

  6. Analytical Chemistry Laboratory. Progress report for FY 1996

    Energy Technology Data Exchange (ETDEWEB)

    Green, D.W.; Boparai, A.S.; Bowers, D.L.

    1996-12-01

    The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year (FY) 1996. This annual report is the thirteenth for the ACL. It describes effort on continuing and new projects and contributions of the ACL staff to various programs at ANL. The ACL operates in the ANL system as a full-cost-recovery service center, but has a mission that includes a complementary research and development component: The Analytical Chemistry Laboratory will provide high-quality, cost-effective chemical analysis and related technical support to solve research problems of our clients -- Argonne National Laboratory, the Department of Energy, and others -- and will conduct world-class research and development in analytical chemistry and its applications. Because of the diversity of research and development work at ANL, the ACL handles a wide range of analytical chemistry problems. Some routine or standard analyses are done, but the ACL usually works with commercial laboratories if our clients require high-volume, production-type analyses. It is common for ANL programs to generate unique problems that require significant development of methods and adaption of techniques to obtain useful analytical data. Thus, much of the support work done by the ACL is very similar to our applied analytical chemistry research.

  7. Analytical Chemistry Laboratory, progress report for FY 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-01

    The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year (FY) 1993 (October 1992 through September 1993). This annual report is the tenth for the ACL and describes continuing effort on projects, work on new projects, and contributions of the ACL staff to various programs at ANL. The Analytical Chemistry Laboratory is a full-cost-recovery service center, with the primary mission of providing a broad range of analytical chemistry support services to the scientific and engineering programs at ANL. The ACL also has research programs in analytical chemistry, conducts instrumental and methods development, and provides analytical services for governmental, educational, and industrial organizations. The ACL handles a wide range of analytical problems. Some routine or standard analyses are done, but it is common for the Argonne programs to generate unique problems that require development or modification of methods and adaption of techniques to obtain useful analytical data. The ACL is administratively within the Chemical Technology Division (CMT), its principal ANL client, but provides technical support for many of the technical divisions and programs at ANL. The ACL has four technical groups--Chemical Analysis, Instrumental Analysis, Organic Analysis, and Environmental Analysis--which together include about 45 technical staff members. Talents and interests of staff members cross the group lines, as do many projects within the ACL.

  8. Preliminary Engineering Report contaminated groundwater seeps 317/319/ENE area

    International Nuclear Information System (INIS)

    When the Resource Conservation and Recovery Act Facility Investigation (RFI) in the 317/319/ENE Area of Argonne National Laboratory-East (ANL-E) was being completed, groundwater was discovered moving to the surface through a series of seeps. The seeps are located approximately 600 ft south of the ANL fence line in Waterfall Glen Forest Preserve. Samples of this water were collected and analyzed for selected parameters. Two of five seeps sampled were found to contain detectable levels of organic contaminants. Three chemical species were identified: chloroform (14-25 μg/L), carbon tetrachloride (56-340 μg/L), and tetrachloroethylene (3-6 μg/L). The other seeps did not contain detectable levels of volatile organic compounds (VOCs). The water issuing from these two contaminated seeps flows into a narrow ravine, where it is visible as a trickle of water flowing through sand and gravel deposits on the floor of the ravine. Approximately 100-ft downstream of the seep area, the contaminated water is no longer visible, having drained back into the soil in the bed of the ravine. Figure 1 shows the location of the 317/319/ENE Area in relation to the ANL-E site and the Waterfall Glen Forest Preserve

  9. Argonne National Laboratory-East site environmental report for calendar year 1989

    International Nuclear Information System (INIS)

    This report discusses the results of the environmental monitoring program at Argonne National Laboratory (ANL) for 1989. To evaluate the effects of ANL operations on the environment, samples of environmental media collected on the site, at the site boundary, and off the ANL site were analyzed and compared. A variety of radionuclides were measured in air, surface water, groundwater, soil, grass, bottom sediment, and milk samples. In addition, chemical constituents in surface water, groundwater, and ANL effluent water were analyzed. External penetrating radiation doses were measured and the potential for radiation exposure to off-site population groups was estimated. The results of the monitoring program are interpreted in terms of the origin of the radioactive and chemical substances (natural, fallout, ANL, and other) and are compared with applicable environmental quality standards. A US Department of Energy (DOE) dose calculation methodology, based on International Commission on Radiological Protection (ICRP) recommendations, is used in this report. This report also discusses progress being made on corrective actions and restoration projects from past activities. 27 refs., 7 figs., 75 tabs

  10. Argonne National Laboratory-east site environmental report for calendar year 1988

    International Nuclear Information System (INIS)

    The results of the environmental monitoring program at Argonne National Laboratory (ANL) for 1988 are presented and discussed. Sample collections were made on the site, at the site boundary, and off the ANL site for comparison purposes. Measurements were made for a variety of radionuclides in air, surface water, ground water, soil, grass, bottom sediment, and milk. Samples were also analyzed for a variety of chemical constituents in surface water, ground water, and ANL effluent water. External penetrating radiation doses were also measured. The potential for radiation exposure to off-site population groups is estimated. The results of the program are interpreted in terms of the origin of the radioactive and chemical substances and are compared with applicable environmental quality standards. A United States Department of Energy dose calculation methodology, is used in this report. 28 refs., 9 figs., 81 tabs

  11. Progress report for the scintillator plate calorimeter subsystem

    International Nuclear Information System (INIS)

    This report covers the work completed in FY90 by ANL staff and those of Westinghouse STC and BICRON Corporation under subcontract to ANL towards the design of a compensating calorimeter based on the use of scintillator plate as the sensitive medium. It is presented as five task sections dealing with respectively mechanical design; simulation studies; optical system design; electronics development; development of rad hard plastic scintillator and wavelength shifter and a summary. The work carried out by the University of Tennessee under a subcontract from ANL is reported separately. Finally, as principal institution with responsibility for the overall management of this subsystem effort, the summary here reports the conclusions resulting from the work of the collaboration and their impact on our proposed direction of effort in FY91. This proposal, for obvious reasons is given separately

  12. Progress report for the scintillator plate calorimeter subsystem

    Energy Technology Data Exchange (ETDEWEB)

    1990-12-31

    This report covers the work completed in FY90 by ANL staff and those of Westinghouse STC and BICRON Corporation under subcontract to ANL towards the design of a compensating calorimeter based on the use of scintillator plate as the sensitive medium. It is presented as five task sections dealing with respectively mechanical design; simulation studies; optical system design; electronics development; development of rad hard plastic scintillator and wavelength shifter and a summary. The work carried out by the University of Tennessee under a subcontract from ANL is reported separately. Finally, as principal institution with responsibility for the overall management of this subsystem effort, the summary here reports the conclusions resulting from the work of the collaboration and their impact on our proposed direction of effort in FY91. This proposal, for obvious reasons is given separately.

  13. Fiscal years 1993 and 1994 decontamination and decommissioning activities photobriefing book for the Argonne National Laboratory-East Site, Technology Development Division, Decontamination and Decommissioning Projects Department

    International Nuclear Information System (INIS)

    This photobriefing book describes the ongoing decontamination and decommissioning projects at the Argonne National Laboratory (ANL)-East Site near Lemont, Illinois. The book is broken down into three sections: introduction, project descriptions, and summary. The introduction elates the history and mission of the Decontamination and Decommissioning (D and D) Projects Department at ANL-East. The second section describes the active ANL-East D and D projects, giving a project history and detailing fiscal year (FY) 1993 and FY 1994 accomplishments and FY 1995 goals. The final section summarizes the goals of the D and D Projects Department and the current program status. The D/D projects include the Experimental Boiling Water Reactor, Chicago Pile-5 Reactor, that cells, and plutonium gloveboxes. 73 figs

  14. Ureteroscopy-Assisted Retrograde Nephrostomy (UARN after Anatrophic Nephrolithotomy

    Directory of Open Access Journals (Sweden)

    Takashi Kawahara

    2012-01-01

    Full Text Available Introduction. Open surgical anatrophic nephrolithotomy (ANL had been the standard treatment for large renal calculi prior to the development of endoscopic devices and endoscopic techniques. A previous report described the efficacy of ureteroscopy-assisted retrograde nephrostomy (UARN and presented a case of renal calculi successfully treated with UARN during percutaneous nephrolithotomy (PCNL in a patient after ANL. Case Presentation. A 61-year-old male with left renal calculi was referred for further treatment. The patient was placed under general and epidural anesthesia, in a Galdakao-modified Valdivia position. A flexible ureteroscope (URS was inserted, and a Lawson retrograde nephrostomy puncture wire was advanced into the flexible URS. The puncture wire then followed the route from the renal pelvis to the exit skin. Calculus fragmentation was undertaken using a pneumatic lithotripter. Conclusions. UARN for PCNL was therefore found to be a safe, effective, and appropriate treatment for a patient presenting with renal calculi after undergoing ANL.

  15. Using electrochemical separation to reduce the volume of high-level nuclear waste

    International Nuclear Information System (INIS)

    Argonne National Laboratory (ANL) has developed an electrochemical separation technique called electrorefining that will treat a variety of metallic spent nuclear fuel and reduce the volume of high-level nuclear waste that requires disposal. As part of that effort, ANL has developed a high throughput electrorefiner (HTER) that has a transport rate approximately three times faster than electrorefiners previously developed at ANL. This higher rate is due to the higher electrode surface area, a shorter transport path, and more efficient mixing, which leads to smaller boundary layers about the electrodes. This higher throughput makes electrorefining an attractive option in treating Department of Energy spent nuclear fuels. Experiments have been done to characterize the HTER, and a simulant metallic fuel has been successfully treated. The HTER design and experimental results is discussed

  16. Review of the treat upgrade reactor scram system reliability analysis

    International Nuclear Information System (INIS)

    In order to resolve some key LMFBR safety issues, ANL personnel are modifying the TREAT reactor to handle much larger experiments. As a result of these modifications, the upgraded Treat reactor will not always operate in a self-limited mode. During certain experiments in the upgraded TREAT reactor, it is possible that the fuel could be damaged by overheating if, once the computer systems fail, the reactor scram system (RSS) fails on demand. To help ensure that the upgraded TREAT reactor is shut down when required, ANL personnel have designed a triply redundant RSS for the facility. The RSS is designed to meet three reliability goals: (1) a loss of capability failure probability of 10-9/demand (independent failures only); (2) an inadvertent shutdown probability of 10-3/experiment; and (3) protection agaist any known potential common cause failures. According to ANL's reliability analysis of the RSS, this system substantially meets these goals

  17. Project plan for the decontamination and decommissioning of the Argonne National Laboratory Experimental Boiling Water Reactor

    International Nuclear Information System (INIS)

    In 1956, the Experimental Boiling Water Reactor (EBWR) Facility was first operated at Argonne National Laboratory (ANL) as a test reactor to demonstrate the feasibility of operating an integrated power plant using a direct cycle boiling water reactor as a heat source. In 1967, ANL permanently shut down the EBWR and placed it in dry lay-up. This project plan presents the schedule and organization for the decontamination and decommissioning of the EBWR Facility which will allow it to be reused by other ANL scientific research programs. The project total estimated cost is $14.3M and is projected to generate 22,000 cubic feet of low-level radioactive waste which will be disposed of at an approved DOE burial ground. 18 figs., 3 tabs

  18. Decontamination and decommissioning of the Experimental Boiling Water Reactor at Argonne National Laboratory

    International Nuclear Information System (INIS)

    The Experimental Boiling Water Reactor (EBWR), located on the Argonne National Laboratory-East (ANL-E) site, started operations in 1957. The initial rating was 20 MW(t). The rating was eventually increased to 70 MW(t) in 1959 and 100 MW(t) in 1962. The reactor was shut down in 1967 and all of the fuel was removed from the facility. The facility was placed in dry lay-up until 1986. ANL-E personnel started the decontamination and decommissioning (D ampersand D) effort in 1986. Supporting equipment such as the external steam system and some of the upper reactor components, the core riser and the top fuel shroud, were removed at that time. Characterization of the facility was also undertaken. The contract to complete the EBWR D ampersand D Project was issued in December 1993. The initial schedule called for the final effort to be divided into five phases that were to be completed over a four year period. However, this schedule was subsequently consolidated, at the request of ANL-E, to a thirteen month period, with the on-site work to be completed by the end of 1994. The EBWR D ampersand D Project is approximately 88% complete. A small quantity of reactor internals remains to be volume reduced along with the removal of the SFSP water treatment system. Upon completion of this work the facility will be decontaminated and a final survey completed. The planned completion of on-site work is scheduled for July 1995

  19. Indonesian Achievement [Country report: Indonesia

    International Nuclear Information System (INIS)

    Since 1996 Indonesia has produced 99Mo from HEU fission product mainly for domestic consumption. Due to limited and restricted raw material of HEU, Indonesia has a conversion program from HEU to LEU for producing 99Mo from LEU foil target. The substitution of low enriched uranium (LEU) metal foils for the HEU UO2 used in current target designs will be applied for production of 99Mo commercially. Batan has had a joint research project with ANL to develop LEU-metal-foil target fabrication since 1992. Many achievements have resulted from the experiments. Design target has undergone several changes in design, materials and wrapping of LEU foil targets. ANL has developed several of LEU target design and fabrication, and has demonstrated Radio Metallurgy Installation hot cell in Batan for disassembly process to take out LEU foil from the target after being irradiated in the RSG-GAS BATAN reactor. Installed power of RSG-GAS is 30 MW but operational power is 15 MW. LEU foil targets were irradiated in CIP of RSG-GAS with thermal neutron flux 2.4x1014n cm-2s-1. Chemical processing was conducted in Isotope Production Centre hot cell for producing 99Mo which will be used to produce 99mTc generator. Batan has a license to use the process from US DOE. The experiment was terminated temporarily in 2001 due to September eleven accident. In 2004, cooperation between the ANL and BATAN was continued. In November 2005, ANL provided training on LEU target assembly to BATAN by simulation of Cu-foil as LEU foil. Then BATAN personnel demonstrated reassembly of 2 ANL LEU targets to replace Zn and Al foil barrier with Ni foil barrier in January 2006. In 2006, Indonesia began to manufacture foil targets using depleted uranium following the procedures established by ANL

  20. Historic preservation requirements and the evaluation of cold war era nuclear facilities at Argonne National Laboratory-East

    International Nuclear Information System (INIS)

    Project design for the decontamination and decommissioning (D and D) of federal facilities must address the requirements of the National Environmental Policy Act which includes compliance with the National Historic Preservation Act (NHPA). Section 106 of the NHPA requires that Federal agencies consider any effect their activities may have on historic properties. While a cultural property is not usually considered historic until it has reached an age of 50 years or older, special consideration is given to younger properties if they are of exceptional importance in demonstrating unique development in American history, architecture, archaeology, engineering, or culture. As part of the U.S. Department of Energy's (DOE's) D and D program at Argonne National Laboratory-East (ANL-E), site properties are evaluated within the context of the Cold War Era and within themes associated with nuclear technology. Under this program, ANL-E staff have conducted archival research on three nuclear reactor facilities, one accelerator, and one laboratory building. DOE and ANL-E have been working closely with the Illinois Historic Preservation Agency (IHPA) to determine the eligibility of these properties for listing on the National Register of Historic Places. In 1998, in consultation with the IHPA, the DOE determined that the reactor facilities were eligible. Memoranda of Agreement were signed between the DOE and the IHPA stipulating mitigation requirements for the recordation of two of these properties. The laboratory building was recently determined eligible and will likely undergo similar documentation procedures. The accelerator was determined not eligible. Similar studies and determinations will be required for all future D and D projects

  1. Utility industry evaluation of the metal fuel facility and metal fuel performance for liquid metal reactors

    International Nuclear Information System (INIS)

    A team of utility industry representatives evaluated the liquid metal reactor metal fuel process and facility conceptual design being developed by Argonne National Laboratory (ANL) under Department of Energy sponsorship. The utility team concluded that a highly competent ANL team was making impressive progress in developing high performance advanced metal fuel and an economic processing and fabrication technology. The utility team concluded that the potential benefits of advanced metal fuel justified the development program, but that, at this early stage, there are considerable uncertainties in predicting the net overall economic benefit of metal fuel. Specific comments and recommendations are provided as a contribution towards enhancing the development program. 6 refs

  2. TOURISM POTENTIALITY OF OLD HALFETİ (ŞANLIURFA) REPLACED BY BİRECİK DAM

    OpenAIRE

    Zeki Boyraz; M. Salih Bostancı

    2015-01-01

    In this study, tourism potentiality of old Halfeti will be tired to be depicted. Old Halfeti, the subject of the study, stands in 130 km west of Şanlıurfa city center, in the east of Fırat River and on 388 m height. While old Halfeti was a town relate to city of Şanlıurfa, after the year 2000, 2/5 (180 hectar) of old Halfeti was covered with the water of dam lake as a result of completion of Birecik Dam that is a part of GAP. Whole of the region except two districts have been moved to the ...

  3. Supplemental site inspection for Air Force Plant 59, Johnson City, New York, Volume 1: Investigation report

    Energy Technology Data Exchange (ETDEWEB)

    Nashold, B.; Rosenblatt, D.; Hau, J. [and others

    1995-08-01

    This summary describes a Supplemental Site Inspection (SSI) conducted by Argonne National Laboratory (ANL) at Air Force Plant 59 (AFP 59) in Johnson City, New York. All required data pertaining to this project were entered by ANL into the Air Force-wide Installation Restoration Program Information System (IRPIMS) computer format and submitted to an appropriate authority. The work was sponsored by the United States Air Force as part of its Installation Restoration Program (IRP). Previous studies had revealed the presence of contaminants at the site and identified several potential contaminant sources. Argonne`s study was conducted to answer questions raised by earlier investigations.

  4. Implementing partnerships in nonreactor facility safety analyses

    International Nuclear Information System (INIS)

    Faculty and students from LSU have been participating in nuclear safety analyses and radiation protection projects at ANL-W at INEL since 1973. A mutually beneficial relationship has evolved that has resulted in generation of safety-related studies acceptable to Argonne and DOE, NRC, and state regulatory groups. Most of the safety projects have involved the Hot Fuel Examination Facility or the Fuel Conditioning Facility; both are hot cells that receive spent fuel from EBR-II. A table shows some of the major projects at ANL-W that involved LSU students and faculty

  5. Æstetisk smag – med mennesker som pynt?

    DEFF Research Database (Denmark)

    Eichberg, Henning

    2015-01-01

    Anmeldelse af Claus Bøje & Søren Riiskjær (red.): Tag på fælleden – idrættens huse. 20 år med Lokale og Anlægs-fonden. København: LOA.......Anmeldelse af Claus Bøje & Søren Riiskjær (red.): Tag på fælleden – idrættens huse. 20 år med Lokale og Anlægs-fonden. København: LOA....

  6. Evaluating the environmental impacts of the energy system: The ENPEP [ENergy and Power Evaluation Program] approach

    International Nuclear Information System (INIS)

    Argonne National Laboratory (ANL) has developed the ENergy and Power Evaluation Program (ENPEP), a PC-based energy planning package intended for energy/environmental analysis in developing countries. The IMPACTS module of ENPEP examines environmental implications of overall energy and electricity supply strategies that can be developed with other ENPEP modules, including ELECTRIC, the International Atomic Energy Agency's Wien Automatic System Planning Package (WASP-III). The paper presents the status and characteristics of a new IMPACTS module that is now under development at ANL. 3 figs

  7. Safety aspects of the US advanced LMR [liquid metal reactor] design

    International Nuclear Information System (INIS)

    The cornerstones of the United States Advanced Liquid Metal Cooled Reactor (ALMR) program sponsored by the Department of Energy are: the plant design program at General Electric based on the PRISM (Power Reactor Innovative Small Module) concept, and the Integral Fast Reactor program (IFR) at Argonne National Laboratory (ANL). The goal of the US program is to produce a standard, commercial ALMR, including the associated fuel cycle. This paper discusses the US regulatory framework for design of an ALMR, safety aspects of the IFR program at ANL, the IFR fuel cycle and actinide recycle, and the ALMR plant design program at GE. 6 refs., 5 figs

  8. AFCI Storage & Disposal FY-06 Progress Report

    Energy Technology Data Exchange (ETDEWEB)

    Halsey, W G; Wigeland, R; Dixon, B

    2006-09-27

    AFCI Storage and Disposal participants at LLNL, ANL and INL provide assessment of how AFCI technology can optimize the future evolution of the fuel cycle, including optimization of waste management. Evaluation of material storage and repository disposal technical issues provides feedback on criteria and metrics for AFCI, and evaluation of AFCI waste streams provides technical alternatives for future repository optimization. LLNL coordinates this effort that includes repository analysis at ANL and incorporation of repository impacts into AFCI criteria at INL. Cooperative evaluation with YMP staff is pursued to provide a mutually agreed technical base. Cooperation with select international programs is supported.

  9. Review process and quality assurance in the EBR-II probabilistic risk assessment

    International Nuclear Information System (INIS)

    A Probabilistic Risk Assessment (PRA) of the Experimental Breeder Reactor II (EBR-II), a Department of Energy (DOE) Category A reactor, has recently been completed at Argonne National Laboratory (ANL). Within the scope of the ANL QA Programs, a QA Plan specifically for the EBR-II PRA was developed. The QA Plan covered all aspects of the PRA development, with emphasis on the procedures for document and software control, and the internal and external review process. The effort spent in the quality assurance tasks for the EBR-II PRA has reciprocated by providing acceptance of the work and confidence in the quality of the results

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

    International Nuclear Information System (INIS)

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

  11. Fire Burning Characteristics, Attacking Techniques and Safety Precautions in Pinus pumila Scrubs

    Institute of Scientific and Technical Information of China (English)

    2010-01-01

    In China, Pinus pumila is mainly distributed in Daxing’anling, while those growing in the eastern Daxing’anling are primarily covered under the jurisdiction of Huzhong Forest Bureau. P. pumila is an evergreen shrub, 3-6 m high, and always grows vigorously. Its trunks creep along the ground, usually 10 m long or more. It is easily flammable because of the large amounts of resins and volatile oils in its body. Attacking forest fires is a dangerous work, especially in P. pumila scrubs. The fires in P. pumila s...

  12. ŞANLIURFA İLİNDE BOĞULMA VAKALARININ İNCELENMESİ (2001-2008)

    OpenAIRE

    BENEK, Sedat; ÖZCANLI, MEHMET

    2015-01-01

    The rate of death cases caused by drowning within death occurring varies to settlements and population density. According to data of Forensic Medicine Directorate in Şanlıurfa, between 2001 and 2008 years, majority (67.7%) of these are in the irrigation channels, 189 drowning cases occurred. This study aims to discuss the measures to be taken, the causes and the distribution of drowning cases at time and place in the province of Şanlıurfa. The data sources are the death archives and autopsy e...

  13. Methods for removing transuranic elements from waste solutions

    International Nuclear Information System (INIS)

    This report outlines a treatment scheme for separating and concentrating the transuranic (TRU) elements present in aqueous waste solutions stored at Argonne National Laboratory (ANL). The treatment method selected is carrier precipitation. Potential carriers will be evaluated in future laboratory work, beginning with ferric hydroxide and magnetite. The process will result in a supernatant with alpha activity low enough that it can be treated in the existing evaporator/concentrator at ANL. The separated TRU waste will be packaged for shipment to the Waste Isolation Pilot Plant

  14. Verification Survey of the Building 315 Zero Power Reactor-6 Facility, Argonne National Laboratory-East, Argonne, Illinois

    International Nuclear Information System (INIS)

    Oak Ridge Institute for Science and Education (ORISE) conducted independent verification radiological survey activities at Argonne National Laboratory's Building 315, Zero Power Reactor-6 facility in Argonne, Illinois. Independent verification survey activities included document and data reviews, alpha plus beta and gamma surface scans, alpha and beta surface activity measurements, and instrumentation comparisons. An interim letter report and a draft report, documenting the verification survey findings, were submitted to the DOE on November 8, 2006 and February 22, 2007, respectively (ORISE 2006b and 2007). Argonne National Laboratory-East (ANL-E) is owned by the U.S. Department of Energy (DOE) and is operated under a contract with the University of Chicago. Fundamental and applied research in the physical, biomedical, and environmental sciences are conducted at ANL-E and the laboratory serves as a major center of energy research and development. Building 315, which was completed in 1962, contained two cells, Cells 5 and 4, for holding Zero Power Reactor (ZPR)-6 and ZPR-9, respectively. These reactors were built to increase the knowledge and understanding of fast reactor technology. ZPR-6 was also referred to as the Fast Critical Facility and focused on fast reactor studies for civilian power production. ZPR-9 was used for nuclear rocket and fast reactor studies. In 1967, the reactors were converted for plutonium use. The reactors operated from the mid-1960's until 1982 when they were both shut down. Low levels of radioactivity were expected to be present due to the operating power levels of the ZPR's being restricted to well below 1,000 watts. To evaluate the presence of radiological contamination, DOE characterized the ZPRs in 2001. Currently, the Melt Attack and Coolability Experiments (MACE) and Melt Coolability and Concrete Interaction (MCCI) Experiments are being conducted in Cell 4 where the ZPR-9 is located (ANL 2002 and 2006). ANL has performed final

  15. Computed results on the IAEA benchmark problems at JAERI

    International Nuclear Information System (INIS)

    The outline of the computer code system of JAERI for analysing research reactors is presented and the results of check calculations to validate the code system are evaluated by the experimental data. Using this computer code system, some of the IAEA benchmark problems are solved and the results are compared with those of ANL. (author)

  16. Engineering and Physics Optimization of Breed and Burn Fast Reactor Systems

    Energy Technology Data Exchange (ETDEWEB)

    Michael J. Driscoll; Pavel Hejzlar; Peter Yarsky; Dan Wachs; Kevan Weaver; Ken Czerwinski; Michael Pope; Cliff Davis; Theron Marshall; James Parry

    2005-12-09

    This project is organized under four major tasks (each of which has two or more subtasks) with contributions among the three collaborating organizations (MIT, INEEL and ANL-West): Task A: Core Physics and Fuel Cycle; Task B: Core Thermal Hydraulics; Task C: Plant Design Task; and D: Fuel Design.

  17. Physiologic correlates to background noise acceptance

    Science.gov (United States)

    Tampas, Joanna; Harkrider, Ashley; Nabelek, Anna

    2001-05-01

    Acceptance of background noise can be evaluated by having listeners indicate the highest background noise level (BNL) they are willing to accept while following the words of a story presented at their most comfortable listening level (MCL). The difference between the selected MCL and BNL is termed the acceptable noise level (ANL). One of the consistent findings in previous studies of ANL is large intersubject variability in acceptance of background noise. This variability is not related to age, gender, hearing sensitivity, personality, type of background noise, or speech perception in noise performance. The purpose of the current experiment was to determine if individual differences in physiological activity measured from the peripheral and central auditory systems of young female adults with normal hearing can account for the variability observed in ANL. Correlations between ANL and various physiological responses, including spontaneous, click-evoked, and distortion-product otoacoustic emissions, auditory brainstem and middle latency evoked potentials, and electroencephalography will be presented. Results may increase understanding of the regions of the auditory system that contribute to individual noise acceptance.

  18. Regnvandsbassiner virker efter hensigten

    DEFF Research Database (Denmark)

    Bentzen, Thomas Ruby

    2009-01-01

    Forskere fra Aalborg Universitet har efter en længere periode undersøgt effekten af de regnvandsbassiner, Vejdirektoratet anlægger langs motorvejene, og nogle af undersøgelserne har fundet sted ved Årslev. Undersøgelserne viser, at størstedelen af de forurenende stoffer fra vejen bliver i bassine...

  19. Heavy ion fusion program. Semi-annual progress report, October 1, 1979-March 30, 1980

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    HIF activity at ANL during FY 1980 has been primarily concentrated on conceptual design work, and on initial tests of the independently-phased rf acceleration cavities. Calculations for near-term foil-heating experiments were carried out, and a specific cost-effective synchrotron (Beam Development Facility) plan was developed. Program logics were further refined, and some conceptual reactor issues were addressed.

  20. 78 FR 40499 - Public Land Order No. 7818; Withdrawal of Public Lands for the Protection and Preservation of...

    Science.gov (United States)

    2013-07-05

    ... order withdraws 303,900 acres of public lands from location and entry under the United States mining... in Six Southwestern States Web site ( http://solareis.anl.gov ) and are also available from the... United States mining laws (30 U.S.C. Ch. 2), but not from the public land, mineral leasing,...

  1. Guide til sand undervisning

    DEFF Research Database (Denmark)

    Pedersen, Morten Lauge

    2011-01-01

    I en kommentar skriver Morten Lauge Pedersen, der er lektor ved Institut for Byggeri og Anlæg, Aalborg Universitet, at det vigtigste for en lektors undervisning er det akademiske kvarter, som, godt og vel, er en grundlovsfæstet ret for universitetsansatte. Det er samtidig vigtigt, at de studerend...

  2. Cost Quality Management Assessment for the Chicago Operations Office. Final report

    International Nuclear Information System (INIS)

    The Office of Engineering and Cost Evaluation (EM-24, now the Office of Engineering and Cost Management) conducted a Cost Quality Management Assessment (CQMA) at the Department of Energy (DOE) Chicago Operations Office (DOE-CH) on December 9--20, 1991. The CQMA team, composed of specialist from the Department of Energy, other Federal agencies, and the private sector used Performance objectives and Criteria (POCs) to assess the state of cost-management activities at DOE-CH. The Round II CQMA was conducted June 6--17, 1994, to examine DOE-CH's progress against its Action Plan and to review DOE-CH's cost and cost-related management practices against the POCs in the CQMA Site Handbook (Rev. 2). The interviews and document reviews conducted by CQMA team members show that DOE-CH has made commendable progress when practice is measured against the POCs. Of the 48 POCs discussed in this document, DOE-CH met 13 (28 %), partially met 32 (66 %), and did not meet only 3 (6 %). Noteworthy accomplishments at DOE-CH and the Argonne National Laboratory-East (ANL-E) include: (1) Preparation of an ANL-E CQMA Self-Assessment; (2) Development of the Argonne National Laboratory Project Management Manual; (3) Development of a corporate culture that recognizes the realities of cost and schedule constraints

  3. Reduction of patient dose delivered by CHR diagnostic x-ray examinations

    International Nuclear Information System (INIS)

    Three changes in technique have been made which reduce the x-ray dose delivered by diagnostic examinations of patients of the Center for Human Radiobiology (CHR): Kodak Lanex Regular screens and Kodak Ortho G film have been substituted for DuPont Cronex Parspeed screens and DuPont Cronex 4 film for five projections in the MIT examinations; 3 mm Al added filtration is now used in place of 1 mm Al added filtration in the ANL examination; improvements in collimation for the ANL examination have been made. Use of the new screen-film combination at MIT has reduced the mean dose to the active marrow of the female RANDO phantom from 606 +- 69 mrad to 235 +- 16 mrad; it has reduced the ovary dose from 606 +- 40 mrad to 291 +- 19 mrad and has left the breast dose unchanged at 333 +- 103 mrad. The change from 1 mm Al to 3 mm Al added filtration at ANL, without changes in collimation, would reduce the mean marrow dose in the phantom from 232 +- 14 mrad to 175 +- 26 mrad, reduce the ovary dose from 243 +- 25 mrad to 162 +- 38 mrad and reduce the breast dose from 388 +- 35 mrad to 226 +- 9 mrad. The changes in collimation at ANL should reduce these doses even further but the quantitative effect has not been ascertained

  4. Characterization report for Building 301 Hot Cell Facility

    International Nuclear Information System (INIS)

    During the period from October, 1997, through March, 1998, ANL-E Health Physics conducted a pre-D and D characterization of Building 301, referred to as the Hot Cell Facility. While primary emphasis was placed on radiological evaluation, the presence of non-nuclear hazardous and toxic material was also included in the scope of the characterization. This is one of the early buildings on the ANL-E site, and was heavily used in the 1950's and 1960's for various nuclear reaction and reactor design studies. Some degree of cleanup and contamination fixation was done in the 1970's, so that the building could be used with a minimum of risk of personnel contamination. Work records are largely nonexistent for the early history of the building, so that any assumptions about extent and type of contamination had to be kept very open in the survey planning process. The primary contaminant was found to be painted-over Cs-137 embedded in the concrete floors, although a variety of other nuclides consistent with the work said to have been performed were found in smaller quantities. Due to leaks and drips through the floor, a relatively modest amount of soil contamination was found in the service trench under the building, not penetrating deeply. Two contaminated, disconnected drain lines leaving the building could not be traced by site records, and remain a problem for remediation. The D and D Characterization Plan was fulfilled

  5. Fiscal year 1996 decontamination and decommissioning activities photobriefing book for the Argonne National Laboratory-East Site, Technology Development Division, Waste Management Program, Decontamination and Decommissioning Projects Department

    International Nuclear Information System (INIS)

    The Photobriefing Book describes the Decontamination and Decommissioning (D and D) Program at the Argonne National Laboratory-East Site (ANL-E) near Lemont, Illinois. This book summarizes current D and D projects, reviews fiscal year (FY) 1996 accomplishments, and outlines FY 1997 goals. A section on D and D Technology Development provides insight on new technologies for D and D developed or demonstrated at ANL-E. Past projects are recapped and upcoming projects are described as Argonne works to accomplish its commitment to, ''Close the Circle on the Splitting of the Atom.'' Finally, a comprehensive review of the status and goals of the D and D Program is provided to give a snap-shot view of the program and the direction it's taking as it moves into FY 1997. The D and D projects completed to date include: Plutonium Fuel Fabrication Facility; East Area Surplus Facilities; Experimental Boiling Water Reactor; M-Wing Hot Cell Facilities; Plutonium Gloveboxes; and Fast Neutron Generator

  6. Bericht am Feuer. Gespräche, E-Mails und Telefonate zum Werk von Christoph Ransmayr von Insa Wilke (Hg.

    Directory of Open Access Journals (Sweden)

    Johanna Lenhart

    2014-09-01

    Full Text Available Christoph Ransmayr baut seine Bücher immer ausgehend von Gesprächen auf. Anlässlich seines 60. Geburtstags hat Insa Wilke einen Materialienband herausgegeben, den Johanna Lenhart für die MEDIENIMPULSE rezensiert hat …

  7. Vejstrækningers geometri

    DEFF Research Database (Denmark)

    Bolet, Lars; Kjems, Erik

    Undervisningsnoten er skrevet til kurserne i Vej- og Trafikteknik henholdsvis i Geometrisk Vejprojektering på Aalborg Universitets ingeniøruddannelser i byggeri og anlæg. Notatet behandler fastlæggelsen af en vejstræknings linjeføring og længdeprofil, herunder vejprojektets rammevilkår, tracering...

  8. 76 FR 51281 - Energy Conservation Program for Consumer Products and Certain Commercial and Industrial Equipment...

    Science.gov (United States)

    2011-08-18

    ... levels. DOE impact analyses include a: life-cycle cost analysis, manufacturer impact analysis, national.... However, DOE notes that DOE's analysis does identify such benefits separately in its life-cycle cost and...'s ANL has, in the past, compared different life-cycle assessment methods and found that the...

  9. Test plan for non-radioactive testing of vertical calciner for development of direct denitration conversion of Pu-bearing liquors to stable, storage solids

    International Nuclear Information System (INIS)

    Plutonium-bearing liquors, including ANL scrap liquors, will be used for development and demonstration of a vertical calciner direct denitration process for conversion of those liquors to stable, storable PuO2-rich solids. This test plan is to test with non-radioactive stand-in materials to demonstrate adequate performance of the vertical calciner and ancillary equipment

  10. Preparing a self-evaluation report for training program accreditation

    International Nuclear Information System (INIS)

    This document describes the process used by Argonne National Laboratory (ANL) Training/Procedures personnel at Experimental Breeder Reactor 2 (EBR-II) to develop a Self-Evaluation Report for the Nuclear Power Plant Operator training program. The document also describes problems encountered and lessons learned during development of the Self-Evaluation Report. 5 refs., 2 tabs

  11. FELIX construction status and experimental program

    International Nuclear Information System (INIS)

    FELIX (Fusion Electromagnetic Induction Experiment) is an experimental test facility being constructed at Argonne National Laboratory (ANL) for the study of electromagnetic effects in the first wall/blanket/shield (FWBS) systems of fusion reactors. The facility design, construction status, experimental program, instrumentation, and associated computer-code comparisons are described

  12. Measurements of reactor-relevant electromagnetic effects with the FELIX facility

    International Nuclear Information System (INIS)

    Recent experiments with the FELIX (Fusion Electromagnetic Induction eXperiment) facility at Argonne National Laboratory (ANL) suggest that the expected electromagnetic forces and torques in a tokamak first wall, blanket, and shield (FWBS) system can be modelled by a single eddy current mode, with a simple characterization

  13. Design/build/mockup of the Waste Isolation Pilot Plant gas generation experiment glovebox

    International Nuclear Information System (INIS)

    A glovebox was designed, fabricated, and mocked-up for the WIPP Gas Generation Experiments (GGE) being conducted at ANL-W. GGE will determine the gas generation rates from materials in contact handled transuranic waste at likely long term repository temperature and pressure conditions. Since the customer's schedule did not permit time for performing R ampersand D of the support systems, designing the glovebox, and fabricating the glovebox in a serial fashion, a parallel approach was undertaken. As R ampersand D of the sampling system and other support systems was initiated, a specification was written concurrently for contracting a manufacturer to design and build the glovebox and support equipment. The contractor understood that the R ampersand D being performed at ANL-W would add additional functional requirements to the glovebox design. Initially, the contractor had sufficient information to design the glovebox shell. Once the shell design was approved, ANL-W built a full scale mockup of the shell out of plywood and metal framing; support systems were mocked up and resultant information was forwarded to the glovebox contractor to incorporate into the design. This approach resulted in a glovebox being delivered to ANL-W on schedule and within budget

  14. Måling af tryktab i taghætte

    DEFF Research Database (Denmark)

    Jensen, Rasmus Lund; Jønsson, Kim Trangbæk

    På laboratoriet for Indeklima og Energi, Institut for Byggeri og Anlæg, Aalborg Universitet udførtes februar 2015 målinger af tryktab over en taghætte fra Designit Fiskerivej 2, 8000 Aarhus C, Komproment Jellingvej 11, 9230 Svenstrup og Ecovent Samsøvej 18-22, 8382 Hinnerup. Målingerne omfattede...

  15. RH-TRU Waste Characterization by Acceptable Knowledge at the Idaho National Engineering and Environmental Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Schulz, C.; Givens, C.; Bhatt, R.; Whitworth, J.

    2003-02-24

    Idaho National Engineering and Environmental Laboratory (INEEL) is conducting an effort to characterize approximately 620 drums of remote-handled (RH-) transuranic (TRU) waste currently in its inventory that were generated at the Argonne National Laboratory-East (ANL-E) Alpha Gamma Hot Cell Facility (AGHCF) between 1971 and 1995. The waste was generated at the AGHCF during the destructive examination of irradiated and unirradiated fuel pins, targets, and other materials from reactor programs at ANL-West (ANL-W) and other Department of Energy (DOE) reactors. In support of this effort, Shaw Environmental and Infrastructure (formerly IT Corporation) developed an acceptable knowledge (AK) collection and management program based on existing contact-handled (CH)-TRU waste program requirements and proposed RH-TRU waste program requirements in effect in July 2001. Consistent with Attachments B-B6 of the Waste Isolation Pilot Plant (WIPP) Hazardous Waste Facility Permit (HWFP) and th e proposed Class 3 permit modification (Attachment R [RH-WAP] of this permit), the draft AK Summary Report prepared under the AK procedure describes the waste generating process and includes determinations in the following areas based on AK: physical form (currently identified at the Waste Matrix Code level); waste stream delineation; applicability of hazardous waste numbers for hazardous waste constituents; and prohibited items. In addition, the procedure requires and the draft summary report contains information supporting determinations in the areas of defense relationship and radiological characterization.

  16. Supervisand og supervisor

    DEFF Research Database (Denmark)

    Jacobsen, Claus Haugaard

    2007-01-01

    Kapitlet redegør for aspekter ved det komplekse forhold mellem supervisand og supervisor, og der anlægges en række forskellige perspektiver. Først beskrives forholdet fra supervisandens perspektiv. At indtræde i rollen som supervisand er, foruden at være lærerigt og fagligt udviklende, ofte også ...

  17. Management of wildlife causing damage at Argonne National Laboratory-East, DuPage County, Illinois

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    The DOE, after an independent review, has adopted an Environmental Assessment (EA) prepared by the US Department of Agriculture (USDA) which evaluates use of an Integrated Wildlife Damage Management approach at Argonne National Laboratory-East (ANL-E) in DuPage County, Illinois (April 1995). In 1994, the USDA issued a programmatic Environmental Impact Statement (EIS) that covers nationwide animal damage control activities. The EA for Management of Wildlife Causing Damage at ANL-E tiers off this programmatic EIS. The USDA wrote the EA as a result of DOE`s request to USDA to prepare and implement a comprehensive Wildlife Management Damage Plan; the USDA has authority for animal damage control under the Animal Damage Control Act of 1931, as amended, and the Rural Development, Agriculture and Related Agencies Appropriations Act of 1988. DOE has determined, based on the analysis in the EA, that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (NEPA). Therefore, the preparation of an EIS is not required. This report contains the Environmental Assessment, as well as the Finding of No Significant Impact (FONSI).

  18. Preparing for radiological assessments in the event of a tornado strike at Argonne National Lab.-East

    International Nuclear Information System (INIS)

    Argonne National Laboratory-East (ANL) is a Department of Energy (DOE)-owned, contractor-operated national laboratory located 22 miles southwest of downtown Chicago on a wooded, 1700-acre site. The principal nuclear facilities at ANL include a large fast neutron source (Intense Pulse Neutron Source) in which high-energy protons strike a uranium target to produce neutrons for research studies; 60Co irradiation sources; chemical and metallurgical plutonium laboratories, some of which are currently being decommissioned; several large hot cell facilities designed for work with multicurie quantities of actinide elements and irradiated reactor fuel materials; a few small research reactors currently in different phases of being decommissioned; and a variety of research laboratories handling many different sources in various chemical and physical forms. The hazards analysis for the ANL site shows that tornado strikes are a serious threat. The site has been struck twice in the past 20 yr, receiving only minor building damage and no release of radioactivity to the environment. Although radioactive materials in general are handled in areas that provide good tornado protection, ANL is prepared to address the problems that would occur should there be a loss of control of radioactive materials due to severe building damage

  19. Advanced cell technology for high performance Li-A1/FeS{sub 2} secondary batteries.

    Energy Technology Data Exchange (ETDEWEB)

    Henriksen, G. L.

    1998-07-10

    In early 1993. Argonne National Laboratory (ANL) initiated a major R and D effort to develop bipolar Li-Al/LiCl-LiBr-KBr/FeS{sub 2} batteries for electric vehicles, targeting the USABC Long-Term Goals. Significant advancements were achieved in the areas of (i) chemical purity, (ii) electrode and electrolyte additives, and (iii) peripheral seals. It was determined that key chemical constituents contained undesirable impurities. ANL developed new chemical processes for preparing Li{sub 2}S, FeS, and CoS{sub 2} that were >98.5% pure. We evaluated a large variety of electrode and electrolyte additives for reducing cell area specific impedance (ASI). Candidate positive electrode additives offered increased electronic conductivity, enhanced reaction kinetics, and/or improved porous electrode morphology. CoS{sub 2}, CuFeS{sub 2}, MgO, and graphite (fibers) were identified as the most beneficial impedance-reducing positive electrode additives. Although electronically conductive carbon and graphite additives produced measurable ASI reductions in the negative electrode, they degraded its structural integrity and were deemed impractical. Lil and LiF were identified as beneficial electrolyte additives, that enhance positive electrode kinetics. ANL refined its baseline metal/ceramic peripheral seal and increased its strength by a factor of three (achieving a safety factor >10). In parallel, ANL developed a high-strength advanced metal/ceramic seal that offers appreciable cost reductions.

  20. Las hojas de «Glosas»: un trayecto y una trayectoria respetables

    Directory of Open Access Journals (Sweden)

    Joaquín Segura

    2010-12-01

    Full Text Available En el presente artículo se relata el nacimiento de la Academia Norteamericana de la Lengua Española (ANLE en 1973 y la creación veintiún años más tarde de la Comisión de Traducciones de la ANLE y de su revista trimestral «Glosas», destinada a dar orientaciones sobre la traducción de neologismos, frases y giros del inglés al español y a informar de novedades bibliográficas y científico-técnicas de interés para la traducción inglés-español. En el siguiente texto encontrará el lector algunos de los principales temas tratados por la revista. ------------------------------------------------------ «Glosas»: a respectable journey and journeyman. This article describes the birth of the North American Academy of the Spanish Language (ANLE in 1973 as well as the establishment 21 years later of the ANLE's Translations Commission and the launching of its quarterly publication «Glosas», designed to provide guidance on the translation of new words, phrases and expressions from English into Spanish and to report on bibliographic and on scientific and technical news relevant to English-Spanish translation practice.

  1. Sintering and Particle Dynamics in Supported Metal Catalysts

    DEFF Research Database (Denmark)

    Hansen, Thomas Willum

    2006-01-01

    viser en god overensstemmelse med en kinetisk beskrivelse af sintringsraten under industrielle betingelser, så observationerne i elektronmikroskopet må formodes at være repræsentative for sintring i et industrielt anlæg. Resultaterne indikerer yderligere, at keramikkens overfladestruktur har en kraftig...

  2. Reference class forecasting

    DEFF Research Database (Denmark)

    Flyvbjerg, Bent

    Underbudgettering og budgetoverskridelser forekommer i et flertal af større bygge- og anlægsprojekter. Problemet skyldes optimisme og/eller strategisk misinformation i budgetteringsprocessen. Reference class forecasting (RCF) er en prognosemetode, som er udviklet for at reducere eller eliminere...

  3. Prof. Dr. Bojan Čop

    OpenAIRE

    Janez Orešnik

    2015-01-01

    Dieser Band ist dem Indogermanisten Bojan Čop anläßlich seines 70. Geburts­ tags am 23. Mai 1993 gewidmet. Mit der nachstehenden, viel zu knappen Würdigung unseres bedeutendsten noch forschenden Vertreters der historischen Sprachwissen­ schaft verneigen wir uns - Fachkollegen wie Interessenten - vor einer großen Lei­ stung.

  4. Prof. Dr. Bojan Čop

    Directory of Open Access Journals (Sweden)

    Janez Orešnik

    2015-09-01

    Full Text Available Dieser Band ist dem Indogermanisten Bojan Čop anläßlich seines 70. Geburts­ tags am 23. Mai 1993 gewidmet. Mit der nachstehenden, viel zu knappen Würdigung unseres bedeutendsten noch forschenden Vertreters der historischen Sprachwissen­ schaft verneigen wir uns - Fachkollegen wie Interessenten - vor einer großen Lei­ stung.

  5. Irradiation effects on reactor structural materials. Semiannual progress report, March 1975--July 1975

    International Nuclear Information System (INIS)

    Mechanical properties and irradiation effects are reported by Aerojet, ANL, AI, GE, HEDL, NRL, ORNL, PNL, and Univ. of Cincinnati for: Type 304, 304L, and 316 stainless steels; Inconel 718; nickel; Ni alloys; V alloys; Mo; Nb; and Nb--1 Zr

  6. Evaluation and analysis of non-intrusive techniques for detecting illicit substances

    Energy Technology Data Exchange (ETDEWEB)

    Micklich, B.J.; Roche, C.T.; Fink, C.L.; Yule, T.J.; Demirgian, J.C. [Argonne National Lab., IL (United States); Kunz, T.D.; Ulvick, S.J.; Cui, J. [Houston Advanced Research Center, The Woodlands, TX (United States)

    1995-12-31

    Argonne National Laboratory (ANL) and the Houston Advanced Research Center (HARC) have been tasked by the Counterdrug Technology Assessment Center of the Office of National Drug Control Policy to conduct evaluations and analyses of technologies for the non-intrusive inspection of containers for illicit substances. These technologies span the range of nuclear, X-ray, and chemical techniques used in nondestructive sample analysis. ANL has performed assessments of nuclear and X-ray inspection concepts and undertaken site visits with developers to understand the capabilities and the range of applicability of candidate systems. ANL and HARC have provided support to law enforcement agencies (LEAs), including participation in numerous field studies. Both labs have provided staff to assist in the Narcotics Detection Technology Assessment (NDTA) program for evaluating drug detection systems. Also, the two labs are performing studies of drug contamination of currency. HARC has directed technical evaluations of automated ballistics imaging and identification systems under consideration by law enforcement agencies. ANL and HARC have sponsored workshops and a symposium, and are participating in a Non-Intrusive Inspection Study being led by Dynamics Technology, Incorporated.

  7. Syv veje til branding

    DEFF Research Database (Denmark)

    Hermansen, Judy

    2008-01-01

    Mange brandingbøger kommer med én bestemt opskrift på, hvad branding er for noget, og hvad det er for nogle strategier, man skal anlægge. Men der ligger altid mange antagelser bag de gode råd, som bare aldrig bliver sagt explicit. Hvilke antagelser bygger relationsteorien fx på? Eller Martin...

  8. Utilization of arylaliphatic nitriles by haloalkaliphilic Halomonas nitrilicus sp. nov. isolated from soda soils

    NARCIS (Netherlands)

    Chmura, A.; Shapovalova, A.A.; Van Pelt, S.; Van Rantwijk, F.; Tourova, T.P.; Muyzer, G.; Sorokin, D.Y.

    2008-01-01

    An enrichment culture from saline soda soils, using acetate as carbon and energy source and 2- phenylpropionitrile as nitrogen source (PPN) at pH 10, resulted in the isolation of strain ANL-αCH3. The strain was identified as a representative of the genus Halomonas in the Gammaproteobacteria. The bac

  9. Proposed environmental remediation at Argonne National Laboratory, Argonne, Illinois

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    The Department of Energy (DOE) has prepared an Environmental Assessment evaluating proposed environmental remediation activity at Argonne National Laboratory-East (ANL-E), Argonne, Illinois. The environmental remediation work would (1) reduce, eliminate, or prevent the release of contaminants from a number of Resource Conservation and Recovery Act (RCRA) Solid Waste Management Units (SWMUs) and two radiologically contaminated sites located in areas contiguous with SWMUs, and (2) decrease the potential for exposure of the public, ANL-E employees, and wildlife to such contaminants. The actions proposed for SWMUs are required to comply with the RCRA corrective action process and corrective action requirements of the Illinois Environmental Protection Agency; the actions proposed are also required to reduce the potential for continued contaminant release. Based on the analysis in the EA, the DOE has determined that the proposed action does not constitute a major federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (NEPA). Therefore, the preparation of an Environmental Impact Statement is not required.

  10. Proposed environmental remediation at Argonne National Laboratory, Argonne, Illinois

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) has prepared an Environmental Assessment evaluating proposed environmental remediation activity at Argonne National Laboratory-East (ANL-E), Argonne, Illinois. The environmental remediation work would (1) reduce, eliminate, or prevent the release of contaminants from a number of Resource Conservation and Recovery Act (RCRA) Solid Waste Management Units (SWMUs) and two radiologically contaminated sites located in areas contiguous with SWMUs, and (2) decrease the potential for exposure of the public, ANL-E employees, and wildlife to such contaminants. The actions proposed for SWMUs are required to comply with the RCRA corrective action process and corrective action requirements of the Illinois Environmental Protection Agency; the actions proposed are also required to reduce the potential for continued contaminant release. Based on the analysis in the EA, the DOE has determined that the proposed action does not constitute a major federal action significantly affecting the quality of the human environment within the meaning of the National Environmental Policy Act of 1969 (NEPA). Therefore, the preparation of an Environmental Impact Statement is not required

  11. Research, development and demonstration of nickel-zinc batteries for electric vehicle propulsion. Annual report, 1978

    Energy Technology Data Exchange (ETDEWEB)

    1979-10-01

    The work carried out under the Yardney Contract with ANL for R, D and D on nickel zinc batteries over the past year was directed in three major areas: (1) elucidating the failure modes of the nickel-zinc battery system; (2) improving performance of the system; and (3) effecting a cost reduction program. Progress on the three areas is reported. (TFD)

  12. Argonne Code Center: compilation of program abstracts

    International Nuclear Information System (INIS)

    This publication is the tenth supplement to, and revision of, ANL-7411. It contains additional abstracts and revisions to some earlier abstracts and other pages. Sections of the document are as follows: preface; history and acknowledgements; abstract format; recommended program package contents; program classification guide and thesaurus; and abstract collection

  13. Inspection and monitoring plan, contaminated groundwater seeps 317/319/ENE Area, Argonne National Laboratory

    International Nuclear Information System (INIS)

    During the course of completing the Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) in the 317/319/East-Northeast (ENE) Area of Argonne National Laboratory-East (ANL-E), groundwater was discovered moving to the surface through a series of groundwater seeps. The seeps are located in a ravine approximately 600 ft south of the ANL-E fence line in Waterfall Glen Forest Preserve. Samples of the seep water were collected and analyzed for selected parameters. Two of the five seeps sampled were found to contain detectable levels of organic contaminants. Three chemical species were identified: chloroform (14--25 microg/L), carbon tetrachloride (56--340 microg/L), and tetrachloroethylene (3--6 microg/L). The other seeps did not contain detectable levels of volatile organics. The nature of the contaminants in the seeps will also be monitored on a regular basis. Samples of surface water flowing through the bottom of the ravine and groundwater emanating from the seeps will be collected and analyzed for chemical and radioactive constituents. The results of the routine sampling will be compared with the concentrations used in the risk assessment. If the concentrations exceed those used in the risk assessment, the risk calculations will be revised by using the higher numbers. This revised analysis will determine if additional actions are warranted

  14. Emissionsfaktorer og emissionsopgørelse for decentral kraftvarme

    DEFF Research Database (Denmark)

    Nielsen, M.; Illerup, J. B.

    Der er udarbejdet nye emissionsfaktorer for decentrale kraftvarmeværker <25 MWe. Emissionsfaktorerne er baseret på såvel projektmålinger som eksisterende målinger foretaget på danske værker. Følgende anlægstyper er omfattet af udred-ningen: Affaldsbaseret kraftvarme, halm- og træfyrede kraftvarme...

  15. Calculation of the limiting CESSAR Feedwater Line-Break and Steam Line-Break transients

    International Nuclear Information System (INIS)

    Argonne National Laboratory (ANL), under contract to the Nuclear Regulatory Commission, performed audit calculations of the limiting Feedwater Line Break (FLB) and Steam Line Break (SLB) transients presented in the CESSAR FSAR. The results of the FLB and SLB calculations are discussed

  16. Carex vulpinoidea Michx., een neofiet voor Europa

    OpenAIRE

    Corporaal, A.

    1988-01-01

    Häufig ist es schwierig festzustellen, ob eine nicht einheimische Art adventiv genannt werden kann. Anläßlich von Funden der amerikanischen Carex vulpinoidea wird auf diese Fragestellung eingegangen. Vergleichende Untersuchungen der Habitate ergibt, daß C. vulpinoidea als Neophyt angesehen werden muß.

  17. Sloshing analysis of tanks containing multiple fluid layers

    International Nuclear Information System (INIS)

    The effect of liquid density changes in high level radioactive liquid waste storage tanks is studied. The density variations with the liquid depth is modeled by layers of piece wise constant densities. A computational formulation based on the finite element method is presented. The computer code FLUSTR-ANL has been modified for the analysis of the sloshing response under seismic excitation

  18. Heavy ion fusion program. Semi-annual progress report, October 1, 1979-March 30, 1980

    International Nuclear Information System (INIS)

    HIF activity at ANL during FY 1980 has been primarily concentrated on conceptual design work, and on initial tests of the independently-phased rf acceleration cavities. Calculations for near-term foil-heating experiments were carried out, and a specific cost-effective synchrotron (Beam Development Facility) plan was developed. Program logics were further refined, and some conceptual reactor issues were addressed

  19. Faktorer i psykoterapeuters faglige udvikling

    DEFF Research Database (Denmark)

    Jacobsen, Claus Haugaard; Nielsen, Jan; Mathisen, Birgit Bork

    2010-01-01

    Denne artikel gennemgår den senere tids udforskning af psykoterapeuters faglige udvikling, idet der anlægges et udviklingspsykopatologisk perspektiv. Her inddrages psykoterapeuters personlige karakteristika og på baggrund af foreliggende forskningsresultater diskuteres begrebet ”psykoterapeut-egn...

  20. Energieffektiv rejektvandsrensning - den hollandske genvej

    DEFF Research Database (Denmark)

    Maribo, Peder

    Fjernelse af kvælstof fra rejektvand kan ske uden kulstofkilde i en proces, hvor ammonium oxideres til nitrit, der herefter reagerer med ammonium til atmosfærisk kvælstof. I Holland er der etableret flere fundskala anlæg, der betyder en billig og effektiv fjernelse af kvælstof fra internt spildev...

  1. Argonne Code Center: compilation of program abstracts

    Energy Technology Data Exchange (ETDEWEB)

    Butler, M.K.; DeBruler, M.; Edwards, H.S.

    1976-08-01

    This publication is the tenth supplement to, and revision of, ANL-7411. It contains additional abstracts and revisions to some earlier abstracts and other pages. Sections of the document are as follows: preface; history and acknowledgements; abstract format; recommended program package contents; program classification guide and thesaurus; and abstract collection. (RWR)

  2. Burn-Up Dependence of Bubble Morphology of Uranium Silicide Dispersion Fuels Used in Research Reactor

    International Nuclear Information System (INIS)

    Burn-up dependence of fission gas bubble morphology of U3Si2-Al and U3Si-Al dispersion fuels are reviewed with the data of ANL(Argonne Nation Laboratory) and KAERI(Korea Atomic Energy Research Institute

  3. Kitaani Pinngortitaq pinngortitamillu atuineq avatangiisitigut naliliiffigineqarpoq

    DEFF Research Database (Denmark)

    Voigt, Steen

    2008-01-01

    For første gang foreligger i rapportform en samlende beskrivelse af en stor del af plante- og dyrelivet i Vestgrønland fra Nuuk til Sisimiut. Rapporten "Aluminiumssmelter og vandkraft i det centrale Vestgrønland" indgår i grundlaget for en strategisk miljøvurdering af anlæggelsen af et aluminiums...

  4. Natur og naturudnyttelse i Vestgrønland miljøvurderet

    DEFF Research Database (Denmark)

    Voigt, Steen

    2008-01-01

    For første gang foreligger i rapportform en samlende beskrivelse af en stor del af plante- og dyrelivet i Vestgrønland fra Nuuk til Sisimiut. Rapporten "Aluminiumssmelter og vandkraft i det centrale Vestgrønland" indgår i grundlaget for en strategisk miljøvurdering af anlæggelsen af et aluminiums...

  5. Pårørendeinddragelse

    DEFF Research Database (Denmark)

    Hansen, Jeppe Oute

    "Introduktion: Det er et væsentligt sundhedspolitisk indsatsområde at inddrage pårørende i pleje, behandling og rehabilitering af mennesker med sindslidelser såvel som mennesker med somatiske lidelser. Med udgangspunkt i eksempler fra psykiatriske sammenhænge anlægges i dette kapitel et mere krit...

  6. Plutonium working group report on environmental, safety and health vulnerabilities associated with the Department's plutonium storage. Volume II, Appendix B, Part 8: Argonne National Laboratory - East and New Brunswick Laboratory site assessment team report

    International Nuclear Information System (INIS)

    The objective of the Plutonium ES ampersand H Vulnerability Assessment Project is to conduct a comprehensive assessment of the environmental, safety and health (ES ampersand H) vulnerabilities arising from the Department's storage and handling of Its current plutonium holdings. The term open-quote ES ampersand H vulnerabilitiesclose quotes is defined for the purpose of this project to mean conditions or weaknesses that could lead to unnecessary or increased radiation exposure of workers, release of radioactive materials to the environment, or radiation exposure of the public. The assessment will identify and prioritize ES ampersand H vulnerabilities, and will serve as an information base for identifying corrective actions and options for the safe management of fissile materials. The Argonne National Laboratory-East (ANL-E) Site Assessment Team (SAT) was formed from Department of Energy (DOE) Chicago Operations Office-Argonne Area Office Personnel, to conduct a self-assessment of the plutonium holdings and any associated ES ampersand H vulnerabilities at the ANL-E site

  7. THE NOX SYSTEM IN NUCLEAR WASTE

    Science.gov (United States)

    A collaborative program between ANL and PNNL is proposed to study the radiation, and radiation induced, chemistry of the NOx system in waste simulants. The study will develop a computer model providing predictive capabilities for future EM operations including the characterizatio...

  8. Minedrift og miljø i Grønland

    DEFF Research Database (Denmark)

    Johansen, P.; Asmund, G.; Glahder, C. M.;

    zink, som er frigjort fra de mineraler, som er brudt og oparbejdet. Forureningen kommer især fra tailings fra de anlæg, hvor indholdet af værdifulde mineraler i malmen er blevet adskilt og opkoncentreret. En anden vigtig forureningskilde har været såkaldt gråbjerg, dvs. brudt materiale, hvor...

  9. Standard reference and other important nuclear data. Supplement 1 to the report BNL-NCS-51123 (Dec. 1979) = ENDF-300 = IAEA-NDS-15/300 (microfiche)

    International Nuclear Information System (INIS)

    The document contains inserts to be added to the report 'Standard Reference and Other Important Nuclear Data' (BNL-NCS-51123, ENDF-300), including the following two articles: Fast Neutron Capture in 238U and 232Th by W.P. Poentiz (ANL), and 239Pu Decay Power Discrepancy by T.R. England and P.G. Young (LANL)

  10. Perspektiven für Information und Kommunikation in der Psychologie

    OpenAIRE

    Weichselgartner, Erich

    2005-01-01

    Vortrag von Erich Weichselgartner (Zentrum für Psychologische Information und Dokumentation, ZPID, Trier und Mitglied der IUK-Kommission der Deutschen Gesellschaft für Psychologie) anlässlich der 11. Iuk-Jahrestagung 2005 in Bonn. Thema: Stand und Aussichten der IUK-Initiativen im Fach Psychologie unter besonderer Berücksichtigung des Open Access.

  11. High energy physics. Progress report, March 1, 1980-February 28, 1981

    International Nuclear Information System (INIS)

    During this contract year results of several ANL/ZGS experiments have been published, and the data analysis of three others is in various stages of completion. PPT VI was refurburished and made into a portable polarized target system. Several new experiments have been proposed. Separate abstracts were prepared for two experiments that have produced data but have not yet been published. 7 figures

  12. Undersøgelse af overfladejævnhed af slotsgrusstier

    DEFF Research Database (Denmark)

    Kristoffersen, Palle

    2010-01-01

    Ni år gamle "slotsgrusstier" i Frederiksberg Have er blevet riflede som et vaskebræt og lever ikke længere op til kravet i Normer og Vejledning for Anlægsgartnerarbejde NOVA. Skov & Landskab har undersøgt situationen, der først og fremmest skyldes materialeflytninger....

  13. Kombinerede sol/varmepumpeanlæg i praksis

    DEFF Research Database (Denmark)

    Andersen, Elsa; Furbo, Simon

    2010-01-01

    I rapporten analyseres målinger fra kombinerede sol/varmepumpeanlæg i praksis. Anlæggene er installeret af Nordic Energy Group og målingerne er ligeledes foretaget af Nordic Energy Group. Analysen viser at energiforbruget og energiprisen kan reduceres betragteligt ved at installere et kombianlæg i...

  14. Erwartungslücke auch beim Audit Committee

    OpenAIRE

    Leibfried, Peter

    2008-01-01

    Peter Leibfried hält anlässlich des fünfjährigen Jubiläums von KPMG's Audit Committee Institute eine Festrede zum Thema "Erwartungslücke auch beim Audit Committee" im Grand Hotel Dolder in Zürich.

  15. Resource recovery from waste incineration residues

    DEFF Research Database (Denmark)

    Allegrini, Elisa

    Affaldsforbrænding er i mange lande en vigtig teknologi til behandling og energiudnyttelse af affald. Udover energi resulterer forbrænding også i produktion af asker. Størstedelen af askerne udgøres af slagge, som efter behandling har gode tekniske egenskaber og kan anvendes til bygge- og anlægsf...

  16. Decontamination and dismantlement of the building 200/205 pneumatic transfer tube at Argonne National Laboratory-East project final report.

    Energy Technology Data Exchange (ETDEWEB)

    Wiese, E. C.

    1998-12-11

    The Building 200/205 Pneumatic Transfer Tube D&D Project was directed toward the following goals: Remove any radioactive and hazardous materials associated with the transfer tube; Survey the transfer tube to identify any external contamination; Remove the transfer tube and package for disposal; Survey the soil and sand surrounding the transfer tube for any contamination; and Backfill the trench in which the tube sat and restore the area to its original condition. These goals had been set in order to eliminate the radiological and hazardous safety concerns inherent in the buried transfer tube and to allow, upon completion of the project, the removal of this project from the ANL-E action item list. The physical condition of the transfer tube and possible nuclear fuel samples lost in the tube were the primary areas of concern, while the exact location of the transfer tube was of secondary concern. ANL-E health physics technicians collected characterization data from the ends of the Building 200/205 pneumatic transfer tube in January 1998. The characterization surveys identified contamination to a level of 67,000 dpm (1,117 Bq) ({beta}/{gamma}) and 20,000 dpm (333 Bq) {alpha} smearable at the opening.

  17. Decontamination and dismantlement of the building 594 waste ion exchange facility at Argonne National Laboratory-East project final report.

    Energy Technology Data Exchange (ETDEWEB)

    Wiese, E. C.

    1998-11-23

    The Building 594 D&D Project was directed toward the following goals: Removal of any radioactive and hazardous materials associated with the Waste Ion Exchange Facility; Decontamination of the Waste Ion Exchange Facility to unrestricted use levels; Demolition of Building 594; and Documentation of all project activities affecting quality (i.e., waste packaging, instrument calibration, audit results, and personnel exposure) These goals had been set in order to eliminate the radiological and hazardous safety concerns inherent in the Waste Ion Exchange Facility and to allow, upon completion of the project, unescorted and unmonitored access to the area. The ion exchange system and the resin contained in the system were the primary areas of concern, while the condition of the building which housed the system was of secondary concern. ANL-E health physics technicians characterized the Building 594 Waste Ion Exchange Facility in September 1996. The characterization identified a total of three radionuclides present in the Waste Ion Exchange Facility with a total activity of less than 5 {micro}Ci (175 kBq). The radionuclides of concern were Co{sup 60}, Cs{sup 137}, and Am{sup 241}. The highest dose rates observed during the project were associated with the resin in the exchange vessels. DOE Order 5480.2A establishes the maximum whole body exposure for occupational workers at 5 rem (50 mSv)/yr; the administrative limit at ANL-E is 1 rem/yr (10 mSv/yr).

  18. Metabolic gene expression changes in astrocytes in Multiple Sclerosis cerebral cortex are indicative of immune-mediated signaling

    KAUST Repository

    Zeis, T.

    2015-04-01

    Emerging as an important correlate of neurological dysfunction in Multiple Sclerosis (MS), extended focal and diffuse gray matter abnormalities have been found and linked to clinical manifestations such as seizures, fatigue and cognitive dysfunction. To investigate possible underlying mechanisms we analyzed the molecular alterations in histopathological normal appearing cortical gray matter (NAGM) in MS. By performing a differential gene expression analysis of NAGM of control and MS cases we identified reduced transcription of astrocyte specific genes involved in the astrocyte–neuron lactate shuttle (ANLS) and the glutamate–glutamine cycle (GGC). Additional quantitative immunohistochemical analysis demonstrating a CX43 loss in MS NAGM confirmed a crucial involvement of astrocytes and emphasizes their importance in MS pathogenesis. Concurrently, a Toll-like/IL-1β signaling expression signature was detected in MS NAGM, indicating that immune-related signaling might be responsible for the downregulation of ANLS and GGC gene expression in MS NAGM. Indeed, challenging astrocytes with immune stimuli such as IL-1β and LPS reduced their ANLS and GGC gene expression in vitro. The detected upregulation of IL1B in MS NAGM suggests inflammasome priming. For this reason, astrocyte cultures were treated with ATP and ATP/LPS as for inflammasome activation. This treatment led to a reduction of ANLS and GGC gene expression in a comparable manner. To investigate potential sources for ANLS and GGC downregulation in MS NAGM, we first performed an adjuvant-driven stimulation of the peripheral immune system in C57Bl/6 mice in vivo. This led to similar gene expression changes in spinal cord demonstrating that peripheral immune signals might be one source for astrocytic gene expression changes in the brain. IL1B upregulation in MS NAGM itself points to a possible endogenous signaling process leading to ANLS and GGC downregulation. This is supported by our findings that, among others

  19. IPNS upgrade: A feasibility study

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    Many of Argonne National Laboratory`s (ANL`s) scientific staff members were very active in R&D work related to accelerator-based spoliation sources in the 1970s and early 1980s. In 1984, the Seitz/Eastman Panel of the National Academy of Sciences reviewed U.S. materials science research facilities. One of the recommendations of this panel was that the United States build a reactor-based steady-state source, the Advanced Neutron Source (ANS), at Oak Ridge National Laboratory. Subsequently, R&D activities related to the design of an accelerator-based source assumed a lower priority. The resumption of pulsed-source studies in this country started simultaneously with design activities in Europe aimed at the European Spallation Source (ESS). The European Community funded a workshop in September 1991 to define the parameters of the ESS. Participants in this workshop included both accelerator builders and neutron source users. A consortium of European countries has proposed to build a 5-MW pulsed source, and a feasibility study is currently under way. Soon after the birth of the ESS, a small group at ANL set about bringing themselves up to date on pulsed-source information since 1984 and studied the feasibility of upgrading ANL`s Intense Pulsed Neutron Source (IPNS) to 1 MW by means of a rapidly cycling synchrotron that could be housed, along with its support facilities, in existing buildings. In early 1993, the Kohn panel recommended that (1) design and construction of the ANS should be completed according to the proposed project schedule and (2) development of competitive proposals for cost-effective design and construction of a 1-MW pulsed spallation source should be authorized immediately.

  20. The development and equivalence analysis of mandarin acceptable noise level test materials%普通话可接受噪声级测试材料的开发与等价性评估

    Institute of Scientific and Technical Information of China (English)

    陈建勇; 张华; 陈静; 陈雪清; 郭连生; 曹文; 吴燕君; 李玉玲

    2011-01-01

    目的 开发普通话版可接受噪声级(acceptable noise level,ANL)测试材料.方法 从小学、初中和高中语文教材中选取3篇难易程度不同的短文材料;选取31例听力言语正常人分别进行3种材料的ANL测试,获得3种材料下的最舒适响度级(most comfortable loudness,MCL)、最大背景噪声级(background noise level,BNL)和ANL值.结果 听力正常人群个体问ANL值存在很大差异(F=22.414,P<0.05),变化范围从-1~21 dB HL不等;但3组测试材料的MCL、BNL和ANL值均无统计学差异.相关分析结果显示,3组材料间MCL与ANL的相关性依次为:,r=0.532,P=0.002; ,r=0.474,P=0.007; ,r=0.530,P=0.002.结论 ANL值不受测试材料的影响,可利用不同性质的材料进行ANL测试,便于临床该项测试的开展和应用:初步选取相关性较好且较易理解的作为普通话ANL正式测试材料,用于助听器选配和人工耳蜗植入效果的评估.%OBJECTIVE To develop the mandarin test material of acceptable noise level (ANL) .METHODS ANL tests were measured for 31 normal hearing participants using the different intelligible materials. For each discourse, the most comfortable loudness (MCL) and background noise level (BNL)were found. The ANL was then computed by subtracting the mean BNL from MCL. RESULTS Statistic analysis indicated that there were significant differences of the ANL (P< 0.05) among the normal hearing listeners,but no differences of the three materials' MCL, BNL, and ANL were found. The Pearson correlation coefficients between MCL-ANL showed that "The Spring Festival of Beijing" had much better correlation than the other two discourses. CONCLUSION ANL may not change as speech intelligibility changes and can be measured using various types of speech signals; "The Spring Festival of Beijing" will be used as the mandarin ANL test material to evaluate the outcomes of hearing aid fitting and cochlear implantation.

  1. Preweaning performance and body composition of calves from straightbred Nellore and Bos taurus x Nellore crosses.

    Science.gov (United States)

    Calegare, L; Alencar, M M; Packer, I U; Leme, P R; Ferrell, C L; Lanna, D P D

    2009-05-01

    The objectives were to evaluate preweaning performance, body composition, and efficiency of calves representing straightbred Nellore (NL), F(1), and 3-breed-cross systems. Energy requirements, milk production, and efficiency of 39 cow-calf pairs were recorded from straightbred NL calves from NL cows (10), crossbred (Angus-sired) calves from NL cows (ANL: 9), and crossbred calves (CC; Canchim-sired: 5/8 Charolais, 3/8 Zebu) from ANL (10) and Simmental x NL (10) cows. Cows and their respective calves were individually fed from birth to weaning (17 to 190 d postpartum). At 38 d of age, corn silage (7.8% CP, 2.19 Mcal of ME/kg of DM) was available to calves ad libitum. Milk production at 42, 98, 126, and 180 d postpartum was recorded by weighing calves before and after suckling. The ratio between GE and ME of milk was considered 1:0.93. Calves were slaughtered at weaning and the 9th-, 10th-, and 11th-rib section was removed for body composition estimation. The ANL calves were lighter (P body energy - birth body energy) than the NL calves (388 +/- 23 for ANL, and 438 +/- 15 for CC vs. 312 +/- 22 Mcal for NL calves). Percentages of water (P = 0.74) and chemical fat (P = 0.51) were similar among groups (63.7 +/- 0.6 and 14.3 +/- 0.7% for ANL calves, 63.1 +/- 0.4 and 14.7 +/- 0.5% for CC calves, and 63.3 +/- 0.6 and 13.7 +/- 0.7% of empty BW for water and chemical fat, respectively, for NL calves). Energetic efficiency (kcal of retained energy/Mcal of ME intake) was similar (P = 0.52) among groups (358 +/- 22 for ANL calves, 355 +/- 14 for CC calves, and 327 +/- 22 for NL calves). The greater BW gains and the differences in empty body composition at weaning were not enough to compensate for the greater ME intake of crossbreds. In this study, the crossbreeding systems evaluated increased preweaning calf performance but did not affect gross or energetic calf efficiency. PMID:19122045

  2. The Usage of Mandarin Acceptable Noise Level Test in Outcome Measurements of Hearing Aids%可接受噪声级测试在助听器效果评估中的初步应用

    Institute of Scientific and Technical Information of China (English)

    陈建勇; 张华; 陈雪清; 吴燕君; 孔颖; 郭连生; 李靖; 李玉玲

    2011-01-01

    目的 探讨可接受噪声级(acceptable noise level,ANL)测试在普通话听障人群助听器效果评估中的应用.方法 选取佩带助听器3个月~3年的中度到中重度听障者37例,根据助听器使用情况将其分为全天使用助听器组、部分时间使用组和拒绝使用组;利用前期经过等价性评估的普通话可接受噪声级测试材料,对三组人群依次进行裸耳和助听下的ANL测试,日常生活助听器满意度问卷(the satisfaction with amplification in daily life,SADL)评估,分析三组ANL值和SADL得分的差异.结果 ①37例听障者个体自身裸耳和助听下最舒适响度级(most comfortable level,MCL)、背景噪声级(background noise level,BNL)值差异有统计学意义(P0.05);②全天使用助听器组裸耳下ANL值明显低于部分时间和拒绝使用助听器组(P0.05);④Pearson相关分析显示:裸耳ANL值与听障者性别、年龄均无相关性(P>0.05),与气导平均听阈存在较弱相关性(r=0.460,P=0.004).结论 可接受噪声级测试可反映个体耐受噪声能力的大小,可初步利用其来预估助听器选配效果.%Objective The purpose of this study was to compare the difference of ANL value among the full -time hearing aid users, part-time users, and nonusers,and then to determine the relationship between the hearing aid outcomes of the three groups and ANL values. Methods 37 hearing aid users for 3 months to 3 years were selected for this research. Listeners were assigned to one of the three groups based on patterns of hearing aid use:full-time use (whenever hearing aids are needed), part-time use (occasional use), and non use. ANL test was measured for the three groups using the mandarin acceptable noise level test material. The mandarin ANL test was measured in aided and unaided conditions for each group; and the outiones were evaluated by SADL. The results were analyzed statistically with SPSS13.0 to determine the differences of the ANL value for the

  3. Studies of light radon evaporation residues

    International Nuclear Information System (INIS)

    Predictions of a region of deformation in the N82 nuclides have been made but remain untested by experimental investigation. A series of experiments has been initiated using the ESTU tandem at Yale and the ATLAS facility at ANL, to investigate the possibilities of performing in-beam spectroscopy of heavy nuclei using heavy-ion, fusion reactions. In a mass region where fission is the predominant process at each stage in the decay of the compound system, sensitive selection techniques are necessary to tag the survival of heavy residues. At Yale x-rays characteristic of the residues have been used as a trigger, whereas the Fragment Mass Analyzer at ANL enables mass tagging of recoiling nuclei. Projectiles from 19F to 31P have been used on natural Ta targets and the 181Ta(27Al,xn) 208-xRn reaction has been studied in detail

  4. Analytical Chemistry Laboratory progress report for FY 1984

    International Nuclear Information System (INIS)

    Technical and administrative activities of the Analytical Chemistry Laboratory (ACL) are reported for fiscal year 1984. The ACL is a full-cost-recovery service center, with the primary mission of providing a broad range of technical support services to the scientific and engineering programs at ANL. In addition, ACL conducts a research program in analytical chemistry, works on instrumental and methods development, and provides analytical services for governmental, educational, and industrial organizations. The ACL is administratively within the Chemical Technology Division, the principal user, but provides technical support for all of the technical divisions and programs at ANL. The ACL has three technical groups - Chemical Analysis, Instrumental Analysis, and Organic Analysis. Under technical activities 26 projects are briefly described. Under professional activities, a list is presented for publications and reports, oral presentations, awards and meetings attended. 6 figs., 2 tabs

  5. Siegel[JMMM 7,312(`78)] FIRST EXPERIMENTAL DISCOVERY of Giant-Magnetoresistance Decade Pre ``Fert'' and ``Gruenberg'' ['88 - `78] = 10-Years = One-Decade Sounds, for Nuclear-Power Naïve ``Panacea'' for Global-Warming/Climate-Chan

    Science.gov (United States)

    Hoffmann, Masterace; Siegel, Edward

    Siegel[JMMM 7,312(`78); Monju (12/'95) LMFBR PREDICTION!!!] following: Wigner[JAP 17,857(`46)]-(Alvin)Weinberg(ANL/ORNL/ANS)-(Sidney)Siegel(ANL/ORNL/ANS)-Seitz-Overhauser-Rollnick-Pollard-Lofaro-Markey-Pringle[Nuclear-PowerFrom Physics to Politics(`79)] FIRST EXPERIMENTAL DISCOVERY [SiegelOstwald-ripening/spinodal-decompositio/OVERageing-EMBRITTLEMENT/THERMAL-leading-to-mechanical (TLTM)-INstability/``sensitization'' in: nuclear-reactors/spent-fuel dry-casks/refineries/jet/missile/rocket-engines/...SOUNDS A DIRE WARNING FOR NAIVE Hansen-Sommerville-Holdren-DOE-NRC-OSTP-WNA-NEI-AIP-APS-...calls/media-hype/P.R./spin-doctoring for carbon-``free'' nuclear-power as a SUPPOSED ``panacea'' for climate-change/global-warming: ``TRUST BUT VERIFY!!!'' ; a VERY LOUD CAVEAT EMPTOR!!!

  6. Lagerdimensionering vid bearbetningsproduktionen hos Volvo Powertrain i Skövde

    OpenAIRE

    Engström, Marcus; Gembäck, Johan

    2009-01-01

    Volvo Powertrain tillverkar motorer och drivlinor till AB Volvos samtliga dotterbolag förutom Volvo Aero. Vid anläggningen i Skövde tillverkas motorer och delar till motorer och växellådor och vid anläggningen finns alla tre nödvändiga produktionsområden; gjuteri, bearbetning och montering. När rådande lågkonjunktur slog till stod bearbetningen med väldigt höga lagernivåer vilka företaget snabbt tvingades sänka då det blev huvudfokus från koncernledningen att minska det bundna kapitalet. Utan...

  7. Tensile properties of vanadium-base alloys irradiated in the Fusion-1 low-temperature experiment in the BOR-60 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Tsai, H.; Gazda, J.; Nowicki, L.J.; Billone, M.C.; Smith, D.L. [Argonne National Lab., IL (United States)

    1998-09-01

    The irradiation has been completed and the test specimens have been retrieved from the lithium-bonded capsule at the Research Institute of Atomic Reactors (RIAR) in Russia. During this reporting period, the Argonne National Laboratory (ANL) tensile specimens were received from RIAR and initial testing and examination of these specimens at ANL has been completed. The results, corroborating previous findings showed a significant loss of work hardening capability in the materials. There appears to be no significant difference in behavior among the various heats of vanadium-base alloys in the V-(4-5)Cr-(4-5)Ti composition range. The variations in the preirradiation annealing conditions also produced no notable differences.

  8. Pilot-scale equipment development for pyrochemical treatment of spent oxide fuel

    International Nuclear Information System (INIS)

    Fundamental objectives regarding spent nuclear fuel treatment technologies include, first, the effective distribution of spent fuel constituents among product and stable waste forms and, second, the minimization and standardization of waste form types and volumes. Argonne National Laboratory (ANL) has developed and is presently demonstrating the electrometallurgical treatment of sodium-bonded metal fuel from Experimental Breeder Reactor II, resulting in an uranium product and two stable waste forms, i.e. ceramic and metallic. Engineering efforts are underway at ANL to develop pilot-scale equipment which would precondition irradiated oxide fuel via pyrochemical processing and subsequently allow for electrometallurgical treatment of such non-metallic fuels into standard product and waste forms. This paper highlights the integration of proposed spent oxide fuel treatment with existing electrometallurgical processes. System designs and technical bases for development of pilot-scale oxide reduction equipment are also described

  9. EPICS release 3.11 specific documentation -- EPICS release notes for 3.11

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-01-19

    EPICS release 3.11 is now ready for user testing. A person who wants to set up a simplified application environment to boot an IOC and create databases using R3.11 should follow the directions in Appendix B, page 27, of the EPICS Source/Release Control Manual, Sept. 20, 1993. The R3.11 EPICS path at ANL/APS is /net/phebos/epics/R3.11 so the command to get the new release is /net/phebos/epics/R3.11/Unix/share/bin/getrel /net/phebos/epics/R3.11. An existing R3.8 short form report can be copied to this new directory and used to create a database. ANL/APS is currently testing an Application Developers Source/Release control system. It is not yet ready for general distribution. Attached are the EPICS R3.11 release notes.

  10. Argonne National Laboratory patent portfolio

    International Nuclear Information System (INIS)

    This booklet contains the abstracts of all active U. S. patents on technology items that originated at ANL, the applicability of which is not limited to nuclear reactors. Also listed are the titles of all ANL-originated nuclear-related U. S. patents that are still in force. Selected technology items for which patent applications have been filed and are available for licensing are included in several categories. Categories included in this booklet are as follows: atmospheric and earth sciences; biological and medical sciences; chemistry and chemical engineering; cryogenics and superconductivity; electronics and electrical engineering; energy conversion; measurements and controls; methods and devices; materials and fabrication; physics, accelerators and fusion; and selected nuclear-related technology

  11. The procedures used to review safety analysis reports for packagings submitted to the US Department of Energy for certification

    International Nuclear Information System (INIS)

    This paper presents an overview of the procedures used at the Argonne National Laboratory (ANL) to review Safety Analysis Reports for Packagings (SARPs) submitted to the US Department of Energy (DOE) for issuance of a Certificate of Compliance. Prior to certification and shipment of a packaging for the transport of radioactive materials, a SARP must be prepared describing the design, contents, analyses, testing, and safety features of the packaging. The SARP must be reviewed to ensure that the specific packaging meets all DOE orders and federal regulations for safe transport. The ANL SARP review group provides an independent review and evaluation function for the DOE to ensure that the packaging meets all the prescribed requirements. This review involves many disciplines and includes evaluating the general information, drawings, construction details, operating procedures, maintenance and test programs, and the quality assurance plan for compliance with requirements. 14 refs., 6 figs

  12. Analytical Chemistry Laboratory progress report for FY 1989

    International Nuclear Information System (INIS)

    The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year 1989 (October 1988 through September 1989). The Analytical Chemistry Laboratory is a full-cost-recovery service center, with the primary mission of providing a broad range of analytical chemistry support services to the scientific and engineering programs at ANL. In addition, the ACL conducts a research program in analytical chemistry, works on instrumental and methods development, and provides analytical services for governmental, educational, and industrial organizations. The ACL handles a wide range of analytical problems, from routine standard analyses to unique problems that require significant development of methods and techniques

  13. Analytical Chemistry Laboratory progress report for FY 1985

    International Nuclear Information System (INIS)

    The Analytical Chemistry Laboratory is a full-cost-recovery service center, with the primary mission of providing a broad range of technical support services to the scientific and engineering programs at ANL. In addition, ACL conducts a research program in analytical chemistry, works on instrumental and methods development, and provides analytical services for governmental, educational, and industrial organizations. The ACL handles a wide range of analytical problems, from routine standard analyses to unique problems that require significant development of methods and techniques. The purpose of this report is to summarize the technical and administrative activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for Fiscal Year 1985 (October 1984 through September 1985). This is the second annual report for the ACL. 4 figs., 1 tab

  14. MNSR transient analyses and thermal-hydraulic safety margins for HEU and LEU cores using PARET

    International Nuclear Information System (INIS)

    Thermal-hydraulic performance characteristics of Miniature Neutron Source Reactors under long-term steady-state and transient conditions are investigated. Safety margins and limiting conditions attained during these events are determined. Modeling extensions are presented that enable the PARET/ANL code to realistically track primary loop heatup, heat exchange to the pool, and heat loss from the pool to air over the pool. Comparisons are made of temperature predictions for HEU and LEU fueled cores under transient conditions. Results are obtained using three different natural convection heat transfer correlations: the original (PARET/ANL version 5), Churchill-Chu, and an experiment- based correlation from the China Institute of Atomic Energy (CIAE). The MNSR, either fueled by HEU or by LEU, satisfies the design limits for long-term transient operation. (author)

  15. Automated reasoning applications to design validation and sneak function analysis

    International Nuclear Information System (INIS)

    Argonne National Laboratory (ANL) is actively involved in the LMFBR Man-Machine Integration (MMI) Safety Program. The objective of this program is to enhance the operational safety and reliability of fast-breeder reactors by optimum integration of men and machines through the application of human factors principles and control engineering to the design, operation, and the control environment. ANL is developing methods to apply automated reasoning and computerization in the validation and sneak function analysis process. This project provides the element definitions and relations necessary for an automated reasoner (AR) to reason about design validation and sneak function analysis. This project also provides a demonstration of this AR application on an Experimental Breeder Reactor-II (EBR-II) system, the Argonne Cooling System

  16. EPICS release 3.11 specific documentation -- EPICS release notes for 3.11

    International Nuclear Information System (INIS)

    EPICS release 3.11 is now ready for user testing. A person who wants to set up a simplified application environment to boot an IOC and create databases using R3.11 should follow the directions in Appendix B, page 27, of the EPICS Source/Release Control Manual, Sept. 20, 1993. The R3.11 EPICS path at ANL/APS is /net/phebos/epics/R3.11 so the command to get the new release is /net/phebos/epics/R3.11/Unix/share/bin/getrel /net/phebos/epics/R3.11. An existing R3.8 short form report can be copied to this new directory and used to create a database. ANL/APS is currently testing an Application Developers Source/Release control system. It is not yet ready for general distribution. Attached are the EPICS R3.11 release notes

  17. Status of the dynamic helium charging experiment (DHCE)

    International Nuclear Information System (INIS)

    Irradiation of the seven DHCE capsules was completed in the Materials Open Test Assembly (MOTA)-2B at the end of Cycle 12B in the Fast Flux Test Facility (FFTF). The accrued exposure was 203.3 effective full-power days (EFPDs), vis-a-vis the target exposure of 300 EFPDs. Peak damage in the samples was ∼29 displacement per atom (dpa). All seven capsules have been discharged from the FFTF and are being shipped to Argonne National Laboratory (ANL), where the samples will be retrieved from the capsules and distributed to the experimenters, including Monbusho of Japan, for examination and testing. A substantial effort is underway at ANL to retrieve the samples from the highly tritated capsules

  18. Design and experimental activities supporting commercial U.S. electron accelerator production of Mo-99

    International Nuclear Information System (INIS)

    99mTc, the daughter isotope of 99Mo, is the most commonly used radioisotope for nuclear medicine in the United States. Under the direction of the National Nuclear Security Administration (NNSA), Los Alamos National Laboratory (LANL) and Argonne National Laboratory (ANL) are partnering with North Star Medical Technologies to demonstrate the viability of large-scale 99Mo production using electron accelerators. In this process, 99Mo is produced in an enriched 100Mo target through the 100Mo(γ,n)99Mo reaction. Five experiments have been performed to date at ANL to demonstrate this process. This paper reviews the current status of these activities, specifically the design and performance of the helium gas target cooling system.

  19. The D and D of the Experimental Boiling Water Reactor (EBWR)

    International Nuclear Information System (INIS)

    Argonne National Laboratory has completed the D ampersand D of the Experimental Boiling Water Reactor. The Project consisted of decontaminating and for packaging as radioactive waste the reactor vessel and internals, contaminated piping systems, miscellaneous tanks, pumps, and associated equipment. The D ampersand D work involved dismantling process equipment and associated plumbing, ductwork drain lines, etc., performing size reduction of reactor vessel internals in the fuel pool, packaging and manifesting all radioactive and mixed waste, and performing a thorough survey of the facility after the removal of activated and contaminated material. Non-radioactive waste was disposed of in the ANL-E landfill or recycled. In January 1996 the EBWR facility was formally decommissioned and transferred from EM-40 to EM-30. This paper will discuss the details of this ten year effort

  20. Safety evaluation report related to the evaluation of low-enriched uranium silicide-aluminum dispersion fuel for use in non-power reactors

    International Nuclear Information System (INIS)

    Low-enriched uranium silicide-aluminum dispersion plate-type fuels have been extensively researched and developed under the international program, Reduced Enrichment in Research and Test Reactors. The international effort was led by Argonne National Laboratory (ANL) in the United States. This evaluation is based primarily on reports issued by ANL that discuss and summarize the developmental tests and experiments, including postirradiation examinations, of both miniature and full-sized plates of prototypical fuel compositions. This evaluation concludes that plate-type fuels suitable and acceptable for use in research and test reactors can be fabricated with U3Si2-Al dispersion compacts with uranium densities up to 4.8 g/cm3. 4 refs., 1 fig

  1. First production of potable water by OTEC (Ocean Thermal Energy Conversion) and its potential applications

    Science.gov (United States)

    Thomas, Anthony; Hillis, David L.

    An experiment--the Heat and Mass Transfer Scoping Test Apparatus--was built to obtain design data for a larger test that will assess the technical feasibility of the open-cycle OTEC process. (The closed-cycle concept was successfully demonstrated in 1979.) The DOE-funded project is a joint effort between Argonne National Laboratory (ANL) and the Solar Energy Research Institute (SERI). The apparatus was erected at the Natural Energy Laboratory of Hawaii and became operational in the summer of 1987. It is used by both ANL and SERI to conduct open-cycle OTEC experiments. After initial debugging, it produced 350 gallons per hour of potable water having a salinity of 86 ppM, one-fifth that of local tap water available at the test site.

  2. Simulation of charge breeding of rubidium using Monte Carlo charge breeding code and generalized ECRIS model.

    Science.gov (United States)

    Zhao, L; Cluggish, B; Kim, J S; Pardo, R; Vondrasek, R

    2010-02-01

    A Monte Carlo charge breeding code (MCBC) is being developed by FAR-TECH, Inc. to model the capture and charge breeding of 1+ ion beam in an electron cyclotron resonance ion source (ECRIS) device. The ECRIS plasma is simulated using the generalized ECRIS model which has two choices of boundary settings, free boundary condition and Bohm condition. The charge state distribution of the extracted beam ions is calculated by solving the steady state ion continuity equations where the profiles of the captured ions are used as source terms. MCBC simulations of the charge breeding of Rb+ showed good agreement with recent charge breeding experiments at Argonne National Laboratory (ANL). MCBC correctly predicted the peak of highly charged ion state outputs under free boundary condition and similar charge state distribution width but a lower peak charge state under the Bohm condition. The comparisons between the simulation results and ANL experimental measurements are presented and discussed. PMID:20192325

  3. Analytical Chemistry Laboratory: Progress report for FY 1988

    International Nuclear Information System (INIS)

    The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for fiscal year 1988 (October 1987 through September 1988). The Analytical Chemistry Laboratory is a full-cost recovery service center, with the primary mission of providing a broad range of analytical chemistry support services to the scientific and engineering programs at ANL. In addition, the ACL conducts a research program in analytical chemistry, works on instrumental and methods development, and provides analytical services for governmental, educational, and industrial organizations. The ACL handles a wide range of analytical problems, from routine standard analyses to unique problems that require significant development of methods and techniques

  4. User Interface Program for secure electronic tags

    International Nuclear Information System (INIS)

    This report summarizes and documents the efforts of Argonne National Laboratory (ANL) in developing a secure tag communication user interface program comprising a tag monitor and a communication tool. This program can perform the same functions as the software that was developed at the Lawrence Livermore National Laboratory (LLNL), but it is enhanced with a user-friendly screen. It represents the first step in updating the TRANSCOM Tracking System (TRANSCOM) by incorporating a tag communication screen menu into the main menu of the TRANSCOM user program. A working version of TRANSCOM, enhanced with ANL secure-tag graphics, will strongly support the Department of Energy Warhead Dismantlement/Special Nuclear Materials Control initiatives. It will allow commercial satellite tracking of the movements and operational activities of treaty-limited items and transportation vehicles throughout Europe and the former USSR, as well as the continental US

  5. Safety evaluation report related to the evaluation of low-enriched uranium silicide-aluminum dispersion fuel for use in non-power reactors

    Energy Technology Data Exchange (ETDEWEB)

    1988-07-01

    Low-enriched uranium silicide-aluminum dispersion plate-type fuels have been extensively researched and developed under the international program, Reduced Enrichment in Research and Test Reactors. The international effort was led by Argonne National Laboratory (ANL) in the United States. This evaluation is based primarily on reports issued by ANL that discuss and summarize the developmental tests and experiments, including postirradiation examinations, of both miniature and full-sized plates of prototypical fuel compositions. This evaluation concludes that plate-type fuels suitable and acceptable for use in research and test reactors can be fabricated with U/sub 3/Si/sub 2/-Al dispersion compacts with uranium densities up to 4.8 g/cm/sup 3/. 4 refs., 1 fig.

  6. Refurbishment of an Analytical Laboratory Hot Cell Facility

    International Nuclear Information System (INIS)

    An Analytical Laboratory Hot Cell (ALHC) Facility at Argonne National Laboratory-West (ANL-W) was in service for nearly thirty years. In order to comply with DOE regulations governing such facilities and meet ANL-W programmatic requirements, a major refurbishment effort was undertaken. To place the facility in compliance with current regulations, all penetrations within the facility were sealed, the ventilation system was redesigned, upgraded and replaced, the master-slave manipulators were replaced, the hot cell windows were removed, refurbished, and reinstalled, all hot cell utilities were replaced, a lead-shielded glovebox housing an Inductive Coupled Plasma - Atomic Emission Spectrometer (ICP-AES) System was interfaced with the hot cells, and a new CO2 fire suppression system and other ALHC support equipment were installed

  7. Thermo-mechanical parametric studies of Fixed Mask 1 and Photon Shutter 2 for APS front ends

    International Nuclear Information System (INIS)

    Fixed Mask 1 (FM1) and Photon Shutter 2 (PS2) are two of the critical elements on the front end of the beamlines at the Advanced Photon Source (APS) now under construction at Argonne National Laboratory (ANL). FMl and PS2 use an enhanced heat transfer tube developed at ANL. Due to a high localized thermal gradient on these components, inclined geometry is used in their design to spread the footprint of the x-ray beam. Complete closed form solutions for steady state conditions have been developed for the analyses of the thermal and thermo-mechanical behavior of FMl and PS2. A modified Manson-Coffin fatigue relation is proposed to predict the predict the thermal fatigue. The maximum temperatures and maximum effective stresses have been parametrically studied. Fatigue-failure life predictions are presented for the FM1 and PS2 designs

  8. Thermo-mechanical optimization of Fixed Mask 2 for APS front ends

    International Nuclear Information System (INIS)

    Fixed mask 2 (FM2) is one of the critical elements on the front end of the beamlines at the Advanced Photon Source (APS) now under construction at Argonne National Laboratory (ANL). The FM2 uses an enhanced heat transfer tube developed at ANL. Due to large thermal loads on these components, inclined geometry is used in the design to spread the footprint of the x-ray beam. Even then, thermal loads are very critical. To address the thermal and thermo-mechanical issues, analytical studies have been applied to a simplified model of the FM2 tube. The maximum temperature and maximum effective stress have been parametrically studied. Results for maximum temperatures and stresses are obtained and compared with the available strength/fatigue data for the materials proposed for the fixed mask design

  9. MUSE-4 experiment measurements and analysis

    International Nuclear Information System (INIS)

    This report presents a review of the activities performed by the five teams involved in the MUSE-4 experimental program. More details are provided on the contribution by ANL during the year 9/02 to 9/03. The ANL activity consisted both in direct participation in the experimental measurements and in the physics analysis of the experimental data, mainly for the reactivity level, adjoint flux and fission rate distributions and the analysis of dynamic measurements for reactivity determination techniques in subcritical systems. The results provided to complete the Benchmark organized by the OECD and the CEA on the experiment MUSE-4 are also presented. Deterministic calculations have been performed via the ERANOS code system in connection with JEF2.2, ENDF/B-V and ENDF/B-VI data files

  10. Analytical Chemistry Laboratory: Progress report for FY 1988

    Energy Technology Data Exchange (ETDEWEB)

    Green, D.W.; Heinrich, R.R.; Graczyk, D.G.; Lindahl, P.C.; Erickson, M.D.

    1988-12-01

    The purpose of this report is to summarize the activities of the Analytical Chemistry Laboratory (ACL) at Argonne National Laboratory (ANL) for fiscal year 1988 (October 1987 through September 1988). The Analytical Chemistry Laboratory is a full-cost recovery service center, with the primary mission of providing a broad range of analytical chemistry support services to the scientific and engineering programs at ANL. In addition, the ACL conducts a research program in analytical chemistry, works on instrumental and methods development, and provides analytical services for governmental, educational, and industrial organizations. The ACL handles a wide range of analytical problems, from routine standard analyses to unique problems that require significant development of methods and techniques.

  11. Rättvisande Värdering : En studie om värderingsmetoder inom IFRS mot verkstadsindustrin

    OpenAIRE

    Norén, Sven; Gustavsson, Daniel

    2013-01-01

    Den här studien är genomförd under våren 2013 av två studenter vid Handelshögskolan i Umeå.   Problem & Syfte Studien undersöker vilken värderingsmetod bolag inom verkstadsindustrin som redovisar enligt IFRS bör använda vid värdering av sina anläggningstillgångar, för att mot en investerare uppvisa den mest rättvisande bilden över sin ekonomiska ställning vid utfärdandet av ekonomiska rapporter. Studiens problem lyder redovisar bolag inom verkstadsindustrin värdet av anläggningstillgångar...

  12. Supplemental site inspection for Air Force Plant 59, Johnson City, New York, Volume 3: Appendices F-Q

    Energy Technology Data Exchange (ETDEWEB)

    Nashold, B.; Rosenblatt, D.; Hau, J. [and others

    1995-08-01

    This summary describes a Supplemental Site Inspection (SSI) conducted by Argonne National Laboratory (ANL) at Air Force Plant 59 (AFP 59) in Johnson City, New York. All required data pertaining to this project were entered by ANL into the Air Force-wide Installation Restoration Program Information System (IRPIMS) computer format and submitted to an appropriate authority. The work was sponsored by the United States Air Force as part of its Installation Restoration Program (IRP). Previous studies had revealed the presence of contaminants at the site and identified several potential contaminant sources. Argonne`s study was conducted to answer questions raised by earlier investigations. This volume consists of appendices F-Q, which contain the analytical data from the site characterization.

  13. Interim Status of the Accelerated Site Technology Deployment Integrated Decontamination and Decommissioning Project

    Energy Technology Data Exchange (ETDEWEB)

    A. M Smith; G. E. Matthern; R. H. Meservey

    1998-11-01

    The Idaho National Engineering and Environmental Laboratory (INEEL), Fernald Environmental Management Project (FEMP), and Argonne National Laboratory - East (ANL-E) teamed to establish the Accelerated Site Technology Deployment (ASTD) Integrated Decontamination and Decommissioning (ID&D) project to increase the use of improved technologies in D&D operations. The project is making the technologies more readily available, providing training, putting the technologies to use, and spreading information about improved performance. The improved technologies are expected to reduce cost, schedule, radiation exposure, or waste volume over currently used baseline methods. They include some of the most successful technologies proven in the large-scale demonstrations and in private industry. The selected technologies are the Pipe Explorer, the GammaCam, the Decontamination Decommissioning and Remediation Optimal Planning System (DDROPS), the BROKK Demolition Robot, the Personal Ice Cooling System (PICS), the Oxy-Gasoline Torch, the Track-Mounted Shear, and the Hand-Held Shear.

  14. Analytical Chemistry Laboratory progress report for FY 1984

    Energy Technology Data Exchange (ETDEWEB)

    Green, D.W.; Heinrich, R.R.; Jensen, K.J.; Stetter, J.R.

    1985-03-01

    Technical and administrative activities of the Analytical Chemistry Laboratory (ACL) are reported for fiscal year 1984. The ACL is a full-cost-recovery service center, with the primary mission of providing a broad range of technical support services to the scientific and engineering programs at ANL. In addition, ACL conducts a research program in analytical chemistry, works on instrumental and methods development, and provides analytical services for governmental, educational, and industrial organizations. The ACL is administratively within the Chemical Technology Division, the principal user, but provides technical support for all of the technical divisions and programs at ANL. The ACL has three technical groups - Chemical Analysis, Instrumental Analysis, and Organic Analysis. Under technical activities 26 projects are briefly described. Under professional activities, a list is presented for publications and reports, oral presentations, awards and meetings attended. 6 figs., 2 tabs.

  15. Hedgemöjligheter och riskmätning : för Lantmännen Agroetanol

    OpenAIRE

    Nilsson, Joakim; Söderberg, Viktor

    2007-01-01

    Examensarbetet studerar möjligheterna att använda en statisk cross hedge för att prissäkra etanol. Situationen som analyseras är hämtad från Lantmännen Agroetanol. Agroetanol är Sveriges största producent av etanol och driver den första anläggning i Sverige där vete omvandlas till etanol. Anläggningen är Sveriges största och byggs för närvarande ut så att kapaciteten kommer under år 2008 kommer att öka med 300 procent. Priset på spannmål har stigit dramatiskt under år 2007 samtidigt som etano...

  16. Solid-State 2MW Klystron Power Control System

    CERN Document Server

    Kempkes, Michael; Gaudreau, Marcel; Hawkey, Timothy; Roth, Ian

    2005-01-01

    Under an SBIR effort for the DOE, Diversified Technologies, Inc. designed, built, and installed a solid state power control system for the Advanced Light Source klystrons at Argonne National Laboratory (ANL). This system consists of two major elements - a 100 kV, 20 A CW solid state series switch, and a solid state voltage regulator for the mod-anode of the klystron. The series switch replaces the existing mercury ignitron crowbar, eliminating these environmentally hazardous components while providing enhanced arc protection and faster return to transmit. The mod-anode voltage regulator uses series IGBTs, operating in the linear regime, to provide highly rapid and accurate control of the mod-anode voltage, and therefore the output power from the klystron. Results from the installation and testing of this system at ANL will be presented.

  17. Final Report: Experimental Investigation of Nonlinear Plasma Wake-Fields

    Energy Technology Data Exchange (ETDEWEB)

    Rosenzweig, J.

    1997-10-31

    We discuss the exploration of the newly proposed blowout regime of the plasma wakefield accelerator and advanced photoinjector technology for linear collider applications. The plasma wakefield experiment at ANL produced several ground-breaking results in the physics of the blowout regime. The photoinjector R and D effort produced breakthroughs in theoretical, computational, and experimental methods in high brightness beam physics. Results have been published.

  18. Edb-program optimerer nettilslutning af motorstyring

    DEFF Research Database (Denmark)

    Hansen, Steffan; Asiminoaei, Lucian; Blaabjerg, Frede

    2004-01-01

    er der også et forøget behov for at beregne konsekvenserne på nettet i form af harmoniske strømme og spændinger. Danfoss har i mange år haft muligheden for at tilbyde beregninger til kunderne og deres anlæg, men efterhånden var behovet for nøjagtige og kundetilpassede beregninger evt. i form af...

  19. Comenius' Philosophie der Gewaltlosigkeit in ganzheitlicher Perspektive

    Czech Academy of Sciences Publication Activity Database

    Schifferová, Věra

    Frankfurt a.M: Peter Lang, 2005, s. 401-418. (Schriften zur Triadik und Ontodynamik. 24). ISBN 3-631-5251-5. ISSN 0932-2434. [Deutsch-tschechisches Kolloquium anlässlich des 75. Geburtstages von Heinrich Beck. Bamberg (DE), 13.04.2004-16.04.2004] R&D Projects: GA ČR GA401/03/0863 Institutional research plan: CEZ:AV0Z9009908 Keywords : Comenius * philosophy * Irenism Subject RIV: AA - Philosophy ; Religion

  20. Engineering and Physics Optimization of Breed and Burn Fast Reactor Systems; NUCLEAR ENERGY RESEARCH INITIATIVE (NERI) QUARTERLY PROGRESS REPORT

    Energy Technology Data Exchange (ETDEWEB)

    ERROR, [value too long for type character varying(50); Hejzlar, Pavel; Yarsky, Peter; Driscoll, Mike; Wachs, Dan; Weaver, Kevan; Czerwinski, Ken; Pope, Mike; Parry, James; Marshall, Theron D.; Davis, Cliff B.; Crawford, Dustin; Hartmann, Thomas; Saha, Pradip

    2005-01-31

    This project is organized under four major tasks (each of which has two or more subtasks) with contributions among the three collaborating organizations (MIT, INEEL and ANL-West): Task A: Core Physics and Fuel Cycle; Task B: Core Thermal Hydraulics; Task C: Plant Design; Task D: Fuel Design The lead PI, Michael J. Driscoll, has consolidated and summarized the technical progress submissions provided by the contributing investigators from all sites, under the above principal task headings.

  1. Minutes of the 2. Meeting of the WPRS / EGRPANS / Sodium Fast Reactor Task Force (SFR)

    International Nuclear Information System (INIS)

    Five organizations (SCK/CEN, KIT, KFKI, CEA, ANL) participated in the Sodium-cooled fast reactor (SFR) Benchmark calculations and all results were collected and compiled by CEA and ANL. The compiled results of the large size cores and medium size cores were presented by V. Pascal (CEA) and T. K. Kim (ANL), respectively. Separately, A. Kereszturi presented his recently updated results. It was observed that there is wide variation in core multiplication factor, kinetics parameters, and reactivity feedback coefficients. In particular, compared to the CEA results, ANL calculated smaller k-eff, Doppler constant, but higher sodium void worth and control rod worth. The core modeling issue (heterogeneous vs. homogeneous) and solution method (diffusion vs. transport) were identified as the potential reasons of these discrepancies, including the minor impacts from the depletion chains and lumped fission product modeling. All participants agreed that additional investigation was needed to identify the reasons of these discrepancies. In addition, V. Pascal presented the informative notes of the reactivity feedback calculations methodology proposed by CEA. This document brings together the 5 presentations (slides) given at this meeting: 1 - SFR Task Force : Core behavior during transient as a function of power size and fuel nature (L. Buiron, V. Pascal, F. Varaine); 2 - Sodium Fast Reactor core Feedback and Transient response (SFRFT) Expert Group: preliminary benchmark results for large cores (L. Buiron, V. Pascal, F. Varaine); 3 - Numerical Benchmark Results for 1000 MWth Sodium-cooled Fast Reactor (T.K. Kim and T.A. Taiwo); 4 - Preliminary results of the WPRS Sodium-Cooled Fast Reactor Benchmark problems (A. Kereszturi, I. Pataki, A. Tota, P. Vertes); 5 - SFR Task Force : proposal for Feedback coefficients estimation methodology (L. Buiron, V.Pascal, F. Varaine)

  2. Argonne National Laboratory - West's approach to filter characterization

    International Nuclear Information System (INIS)

    Like other DOE facilities, ANL-W uses a variety of nuclear grade, industrial grade, or furnace-type particulate filters to control airborne radioactivity and hazardous contaminants in radiological containment structures or processes. As designed, these filters entrain and ultimately concentrate contaminants in the media. Toxic metal contaminants include cadmium, chromium, lead; and mercury present in sufficient concentrations to exhibit the hazardous waste characteristic of toxicity as defined in 40 CFR 261.24. Radionuclide contaminants deposited in the media may at times accumulate in sufficient quantity to classify the filter as transuranic or remote-handled waste. Upon their removal from the ventilation system, these particulate filters become wastes, which must be characterized to determine their hazardous and radioactive classifications. A well defined filter characterization process is essential for the proper/consistent waste characterization and minimization and for maintaining personnel radiological exposures as-low-as-reasonably-achievable (ALARA) (1,2). ANL-W has developed an approach to filter sampling and characterization to meet these needs. The ANL-W filter sampling and characterization process is designed to ensure representative sampling and/or process knowledge is utilized in characterizing the filters. The data obtained through sampling and/or process knowledge is used to show compliance with the Resource Conservation and Recovery Act (3) and Treatment/Storage/Disposal Facility Waste Acceptance Criteria. The ANL-W filter characterization involves the collection of process information, filter handling and sampling, sample analysis, data management filter characterization, and waste handling. Each element of the process is streamlined to ensure proper characterization while minimizing radiological exposure to maintenance workers, samplers, laboratory personnel, and waste handlers

  3. Arbejdsmiljø i idé-, program- og projektfaserne

    DEFF Research Database (Denmark)

    Schultz, Casper Siebken; Jørgensen, Kirsten

    Denne rapport præsenterer et koncept til integrering af arbejdsmiljøhensyn i projektering af et bygge- eller anlægsprojekt. Konceptet er målrettet bygherrer og rådgivere, herunder både arkitekter og ingeniører med flere. Konceptet er resultatet af et udviklingsprojekt med titlen ”Kvalitet og Ar-b...

  4. The PLTEMP V2.1 code

    International Nuclear Information System (INIS)

    Recent improvements to the computer code PLTEMP/ANL V2.1 are described. A new iterative, error-minimization solution technique is used to obtain the thermal distribution both within each fuel plate, and along the axial length of each coolant channel. A new, radial geometry solution is available for tube-type fuel assemblies. Software comparisons of these and other new models are described. Applications to Russian-designed IRT-type research reactors are described. (author)

  5. Tillæg til rapport om Havvindmøller i Nissum Bredning

    DEFF Research Database (Denmark)

    Bentzen, Thomas Ruby; Larsen, Torben

    Nærværende rapport er udført for NOE, A.m.b.a. og Nissum Bredning Vindmølle Laug af Aalborg Universitet, Institut for Byggeri og Anlæg i henhold til konsulentaftale af 30.11.2011, som tillæg til tidligere rapport jf. konsulentaftale af 6.7.2010. /1/. Dette tillæg omfatter kun den såkaldte dæmning...

  6. Remedial investigation report for J-Field, Aberdeen Proving Ground, Maryland. Volume 3: Ecological risk assessment

    Energy Technology Data Exchange (ETDEWEB)

    Hlohowskyj, I.; Hayse, J.; Kuperman, R.; Van Lonkhuyzen, R.

    2000-02-25

    The Environmental Management Division of the U.S. Army Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation (RI) and feasibility study (FS) of the J-Field area at APG, pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. As part of that activity, Argonne National Laboratory (ANL) conducted an ecological risk assessment (ERA) of the J-Field site. This report presents the results of that assessment.

  7. Engineering and Physics Optimization of Breed and Burn Fast Reactor Systems. NUCLEAR ENERGY RESEARCH INITIATIVE (NERI) QUARTERLY PROGRESS REPORT

    International Nuclear Information System (INIS)

    This project is organized under four major tasks (each of which has two or more subtasks) with contributions among the three collaborating organizations (MIT, INEEL and ANL-West): Task A: Core Physics and Fuel Cycle; Task B: Core Thermal Hydraulics; Task C: Plant Design; Task D: Fuel Design The lead PI, Michael J. Driscoll, has consolidated and summarized the technical progress submissions provided by the contributing investigators from all sites, under the above principal task headings

  8. Das bovine Ovarialzystensyndrom : Versuch einer in vivo Klassifizierung in Verbindung mit einer Langzeitstudie zur Überprüfung verschiedener Diagnostik- und Therapiemethoden

    OpenAIRE

    Schedel, Klaus

    2002-01-01

    Für die vorliegende Feldstudie standen 337 Kühe mit Ovarialzystensyndrom aus 78 Betrieben zur Verfügung. Bei allen Probanden wurde neben den klassischen klinischen Parametern anläßlich der Erstvorstellung der periphere Progesterongehalt in Vollmilch semiquantitativ durch EIA gemessen und retrospektiv in der Magermilch durch EIA quantifiziert. Bei 61 Probanden wurden zudem die Zysten per vaginam punktiert und in der aspirierten Zystenflüssigkeit (ZF) Progesteron (P4), Östradiol-17ß (E...

  9. Environmental assessment related to the operation of Argonne National Laboratory, Argonne, Illinois

    Energy Technology Data Exchange (ETDEWEB)

    1982-08-01

    In order to evaluate the environmental impacts of Argonne National Laboratory (ANL) operations, this assessment includes a descriptive section which is intended to provide sufficient detail to allow the various impacts to be viewed in proper perspective. In particular, details are provided on site characteristics, current programs, characterization of the existing site environment, and in-place environmental monitoring programs. In addition, specific facilities and operations that could conceivably impact the environment are described at length. 77 refs., 16 figs., 47 tabs.

  10. Social Media

    OpenAIRE

    Weller, Katrin; Meckel, Martin Sebastian; Stahl, Matthias

    2013-01-01

    Anlässlich der 10. Wissenschaftlichen Tagung „Soziale Medien“ am 27. und 28. Juni 2013 im Statistischen Bundesamt in Wiesbaden und in Fortsetzung des 2010 erschienenen Recherche Spezial Web 2.0 – Alle machen mit! werden in dieser Ausgabe in sechs Kapiteln Nachweise zu Veröffentlichungen und Forschungsprojekte der letzten drei Jahre zusammengestellt, die sich mit der Rolle von Social Media in verschiedenen Nutzungskontexten befassen. Social-Media-Dienste sind mittlerweile fester Bestandtei...

  11. SLSF loop handling system. Volume I. Structural analysis

    International Nuclear Information System (INIS)

    SLSF loop handling system was analyzed for deadweight and postulated dynamic loading conditions, identified in Chapters II and III in Volume I of this report, using a linear elastic static equivalent method of stress analysis. Stress analysis of the loop handling machine is presented in Volume I of this report. Chapter VII in Volume I of this report is a contribution by EG and G Co., who performed the work under ANL supervision

  12. PC-DYMAC: Personal Computer---DYnamic Materials ACcounting

    International Nuclear Information System (INIS)

    This manual was designed to provide complete documentation for the computer system used by the EBR-II Fuels and Materials Department, Argonne National Laboratory-West (ANL-W) for accountability of special nuclear materials (SNM). This document includes background information on the operation of the Fuel Manufacturing Facility (FMF), instructions on computer operations in correlation with production and a detailed manual for DYMAC operation. 60 figs

  13. Report of the workshop on electronic and ionic collision cross sections needed in the modeling of radiation interactions with matter

    International Nuclear Information System (INIS)

    The workshop was held on 6-8 December 1983 at Argonne National Laboratory. It was attended by more than 40 scientists from outside the Laboratory and by about 10 members of the Laboratory staff. A full record of the Workshop is available as a topical report entitled ''Proceedings of the Workshop on Electronic and Ionic Collision Cross Sections Needed in the Modeling of Radiation Interactions with Matter,'' ANL-84-28, issued in May 1984

  14. Final report for the Light Water Breeder Reactor proof-of-breeding analytical support project

    Energy Technology Data Exchange (ETDEWEB)

    Graczyk, D.G.; Hoh, J.C.; Martino, F.J.; Nelson, R.E.; Osudar, J.; Levitz, N.M.

    1987-05-01

    The technology of breeding /sup 233/U from /sup 232/Th in a light water reactor is being developed and evaluated by the Westinghouse Bettis Atomic Power Laboratory (BAPL) through operation and examination of the Shippingport Light Water Breeder Reactor (LWBR). Bettis is determining the end-of-life (EOL) inventory of fissile uranium in the LWBR core by nondestructive assay of a statistical sample comprising approximately 500 EOL fuel rods. This determination is being made with an irradiated-fuel assay gauge based on neutron interrogation and detection of delayed neutrons from each rod. The EOL fissile inventory will be compared with the beginning-of-life fissile loading of the LWBR to determine the extent of breeding. In support of the BAPL proof-of-breeding (POB) effort, Argonne National Laboratory (ANL) carried out destructive physical, chemical, and radiometric analyses on 17 EOL LWBR fuel rods that were previously assayed with the nondestructive gauge. The ANL work included measurements on the intact rods; shearing of the rods into pre-designated contiguous segments; separate dissolution of each of the more than 150 segments; and analysis of the dissolver solutions to determine each segment's uranium content, uranium isotopic composition, and loading of selected fission products. This report describes the facilities in which this work was carried out, details operations involved in processing each rod, and presents a comprehensive discussion of uncertainties associated with each result of the ANL measurements. Most operations were carried out remotely in shielded cells. Automated equipment and procedures, controlled by a computer system, provided error-free data acquisition and processing, as well as full replication of operations with each rod. Despite difficulties that arose during processing of a few rod segments, the ANL destructive-assay results satisfied the demanding needs of the parent LWBR-POB program.

  15. Vejstrækningers geometri

    DEFF Research Database (Denmark)

    Bolet, Lars

    Undervisningsnoten er skrevet til grundkurset i Vej- og Trafikteknik på Aalborg Universitets ingeniøruddannelser i byggeri og anlæg. Den behandler kræfter og kørselsdynamik ved kørsel på veje, altså nogle af de grundlæggende, fysiske vilkår, der skal tages i ed ved design af veje og stier....

  16. Virksomhedens bæredygtighed

    DEFF Research Database (Denmark)

    Linneberg, Mai Skjøtt; Thomsen, Christa

    2011-01-01

    herpå er ISO 26000, der er det hidtil mest vidtrækkende eksempel på standardisering af bæredygtighed. Standarden er udviklet i 2010, og Dansk Standard udgav i december 2010 en dansk uddybning, som de lægger op til vil være certificerbar (ISO, 2010). I artiklen anlægger vi et paradoksperspektiv, som...

  17. Synthese und Testung von COX-1-, COX-2- und 5-LOX-Inhibitoren zur topischen Anwendung

    OpenAIRE

    Koppermann, Annika

    2010-01-01

    Das Ziel der Dissertation war die Synthese und pharmakologische Charakterisierung von COX-1-, COX-2- und 5-LOX-Inhibitoren, die zur Behandlung entzündlicher Dermatosen für die topische Anwendung geeignet sein sollten. Hierfür wurden zwei Strukturklassen - die sogenannten Imidazothiazole und die Chalcone-Derivate - entworfen und synthetisiert sowie in verschiedenen in vitro-Testsystemen auf ihre pharmakologische Wirksamkeit untersucht. rnDie Leitsubstanz der ersten Strukturklasse wurde in Anle...

  18. Visuelle Intuition in dynamischen Strukturen

    OpenAIRE

    Thaliath, Babu

    2003-01-01

    In der vorliegenden Abhandlung wird der Versuch unternommen, den Modus epistemologischer Deduktion in der Wissenschaft der Mechanik, insbesondere der Dynamik, als eine visuelle Intuition zu bestimmen. Diese Untersuchung stützt sich auf eine Grundvorstellung von struktureller Intuition, die Martin Kemp in seinem Vortrag „Structural Intuitions in Art and Science“ (gehalten am 16. Dezember 2002 anläßlich einer Vorlesungsreihe mit dem Rahmenthema „Iconic Turn“ bei der Hubert-Burda-Stiftung in Mün...

  19. Technical basis in support of the conversion of the University of Missouri Research Reactor (MURR) core from highly-enriched to low-enriched uranium - core neutron physics

    Energy Technology Data Exchange (ETDEWEB)

    Stillman, J. [Argonne National Lab. (ANL), Argonne, IL (United States); Feldman, E. [Univ. of Missouri, Columbia, MO (United States). Columbia Research Reactor; Foyto, L [Univ. of Missouri, Columbia, MO (United States). Columbia Research Reactor; Kutikkad, K [Univ. of Missouri, Columbia, MO (United States). Columbia Research Reactor; McKibben, J C [Univ. of Missouri, Columbia, MO (United States). Columbia Research Reactor; Peters, N. [Univ. of Missouri, Columbia, MO (United States). Columbia Research Reactor; Stevens, J. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2012-09-01

    This report contains the results of reactor design and performance for conversion of the University of Missouri Research Reactor (MURR) from the use of highly-enriched uranium (HEU) fuel to the use of low-enriched uranium (LEU) fuel. The analyses were performed by staff members of the Global Threat Reduction Initiative (GTRI) Reactor Conversion Program at the Argonne National Laboratory (ANL) and the MURR Facility. The core conversion to LEU is being performed with financial support of the U. S. government.

  20. Electron-cloud measurements and simulations for the APS

    International Nuclear Information System (INIS)

    We compare experimental results with simulations of the electron cloud effect induced by a positron beam at the APS synchrotron light source at ANL, where the electron cloud effect has been observed and measured with dedicated probes. We find good agreement between simulations and measurements for reasonable values of certain secondary electron yield (SEY) parameters, most of which were extracted from recent bench measurements at SLAC

  1. Fusion reactor safety studies, FY 1977

    International Nuclear Information System (INIS)

    This report reviews the technical progress in the fusion reactor safety studies performed during FY 1977 in the Fusion Power Program at the Argonne National Laboratory. The subjects reported on include safety considerations of the vacuum vessel and first-wall design for the ANL/EPR, the thermal responses of a tokamak reactor first wall, the vacuum wall electrical resistive requirements in relationship to magnet safety, and a major effort is reported on considerations and experiments on air detritiation

  2. Komenskýs Verhältnis zu den christlichen Konfessionen seiner Zeit

    Czech Academy of Sciences Publication Activity Database

    Steiner, Martin

    Frankfurt a.M : Peter Lang, 2005, s. 219-236. ISBN 3-631-5251-5. ISSN 0932-2434. - (Schriften zur Triadik und Ontodynamik. 24). [Deutsch-tschechisches Kolloquium anlässlich des 75. Geburtstages von Heinrich Beck. Bamberg (DE), 13.04.2004-16.04.2004] Institutional research plan: CEZ:AV0Z9009908 Keywords : J.A. Comenius and the Christianity * J.A. Comenius and the Czech Reformation Subject RIV: AA - Philosophy ; Religion

  3. Dynamisches Objektverhalten in Virtuellen Umgebungen

    OpenAIRE

    Fröhlich, Torsten

    2002-01-01

    Virtuelle Welten waren in den vergangenen Jahren wegen der hohen Kosten Forschungslaboren vorbehalten und der Öffentlichkeit anlässlich zeitlich begrenzter Ausstellungen und Messen zugänglich. Mit der dramatischen Leistungssteigerung der Personal Computer in den letzten Jahren rückt nun die Anwendung von Virtueller Realität im öffentlichen Raum, etwa in Museen, Freizeitparks in den Bereich des Möglichen. Damit das vielversprechende didaktische Potential dieses neuen Mediums genutzt werden kan...

  4. Erinnerung im Streit. Zum Umgang der deutschen Geschichtswissenschaft mit ihrer eigenen Vergangenheit

    OpenAIRE

    Hasselhorn, Benjamin

    2014-01-01

    Die Beziehungen deutscher Historiker zum nationalsozialistischen Regime sowie das Verhältnis der deutschen Geschichtswissenschaft der ersten Hälfte des 20. Jahrhunderts zum Nationalsozialismus insgesamt sind nach wie vor äußerst kontrovers diskutierte Streitthemen in der Disziplin und immer mal wieder auch im Historikerverband. Zum Ausdruck kam dies jüngst wieder anlässlich der von Christoph Nonn verfassten Biographie des Kölner Historikers Theodor Schieder (1908-1984), einer der bedeutendste...

  5. Remedial investigation report for J-Field, Aberdeen Proving Ground, Maryland. Volume 3: Ecological risk assessment

    International Nuclear Information System (INIS)

    The Environmental Management Division of the U.S. Army Aberdeen Proving Ground (APG), Maryland, is conducting a remedial investigation (RI) and feasibility study (FS) of the J-Field area at APG, pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. As part of that activity, Argonne National Laboratory (ANL) conducted an ecological risk assessment (ERA) of the J-Field site. This report presents the results of that assessment

  6. Energioptimering VAV eller CAV?

    DEFF Research Database (Denmark)

    Kærn, Martin Ryhl; Barky, Tarek; Andersen, Dan Bomholt

    2008-01-01

    Når et HVAC-anlæg projekteres, vælges der oftest mellem fortrængnings- og opblandingsventilation. Herefter vælges hvorvidt luftfl owet skal være variabelt eller konstant – det vil sige, om der skal vælges. VAV eller CAV. Dette valg mellem VAV eller CAV bør foretages på baggrund af en vurdering af...

  7. Final report for the Light Water Breeder Reactor proof-of-breeding analytical support project

    International Nuclear Information System (INIS)

    The technology of breeding 233U from 232Th in a light water reactor is being developed and evaluated by the Westinghouse Bettis Atomic Power Laboratory (BAPL) through operation and examination of the Shippingport Light Water Breeder Reactor (LWBR). Bettis is determining the end-of-life (EOL) inventory of fissile uranium in the LWBR core by nondestructive assay of a statistical sample comprising approximately 500 EOL fuel rods. This determination is being made with an irradiated-fuel assay gauge based on neutron interrogation and detection of delayed neutrons from each rod. The EOL fissile inventory will be compared with the beginning-of-life fissile loading of the LWBR to determine the extent of breeding. In support of the BAPL proof-of-breeding (POB) effort, Argonne National Laboratory (ANL) carried out destructive physical, chemical, and radiometric analyses on 17 EOL LWBR fuel rods that were previously assayed with the nondestructive gauge. The ANL work included measurements on the intact rods; shearing of the rods into pre-designated contiguous segments; separate dissolution of each of the more than 150 segments; and analysis of the dissolver solutions to determine each segment's uranium content, uranium isotopic composition, and loading of selected fission products. This report describes the facilities in which this work was carried out, details operations involved in processing each rod, and presents a comprehensive discussion of uncertainties associated with each result of the ANL measurements. Most operations were carried out remotely in shielded cells. Automated equipment and procedures, controlled by a computer system, provided error-free data acquisition and processing, as well as full replication of operations with each rod. Despite difficulties that arose during processing of a few rod segments, the ANL destructive-assay results satisfied the demanding needs of the parent LWBR-POB program

  8. Real-time monitoring and control of the plasma hearth process

    International Nuclear Information System (INIS)

    A distributed monitoring and control system is proposed for a plasma hearth, which will be used to decompose hazardous organic materials, encapsulate actinide waste in an obsidian-like slag, and reduce storage volume of actinide waste. The plasma hearth will be installed at ANL-West with the assistance of SAIC. Real-time monitoring of the off-gas system is accomplished using a Sun Workstation and embedded PCs. LabWindows/CVI software serves as the graphical user interface

  9. Utilization of arylaliphatic nitriles by haloalkaliphilic Halomonas nitrilicus sp. nov. isolated from soda soils

    OpenAIRE

    Chmura, A.; Shapovalova, A. A.; van Pelt, S.; Van Rantwijk, F.; Tourova, T.P.; Muyzer, G; Sorokin, D. Y.

    2008-01-01

    An enrichment culture from saline soda soils, using acetate as carbon and energy source and 2- phenylpropionitrile as nitrogen source (PPN) at pH 10, resulted in the isolation of strain ANL-αCH3. The strain was identified as a representative of the genus Halomonas in the Gammaproteobacteria. The bacterium was capable of PPN utilization as a nitrogen source only, while phenylacetonitrile (PAN) served both as carbon, energy and nitrogen source. This capacity was not described previously for any...

  10. Presse-briefing

    DEFF Research Database (Denmark)

    Brown, Rikke; Vestergaard, Arnt Louw

      Dette notat præsenterer de første resultater fra en landsdækkende spørgeskemaundersøgelse blandt elever på fire forskellige af erhvervsuddannelsernes grundforløb: Bygge og anlæg, Mad til mennesker, Medieproduktion og det merkantile grundforløb (HG). Over 7.000 elever har besvaret spørgeskemaet,...

  11. The relationship between primary and middle school principals’ change leadership behaviors and teachers’ organizational commitment

    İlkokul ve ortaokul müdürlerinin değişim liderliği davranışları ile öğretmenlerin örgütsel bağlılıkları arasındaki ilişki

    OpenAIRE

    Demet Çetin Çağrıcı; Ahmet Cezmi Savaş

    2016-01-01

    The purpose of the current study is to determine whether primary and middle school teachers’ perceptions of school principals’ change leadership behaviors are correlated with their organizational commitment. The sample of the study was comprised of 252 teachers working at 56 primary and middle schools in Birecik district of Şanlıurfa province. To collect data, “Change Leadership Scale” and “Organizational Commitment Scale” were used. Research data were analyzed using means, standard deviation...

  12. Evaluation of advanced and current leak detection systems

    International Nuclear Information System (INIS)

    Differences between PWRs and BWRs with regard to leak detection have now been analyzed. With regard to detection methods, the greatest differences between reactor types are as follows: (a) the sump pump is reported as the detection method more frequently in BWRs than in PWRs (64% vs. 35%); (b) the radiation monitor is reported as the detection method (excluding false alarms) more frequently in PWRs. Current efforts at Argonne National Laboratory (ANL) to evaluate advanced acoustic leak detection methods are directed toward the generation and analysis of acoustic data from large (0.5 to 10 gal/min) leaks and modification of the software of the GARD/ANL advanced acoustic leak detection system. In order to reach the goal of 10 gal/min leaks, the Steam Generator Test Facility at ANL has been modified to carry out the leak testing. Tests were carried out with water at 5250F and 1100 psi leaking through a fatigue crack in a 4-in. schedule 80 pipe. The crack opening can be varied and was set to generate 0.6- to 8.5-gal/min leaks. Acoustic signals were analyzed with respect to rms values, frequency content, and cross-correlation functions. The GARD/ANL advanced acoustic leak detection system software has been modified to permit intelligent continuous acoustic leak monitoring of reactor components. In the monitor mode the computer continually evaluates the rms signal output of acoustic leak detection sensors placed on the primary circuit. If a leak is suspected, acoustic signals are captured and analyzed to determine the source of the leak, the location and estimated leak rate

  13. Tagungsbericht: Wie viel Kultur verträgt die Psychologie? "100 Jahre Deutsche Gesellschaft für Psychologie"

    OpenAIRE

    Allolio-Näcke, Lars

    2005-01-01

    Anlässlich des 44. Kon­gres­ses der Deutschen Gesellschaft für Psychologie in Göttingen traten erstmals vermehrt und sichtbar Kulturpsychologen auf, die über die Thematik des Kulturvergleichs durch die internationalen Vergleichsstudien zu Schulleistungen (TIMS, IGLU, PISA) die Gegenstandsunangemessenheit der variablenorientierten Individualpsychologie sowie deren Methodologien und Methoden thematisierten. Zentrale Themen waren hierbei vor allem, die Äqui­valenzproblematik (tertium comparation...

  14. Technical Assessment of Organic Liquid Carrier Hydrogen Storage Systems for Automotive Applications

    Energy Technology Data Exchange (ETDEWEB)

    Ahluwalia, R. K. [Argonne National Lab. (ANL), Argonne, IL (United States); Hua, T. Q. [Argonne National Lab. (ANL), Argonne, IL (United States); Peng, J. -K [Argonne National Lab. (ANL), Argonne, IL (United States); Kromer, M. [TIAX LLC, Lexington, MA (United States); Lasher, S. [TIAX LLC, Lexington, MA (United States); McKenney, K. [TIAX LLC, Lexington, MA (United States); Law, K. [TIAX LLC, Lexington, MA (United States); Sinha, J. [TIAX LLC, Lexington, MA (United States)

    2011-06-21

    In 2007-2009, the DOE Hydrogen Program conducted a technical assessment of organic liquid carrier based hydrogen storage systems for automotive applications, consistent with the Program’s Multiyear Research, Development, and Demonstration Plan. This joint performance (ANL) and cost analysis (TIAX) report summarizes the results of this assessment. These results should be considered only in conjunction with the assumptions used in selecting, evaluating, and costing the systems discussed here and in the Appendices.

  15. Precision tomographic analysis of reactor fuels

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Yong Deok; Lee, Chang Hee; Kim, Jong Soo; Jeong, Jwong Hwan; Nam, Ki Yong

    2001-03-01

    For the tomographical assay, search of current status, analysis of neutron beam characteristics, MCNP code simulation, sim-fuel fabrication, neutron experiment for sim-fuel, multiaxes operation system design were done. In sensitivity simulation, the reconstruction results showed the good agreement. Also, the scoping test at ANL was very helpful for actual assay. Therefore, the results are applied for HANARO tomographical system setup and consecutive next research.

  16. China - Nicht alles Gold, was glänzt!

    OpenAIRE

    Kolle, Christian

    2008-01-01

    Anlässlich der XXIX. olympischen Sommerspiele in Peking beschäftigt sich die August-Ausgabe der Recherche Spezial mit den zahlreichen sozialwissenschaftlichen Aspekten und Facetten, die der bevölkerungsreichste Staat der Erde zu bieten hat. Der rasante Aufstieg zur Wirtschaftsmacht innerhalb von nur drei Jahrzehnten hat dem chinesischen Staat zwar internationale Anerkennung gepaart mit ängstlicher Ehrfurcht beschert, ist aber gleichzeitig auch Ursprung einer Reihe von sozialen Problemen i...

  17. Accelerating Structure design and fabrication For KIPT and PAL XFEL

    CERN Document Server

    Hou, Mi; Pei, Shilun

    2014-01-01

    ANL and the National Science Center "Kharkov Institute of Physics Technology" (NSC KIPT, Kharkov, Ukraine) jointly proposed to design and build a 100MeV/100KW linear accelerator which will be used to drive the neutron source subcritical assembly. Now the linac was almost assembled in KIPT by the team from Institute of High Energy Physics (IHEP, Beijing, China). The design and measurement result of the accelerating system of the linac will be described in this paper.

  18. Electron-cloud measurements and simulations for the APS

    OpenAIRE

    Furman, M.A.; Pivi, M.; Harkay, K.C.; Rosenberg, R. A.

    2001-01-01

    We compare experimental results with simulations of the electron cloud effect induced by a positron beam at the APS synchrotron light source at ANL, where the electron cloud effect has been observed and measured with dedicated probes. We find good agreement between simulations and measurements for reasonable values of certain secondary electron yield (SEY) parameters, most of which were extracted from recent bench measurements at SLAC.

  19. De eksterne omkostninger ved energiproduktion

    DEFF Research Database (Denmark)

    Andersen, M. S.; Frohn, L. M.

    2007-01-01

    I et forskningsprojekt som blev afsluttet i 2006 har DMU med ExternE-metoden forsøgt at beregne de eksterne omkostninger for tre danske energianlæg. Det er sket ud fra de informationer om værkernes udledninger som er offentligt tilgængelige. De tre anlæg er Amagerværket, Fynsværket samt Vestforbr...

  20. Wie ewig sind die Denkmalschutzbehörden?

    OpenAIRE

    Streitgespräch,

    2004-01-01

    Streitgespräch anlässlich des Symposiums �Nachdenken über Denkmalpflege� (Teil 3): �Wie ewig sind die Denkmale? Von der Zeitgenossenschaft der Denkmale und der Denkmalpfleger�, Magdeburg, 8. November 2003 Ralph Paschke, Brandenburgisches Landesamt für Denkmalpflege und Archäologisches Landesmuseum, Matthias Donath, Berlin, Moderation: Biagia Bongiorno, Technische Universität Berlin �Wie ewig sind die Denkmalfachbehörden?� war die Ausgangsfrage d...

  1. Anestezi uzmanlarında tükenmişliğin iş tatmini ve intihar düşüncesi ile ilişkisi

    OpenAIRE

    Özkan, Süreyya; Karaman, Emine Uzlaş; Öztürk, Nalan; Ahun, Filiz Akın; Selmi, Nazan Has

    2015-01-01

    Objective: In this research, it was aimed to determine the relationship between the level of burnout of anesthesiologists with job satisfaction and suicide ideation.Methods: 109 anesthesiologists working in education and research, university, private and public hospitals in Istanbul, Ankara, Bursa, Izmir, Kütahya, Denizli, Antalya, Samsun, Bolu, Rize, Erzurum, Amasya, Gaziantep, Şanlıurfa, Ağri, Iğdir, Mus were included in the study. Sociodemographic data form, Minnesota Job Satisfaction Scal...

  2. Feasibility study of the university of Utah TRIGA reactor power upgrade - part II: Thermohydraulics and heat transfer study in respect to cooling system requirements and design

    OpenAIRE

    Babitz Philip; Choe Dongok; Jevremovic Tatjana

    2013-01-01

    The thermodynamic conditions of the University of Utah's TRIGA Reactor were simulated using SolidWorks Flow Simulation, Ansys, Fluent and PARET-ANL. The models are developed for the reactor's currently maximum operating power of 90 kW, and a few higher power levels to analyze thermohydraulics and heat transfer aspects in determining a design basis for higher power including the cost estimate. It was found that the natural convection current becomes much mor...

  3. Carl von Ossietzky

    OpenAIRE

    Suhr, Elke; Ossietzky-Palm, Rosalinda von

    1988-01-01

    Ausstellung und Katalog wurden von Mitarbeitern der Universität Oldenburg anläßlich des 50. Todestages Carl von Ossietzkys erarbeitet. Diese dritte Ossietzky-Ausstellung in Oldenburg steht unter dem Thema "Republikaner ohne Republik". Der Katalog gibt zahlreiche Schautafeln der Ausstellung wieder und enthält ferner kürzere Textbeiträge verschiedener Autoren, darunter auch Erinnerungen von Zeitgenossen Carl von Ossietzkys.

  4. Target Window Reliability

    Energy Technology Data Exchange (ETDEWEB)

    Woloshun, Keith Albert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-02-11

    The target window design implemented and tested in experiments at ANL have performed without failure for the available beam of 6 mm FWHM on a 12 mm diameter target. However, scaling that design to a 25 mm diameter target size for a 12 mm FWHM beam has proven problematic. Combined thermal and mechanical (pressure induced) stresses and strains are too high to maintain the small coolant gaps and provide adequate fatigue lifetime.

  5. The Sodium Process Facility at Argonne National Laboratory-West

    International Nuclear Information System (INIS)

    Argonne National Laboratory-West (ANL-W) has approximately 680,000 liters of raw sodium stored in facilities on site. As mandated by the State of Idaho and the US Department of Energy (DOE), this sodium must be transformed into a stable condition for land disposal. To comply with this mandate, ANL-W designed and built the Sodium Process Facility (SPF) for the processing of this sodium into a dry, sodium carbonate powder. The major portion of the sodium stored at ANL-W is radioactively contaminated. The sodium will be processed in three separate and distinct campaigns: the 290,000 liters of Fermi-1 primary sodium, the 50,000 liters of the Experimental Breeder Reactor-II (EBR-II) secondary sodium, and the 330,000 liters of the EBR-II primary sodium. The Fermi-1 and the EBR-II secondary sodium contain only low-level of radiation, while the EBR-II primary sodium has radiation levels up to 0.5 mSv (50 mrem) per hour at 1 meter. The EBR-II primary sodium will be processed last, allowing the operating experience to be gained with the less radioactive sodium prior to reacting the most radioactive sodium. The sodium carbonate will be disposed of in 270 liter barrels, four to a pallet. These barrels are square in cross-section, allowing for maximum utilization of the space on a pallet, minimizing the required landfill space required for disposal

  6. TOURISM POTENTIALITY OF OLD HALFETİ (ŞANLIURFA REPLACED BY BİRECİK DAM

    Directory of Open Access Journals (Sweden)

    Zeki Boyraz

    2015-12-01

    Full Text Available In this study, tourism potentiality of old Halfeti will be tired to be depicted. Old Halfeti, the subject of the study, stands in 130 km west of Şanlıurfa city center, in the east of Fırat River and on 388 m height. While old Halfeti was a town relate to city of Şanlıurfa, after the year 2000, 2/5 (180 hectar of old Halfeti was covered with the water of dam lake as a result of completion of Birecik Dam that is a part of GAP. Whole of the region except two districts have been moved to the region of Karaotaklak since 1999 by the completion of Birecik dam. Rüştiye and Şimaliye regions that remained in old Halfeti have been united to New Halfeti. Halfeti, with its natural beauty, boat excursions on Birecik Dam Lake, its architecture and Siyahgül, became the member of Cittaslow (peaceful city in 2013 and takes attention as its historical structures stays under the lake. Furthermore, it has been a region visited frequently by tourists in recent years because of its location being near to some touristic places such as Rumkale, Zeugma, Savaşan Köyü, Erenköy. In this study, old Halfeti (Şanlıurfa that has developed with its peripheral in terms of tourism sector will be analyzed.

  7. Improved HEPA Filter Technology for Flexible and Rigid Containment Barriers

    Energy Technology Data Exchange (ETDEWEB)

    P. A. Pinson

    1998-07-01

    Safety and reliability in glovebox operations can be significantly improved and waste packaging efficiencies can be increased by inserting flexible, lightweight, high capacity HEPA filters into the walls of plastic sheet barriers. This HEPA filter/barrier technology can be adapted to a wide variety of applications: disposable waste bags, protective environmental barriers for electronic equipment, single or multiple use glovebag assemblies, flexible glovebox wall elements, and room partitions. These reliable and inexpensive filtered barriers have many uses in fields such as radioactive waste processing, HVAC filter changeout, vapor or grit blasting, asbestos cleanup, pharmaceutical, medical, biological, and electronic equipment containment. The applications can result in significant cost savings, improved operational reliability and safety, and total waste volume reduction. This technology was developed at the Argonne National Laboratory-West (ANL-W) in 1993 and has been used at ANL-W since then at the TRU Waste Characterization Chamber Gloveboxes. Another 1998 AGS Conference paper titled "TRU Waste Characterization Gloveboxes", presented by Mr. David Duncan of ANL-W, describes these boxes.

  8. High-performance batteries for electric-vehicle propulsion and stationary energy storage. Progress report, October 1977--September 1978

    Energy Technology Data Exchange (ETDEWEB)

    Nelson, P.A.; Barney, D.L.; Steunenberg, R.K.

    1978-11-01

    The research, development, and management activities of the programs at Argonne National Laboratory (ANL) and at industrial subcontractors' laboratories on high-temperature batteries during the period October 1977--September 1978 are reported. These batteries are being developed for electric-vehicle propulsion and for stationary-energy-storage applications. The present cells, which operate at 400 to 500/sup 0/C, are of a vertically oriented, prismatic design with one or more inner positive electrodes of FeS or FeS/sub 2/, facing electrodes of lithium--aluminum alloy, and molten LiCl--KCl electrolyte. During this fiscal year, cell and battery development work continued at ANL, Eagle--Picher Industries, Inc., the Energy Systems Group of Rockwell International, and Gould Inc. Related work was also in progress at the Carborundum Co., General Motors Research Laboratories, and various other organizations. A major event was the initiation of a subcontract with Eagle--Picher Industries to develop, design, and fabricate a 40-kWh battery (Mark IA) for testing in an electric van. Conceptual design studies on a 100-MWh stationary-energy-storage module were conducted as a joint effort between ANL and Rockwell International. A significant technical advance was the development of multiplate cells, which are capable of higher performance than bicells. 89 figures, 57 tables.

  9. High-performance batteries for electric-vehicle propulsion and stationary energy storage. Progress report, October 1978-September 1979. [40 kWh, Li-Al and Li-Si anodes

    Energy Technology Data Exchange (ETDEWEB)

    Barney, D. L.; Steunenberg, R. K.; Chilenskas, A. A.; Gay, E. C.; Battles, J. E.; Hornstra, F.; Miller, W. E.; Vissers, D. R.; Roche, M. F.; Shimotake, H.; Hudson, R.; Askew, B. A.; Sudar, S.

    1980-03-01

    The research, development, and management activities of the programs at Argonne National Laboratory (ANL) and at contractors' laboratories on high-temperature batteries during the period October 1978 to September 1979 are reported. These batteries are being developed for electric-vehicle propulsion and for stationary energy-storage applications. The present cells, which operate at 400 to 500/sup 0/C, are of a vertically oriented, prismatic design with one or more inner positive electrodes of FeS or FeS/sub 2/, facing negative electrodes of lithium-aluminum or lithium-silicon alloy, and molten LiCl-KC1 electrolyte. During this reporting period, cell and battery development work has continued at ANL and contractors' laboratories. A 40 kWh electric-vehicle battery (designated Mark IA) was fabricated and delivered to ANL for testing. During the initial heat-up, one of the two modules failed due to a short circuit. A failure analysis was conducted, and the Mark IA program completed. Development work on the next electric-vehicle battery (Mark II) was initiated at Eagle-Picher Industries, Inc. and Gould, Inc. Work on stationary energy-storage batteries during this period has consisted primarily of conceptual design studies. 107 figures, 67 tables.

  10. Effect of surface finish and loading conditions on the LCF behavior of austenitic stainless steel in PWR environment

    International Nuclear Information System (INIS)

    ANL has issued in 2006 a NUREG/CR-6909 report that is now applicable in the US for evaluations of PWR environmental effects in the fatigue analysis of new reactor components. In order to assess the conservativeness of the application of this NUREG report, low cycle fatigue (LCF) tests were performed by AREVA NP on austenitic stainless steel specimens in a PWR environment. The selected material exhibits in an air environment a fatigue behavior consistent with the ANL reference 'air' mean curve. Tests were performed in PWR environment for two various loading conditions: for fully reverse triangular signal (for comparison purpose with tests performed by other laboratories with same loading conditions) and complex signal, simulating strain variation for actual typical PWR thermal transients. Two surface finish conditions were tested: polished and ground. This paper presents the comparison of environmental penalty factors (Fen) as observed experimentally with the ANL formulation (considering the strain integral method for complex loading), and the actual fatigue life of the specimen with the fatigue life predicted through the NUREG/CR-6909 application

  11. Radiological status report for the EBWR containment building. Volume 1: Summary and analysis

    International Nuclear Information System (INIS)

    At the conclusion of the EBWR D and D process, ANL Health Physics conducted a release survey to determine the radiological status of the facility. The primary goal of the survey was to verify that residual activities on building surfaces met DOE and ANL guidelines for downposting of a Radiologically Contaminated Area to a Radiologically Controlled Area. The resultant area was to bear no contamination designation, with no requirements for radiological personnel monitoring or protective clothing. ANL Health Physics designed a survey procedure, using a graded approach considering the building history, the D and D process, and the intended future use. The survey followed the general guidance of NRC NUREG/CR-5849, but simplified and reduced in scope to match the release goal. The building interior surfaces were divided into 15 principal survey units and one special survey unit. Each of the principal survey units had to meet the controlled release guidelines. The procedure consisted of dual full floor scans for beta/gamma activity, sampling measurements of total and removable alpha and beta/gamma activities, and background gamma exposure surveys. In the 15 principal survey units, surface activities were measured at a total of 444 locations. With the exception of certain excluded contaminated areas and mechanical equipment, the building interior meets the limited release guidelines

  12. MURR-IAEA Coordinated Research Project on Developing Techniques for Small-Scale Indigenous 99Mo Production Using LEU Fission or Neutron Activation [Country report: United States of America - MURR

    International Nuclear Information System (INIS)

    The University of Missouri Research Reactor (MURR) officially became an Agreement Holder in October of 2006 based on the sponsorship provided by Argonne National Laboratory (ANL). MURR’s role as an Agreement Holder was to provide support to the CRP based on MURR’s collaboration with ANL. MURR performed two (2) trial demonstrations designed to validate the efficacy of ANL’s annular LEU-foil target and LEU-Modified Cintichem process technologies. The first trial demonstration was performed in October of 2008 using LEU-foil supplied by ANL. The second trial demonstration was performed in April of 2009 using LEU-foil supplied by the Korean Atomic Energy Research Institute (KAERI). The 99Mo yield of each of the trial demonstrations was about 90%. The quality assay of the finished sodium molybdate product was verified to be comparable to the HEU-based sodium molybdate supplied to the worldwide market by the major 99Mo producers. The results and “lessons learned” from these two successful trial demonstrations were shared with all Contract Holders. Other significant contributions made to the subject CRP are listed

  13. Design of Mixed Batch Reactor and Column Studies at Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Wu, Weimin [Stanford Univ., CA (United States); Criddle, Craig S. [Stanford Univ., CA (United States)

    2015-11-16

    We (the Stanford research team) were invited as external collaborators to contribute expertise in environmental engineering and field research at the ORNL IFRC, Oak Ridge, TN, for projects carried out at the Argonne National Laboratory and funded by US DOE. Specifically, we assisted in the design of batch and column reactors using ORNL IFRC materials to ensure the experiments were relevant to field conditions. During the funded research period, we characterized ORNL IFRC groundwater and sediments in batch microcosm and column experiments conducted at ANL, and we communicated with ANL team members through email and conference calls and face-to-face meetings at the annual ERSP PI meeting and national meetings. Microcosm test results demonstrated that U(VI) in sediments was reduced to U(IV) when amended with ethanol. The reduced products were not uraninite but unknown U(IV) complexes associated with Fe. Fe(III) in solid phase was only partially reduced. Due to budget reductions at ANL, Stanford contributions ended in 2011.

  14. The PAMTRAK system and its operational issues

    Energy Technology Data Exchange (ETDEWEB)

    Dahly, B. [Sandia National Labs., Albuquerque, NM (United States); Walters, G. [Argonne National Lab., Idaho Falls, ID (United States)

    1995-10-01

    A system has been developed by Sandia National Laboratories (SNL) as part of the joint laboratory project with Los Alamos National Laboratory and Argonne National Laboratory-West (ANL-W). The objective is to provide support for Safeguards and Security and Nuclear Materials Control and Accountability within the DOE complex. Since its original design PAMTRAK has been enhanced to include material monitoring, personnel monitoring, and video surveillance. Material monitoring is provided by the WATCH (Wireless Alarm Transmission of Container Handling) subsystem by performing continuous surveillance via constantly monitored Tamper Indicating Devices of all material not directly involved in the fuel manufacturing process. Personnel tracking uses radio frequency and infrared sensors to detect unauthorized access to restricted areas and to enforce constant monitoring of containers or other objects within a ``region of interest`` in a storage vault or other restricted area. Advantages of combining these sensor subsystems include reducing personnel radiation exposure by extending the time between required physical inventory intervals as well as adding robustness to existing security measures. PAMTRAK is being demonstrated as part of the integrated materials monitoring and accounting system in the Fuels and Manufacturing Facility (FMF) located at ANL-W. This paper will describe the technologies employed for installation of the system by SNL, as well as the operational issues involved in using the system at ANL-W.

  15. Applications of synchrotron radiation to Chemical Engineering Science: Workshop report

    International Nuclear Information System (INIS)

    This report contains extended abstracts that summarize presentations made at the Workshop on Applications of Synchrotron Radiation to Chemical Engineering Science held at Argonne National Laboratory (ANL), Argonne, IL, on April 22--23, 1991. The talks emphasized the application of techniques involving absorption fluorescence, diffraction, and reflection of synchrotron x-rays, with a focus on problems in applied chemistry and chemical engineering, as well as on the use of x-rays in topographic, tomographic, and lithographic procedures. The attendees at the workshop included experts in the field of synchrotron science, scientists and engineers from ANL, other national laboratories, industry, and universities; and graduate and undergraduate students who were enrolled in ANL educational programs at the time of the workshop. Talks in the Plenary and Overview Session described the status of and special capabilities to be offered by the Advanced Photon Source (APS), as well as strategies and opportunities for utilization of synchrotron radiation to solve science and engineering problems. Invited talks given in subsequent sessions covered the use of intense infrared, ultraviolet, and x-ray photon beams (as provided by synchrotrons) in traditional and nontraditional areas of chemical engineering research related to electrochemical and corrosion science, catalyst development and characterization, lithography and imaging techniques, and microanalysis

  16. Performance comparison of liquid metal and gas cooled ATW system point designs

    International Nuclear Information System (INIS)

    As part of the Advanced Accelerator Application (AAA) program in the U.S., preliminary design studies have been performed at Argonne National Laboratory (ANL) and Los Alamos National Laboratory (LANL) to define and compare candidate Accelerator Transmutation of Waste (ATW) systems. The studies at ANL have focused primarily on the transmutation blanket component of the overall system. Lead-bismuth eutectic (LBE), sodium, and gas cooled systems are among the blanket technology options currently under consideration. This paper summarizes the results from neutronics trade studies performed at ANL. Core designs have been developed for LBE and sodium cooled 840 MWt fast spectrum accelerator driven systems employing re-cycle. Additionally, neutronics analyses have been performed for a helium-cooled 600 MWt hybrid thermal and fast spectrum system proposed by General Atomics (GA), which is operated in the critical mode for three cycles and in a subcritical accelerator driven mode for a subsequent single cycle. For these three point designs, isotopic inventories, consumption rates, and annual burnup rates are compared. The mass flows and the ultimate loss of transuranic (TRU) isotopes to the waste stream per unit of heat generated during transmutation are also compared on a consistent basis. (author)

  17. Safety assessment of the Indonesian multipurpose reactor RSG-GAS against ATWS and hypothetical accidents

    International Nuclear Information System (INIS)

    Investigation on ATWS and hypothetical accidents for the Indonesian Multipurpose Reactor RSG-GAS have been undertaken by computer simulation technique. Two computer codes, namely RELAP5 and PARET-ANL, were used as the main tools. The RELAP5 was utilized to perform system analysis while the PARET-ANL code was used to perform the reactor core analysis in more detail. Two different models have been applied as a basis of the simulation: Typical Working Core model (IWC-model) consisting of four regions with different radial power factors; and the hot-channel model consisting of two regions with different radial power factors. Both RELAP5 ad PARET-ANL results showed that in the occurrence of ATWS, failure on fuel element or fuel plate was limited to the region with the most highest power factor. The results also indicated that no high pressure development occurs in that region, so that mechanical damage on the fuel element or other core components due to pressure shock did not happen.(author)

  18. Environmental Survey preliminary report, Argonne National Laboratory, Argonne, Illinois

    Energy Technology Data Exchange (ETDEWEB)

    1988-11-01

    This report presents the preliminary findings of the first phase of the Environmental Survey of the United States Department of Energy's (DOE) Argonne National Laboratory (ANL), conducted June 15 through 26, 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 ANL. 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 ANL, 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 (ORNL). When completed, the S A results will be incorporated into the Argonne National Laboratory Environmental Survey findings for inclusion in the Environmental Survey Summary Report. 75 refs., 24 figs., 60 tabs.

  19. The PAMTRAK system and its operational issues

    International Nuclear Information System (INIS)

    A system has been developed by Sandia National Laboratories (SNL) as part of the joint laboratory project with Los Alamos National Laboratory and Argonne National Laboratory-West (ANL-W). The objective is to provide support for Safeguards and Security and Nuclear Materials Control and Accountability within the DOE complex. Since its original design PAMTRAK has been enhanced to include material monitoring, personnel monitoring, and video surveillance. Material monitoring is provided by the WATCH (Wireless Alarm Transmission of Container Handling) subsystem by performing continuous surveillance via constantly monitored Tamper Indicating Devices of all material not directly involved in the fuel manufacturing process. Personnel tracking uses radio frequency and infrared sensors to detect unauthorized access to restricted areas and to enforce constant monitoring of containers or other objects within a ''region of interest'' in a storage vault or other restricted area. Advantages of combining these sensor subsystems include reducing personnel radiation exposure by extending the time between required physical inventory intervals as well as adding robustness to existing security measures. PAMTRAK is being demonstrated as part of the integrated materials monitoring and accounting system in the Fuels and Manufacturing Facility (FMF) located at ANL-W. This paper will describe the technologies employed for installation of the system by SNL, as well as the operational issues involved in using the system at ANL-W

  20. Combined SO/sub x//NO/sub x/ removal in a high-sulfur spray-dryer/fabric-filter system

    Energy Technology Data Exchange (ETDEWEB)

    Livengood, C.D.; Huang, H.S.; Allen, J.W.; Farber, P.S.

    1988-01-01

    Argonne National Laboratory (ANL) has been conducting research on combined nitrogen oxides (NO/sub x/) and sulfur dioxide (SO/sub 2/) control. A major portion of this program has been centered around the spray-dryer/fabric-filter system that provides flue-gas cleanup (FGC) for Argonne's largest, coal-fired boiler. Under the combined SO/sub x//NO/sub x/ research program, Argonne conducted two series of field tests on the spray-dryer FGC system. The conditions for the tests were selected on the basis of previous work by Niro Atomizer (using the ANL system), laboratory research at ANL, and intermediate-scale tests at the Pittsburgh Energy Technology Center (PETC). Both changes in process operating conditions and addition of caustic soda (NaOH) to the lime slurry were employed. The results indicated that, under certain operating conditions, it is possible to achieve significant levels of combined control. The addition of NaOH was not essential, but did enhance removal of NO/sub x/. Also, higher levels of SO/sub 2/ in the inlet flue gas were found to be beneficial, and changes in particle characteristics that developed in the drying process were found to play a role that has implications for other technologies based on dry sorbents. 6 refs., 10 figs., 3 tabs.

  1. Status of uranium-silicon alloy fuel development for the RERTR program

    International Nuclear Information System (INIS)

    As part of the national Reduced Enrichment Research and Test Reactor (RERTR) Program, Argonne National Laboratory (ANL) is engaged in a fuel-alloy development project. The fuel alloys are dispersed in an aluminum matrix and metallurgically roll-bonded within 6061 Al alloy. To date, miniplates with up to 40 vol. % fuel alloy have been successfully fabricated. Thirty-one of these plates have been or are being irradiated in the Oak Ridge Reactor (ORR). Three different fuels have been used in the ANL miniplates: U3Si, U3Si2, or U3SiAl. All three are candidates for permitting higher fuel loadings and thus lower enrichments than would be possible with either UAl/sub x/ or U3O8, the current fuels for plate-type elements. The enrichment level employed at ANL is approx. 19.8%. Continuing effort involves the production of miniplates with up to approx. 60 vol. % fuel, the development of a technology for full-size plate fabrication, and post-irradiation examination of miniplates already removed from the ORR Reactor

  2. U-Si and U-Si-Al dispersion fuel alloy development for research and test reactors

    International Nuclear Information System (INIS)

    As part of the National Reduced Enrichment Research and Test Reactor Program, Argonne National Laboratory (ANL) is engaged in a fuel alloy development project. Fuel alloy powder prepared with low-enrichment uranium (235U) is dispersed in an aluminum matrix, and metallurgically roll-bonded within a clad of 6061 Al alloy. Miniplates with up to 55 vol.% fuel alloy (up to 7.0 grams total U per cm3) have been successfully fabricated. Fifty-five of these plates have been or are being irradiated in the Oak Ridge Research Reactor. Three fuel alloys have been used in the ANL miniplates: U3Si (U + 4 wt.% Si), U3Si2 (U + 7.5 wt.% Si), and 'U3SiAl' (U + 3.5 wt.% Si + 1.5 wt.% Al). All are candidates for permitting higher fuel loadings and thus lower enrichments of 235U than would be possible with either UAlx or U3O8, the current fuels for plate-type elements. As an adjunct to the development effort, ANL is engaged in the early stages of technology transfer with commercial fabricators of fuel elements for research reactors. Continuing effort also involves the development of a technology for full-size plate fabrication, and the irradiation of miniplates to a burnup of ∼90% 235U depletion. (author)

  3. Technical evaluation of available state of Nevada survey instruments

    International Nuclear Information System (INIS)

    Argonne National Laboratory (ANL) is reviewing the survey research studies completed by Mountain West Research (1987-1989) for the state of Nevada's Nuclear Waste Project Office. In this research, 14 survey instruments were used to seek data on whether perceptions of risk could be associated with the possible siting of a high-level radioactive waste repository in Nevada and could be a dominant source of potential, significant, adverse economic impacts. This report presents results from phase 1 of the review, in which ANL contracted with the National Opinion Research Center (NORC) at the University of Chicago to evaluate the technical merits of the nine survey instruments that ANL had been able to acquire. The scope of NORC's work was limited to rating the questions and stating their strengths and weaknesses. NORC concluded that the surveys could provide valuable data about risk perceptions and potential behavioral responses. NORC identified a few minor problems with a number of questions and the calculated response rates but claimed these problems would probably not have any major biasing effect. The NORC evaluation would have been more complete if the terms used in the questionnaires had been defined, all survey instruments had been acquired, and all data had been made available to the public

  4. Applications of synchrotron radiation to Chemical Engineering Science: Workshop report

    Energy Technology Data Exchange (ETDEWEB)

    1991-07-01

    This report contains extended abstracts that summarize presentations made at the Workshop on Applications of Synchrotron Radiation to Chemical Engineering Science held at Argonne National Laboratory (ANL), Argonne, IL, on April 22--23, 1991. The talks emphasized the application of techniques involving absorption fluorescence, diffraction, and reflection of synchrotron x-rays, with a focus on problems in applied chemistry and chemical engineering, as well as on the use of x-rays in topographic, tomographic, and lithographic procedures. The attendees at the workshop included experts in the field of synchrotron science, scientists and engineers from ANL, other national laboratories, industry, and universities; and graduate and undergraduate students who were enrolled in ANL educational programs at the time of the workshop. Talks in the Plenary and Overview Session described the status of and special capabilities to be offered by the Advanced Photon Source (APS), as well as strategies and opportunities for utilization of synchrotron radiation to solve science and engineering problems. Invited talks given in subsequent sessions covered the use of intense infrared, ultraviolet, and x-ray photon beams (as provided by synchrotrons) in traditional and nontraditional areas of chemical engineering research related to electrochemical and corrosion science, catalyst development and characterization, lithography and imaging techniques, and microanalysis.

  5. The determination of PCBs in Rocky Flats Type IV waste sludge by gas chromatography/electron capture detection. Part 2

    International Nuclear Information System (INIS)

    Before disposal, radioactive sludge (Type IV) from Rocky Flats Plant (RFP) must be evaluated for polychlorinated biphenyl (PCB) content. The Type IV sludge consists of organic solvents, degreasers, cutting oils, and transuranic (TRU) waste mixed with calcium silicate (MicroCel E reg-sign and Oil Dri reg-sign to form a grease or paste-like material. For laboratory testing, a nonradioactive simulated Type 17V RFP sludge was prepared at Argonne National Laboratory-East (ANL-E). This sludge has a composition similar to that expected from field samples. In an earlier effort, a simplified method was developed for extraction, cleanup of extract, and determination of PCBs in samples of simulated sludge spiked with Aroclors 1254 and 1260. The simplified method has now been used to determine the presence and quantities of other Aroclors in the simulated sludge, namely, Aroclors 10 1 6, 1221, 1232, 1242, and 1248. The accuracy and precision of the data for these Aroclors were found to be similar to the data for sludges spiked with Aroclors 1254 and 1260. Since actual sludges may vary in composition, the method was also verified by analyzing another source of Type IV simulated sludge, prepared by Argonne National Laboratory-West (ANL-W)

  6. Environmental Survey preliminary report, Argonne National Laboratory, Argonne, Illinois

    International Nuclear Information System (INIS)

    This report presents the preliminary findings of the first phase of the Environmental Survey of the United States Department of Energy's (DOE) Argonne National Laboratory (ANL), conducted June 15 through 26, 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 ANL. 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 ANL, 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 (ORNL). When completed, the S ampersand A results will be incorporated into the Argonne National Laboratory Environmental Survey findings for inclusion in the Environmental Survey Summary Report. 75 refs., 24 figs., 60 tabs

  7. Design of Mixed Batch Reactor and Column Studies at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    We (the Stanford research team) were invited as external collaborators to contribute expertise in environmental engineering and field research at the ORNL IFRC, Oak Ridge, TN, for projects carried out at the Argonne National Laboratory and funded by US DOE. Specifically, we assisted in the design of batch and column reactors using ORNL IFRC materials to ensure the experiments were relevant to field conditions. During the funded research period, we characterized ORNL IFRC groundwater and sediments in batch microcosm and column experiments conducted at ANL, and we communicated with ANL team members through email and conference calls and face-to-face meetings at the annual ERSP PI meeting and national meetings. Microcosm test results demonstrated that U(VI) in sediments was reduced to U(IV) when amended with ethanol. The reduced products were not uraninite but unknown U(IV) complexes associated with Fe. Fe(III) in solid phase was only partially reduced. Due to budget reductions at ANL, Stanford contributions ended in 2011.

  8. Technical evaluation of available state of Nevada survey instruments

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-02-01

    Argonne National Laboratory (ANL) is reviewing the survey research studies completed by Mountain West Research (1987-1989) for the state of Nevada`s Nuclear Waste Project Office. In this research, 14 survey instruments were used to seek data on whether perceptions of risk could be associated with the possible siting of a high-level radioactive waste repository in Nevada and could be a dominant source of potential, significant, adverse economic impacts. This report presents results from phase 1 of the review, in which ANL contracted with the National Opinion Research Center (NORC) at the University of Chicago to evaluate the technical merits of the nine survey instruments that ANL had been able to acquire. The scope of NORC`s work was limited to rating the questions and stating their strengths and weaknesses. NORC concluded that the surveys could provide valuable data about risk perceptions and potential behavioral responses. NORC identified a few minor problems with a number of questions and the calculated response rates but claimed these problems would probably not have any major biasing effect. The NORC evaluation would have been more complete if the terms used in the questionnaires had been defined, all survey instruments had been acquired, and all data had been made available to the public.

  9. Thermal-fluid and electrochemical modeling and performance study of a planar solid oxide electrolysis cell : analysis on SOEC resistances, size, and inlet flow conditions.

    Energy Technology Data Exchange (ETDEWEB)

    Yildiz, B.; Smith, J.; Sofu, T.; Nuclear Engineering Division

    2008-06-25

    Argonne National Laboratory and Idaho National Laboratory researchers are analyzing the electrochemical and thermal-fluid behavior of solid oxide electrolysis cells (SOECs) for high temperature steam electrolysis using computational fluid dynamics (CFD) techniques. The major challenges facing commercialization of steam electrolysis technology are related to efficiency, cost, and durability of the SOECs. The goal of this effort is to guide the design and optimization of performance for high temperature electrolysis (HTE) systems. An SOEC module developed by FLUENT Inc. as part of their general CFD code was used for the SOEC analysis by INL. ANL has developed an independent SOEC model that combines the governing electrochemical mechanisms based on first principals to the heat transfer and fluid dynamics in the operation of SOECs. The ANL model was embedded into the commercial STAR-CD CFD software, and is being used for the analysis of SOECs by ANL. The FY06 analysis performed by ANL and reported here covered the influence of electrochemical properties, SOEC component resistances and their contributing factors, SOEC size and inlet flow conditions, and SOEC flow configurations on the efficiency and expected durability of these systems. Some of the important findings from the ANL analysis are: (1) Increasing the inlet mass flux while going to larger cells can be a compromise to overcome increasing thermal and current density gradients while increasing the cell size. This approach could be beneficial for the economics of the SOECs; (2) The presence of excess hydrogen at the SOEC inlet to avoid Ni degradation can result in a sizeable decrease in the process efficiency; (3) A parallel-flow geometry for SOEC operation (if such a thing be achieved without sealing problems) yields smaller temperature gradients and current density gradients across the cell, which is favorable for the durability of the cells; (4) Contact resistances can significantly influence the total cell

  10. Cow/calf preweaning efficiency of Nellore and Bos taurus x Bos indicus crosses.

    Science.gov (United States)

    Calegare, L; Alencar, M M; Packer, I U; Ferrell, C L; Lanna, D P D

    2009-02-01

    The objectives of this study were to determine if percentage Bos taurus (0 or 50%) of the cow had an effect on ME requirements and milk production, and to compare cow/calf efficiency among 3 mating systems. Metabolizable energy requirements were estimated during a feeding trial that encompassed a gestation and lactation feeding trial for each of 2 groups of cows. Cows were 0 or 50% Bos taurus (100 or 50% Nellore) breed type: Nellore cows (NL; n = 10) mated to Nellore bulls, NL cows (n = 9) mated to Angus bulls, Angus x Nellore (ANL; n = 10) and Simmental x Nellore (SNL; n = 10) cows mated to Canchim (5/8 Charolais 3/8 Zebu) bulls. Cows were individually fed a total mixed diet that contained 11.3% CP and 2.23 Mcal of ME/kg of DM. At 14-d intervals, cows and calves were weighed and the amount of DM was adjusted to keep shrunk BW and BCS of cows constant. Beginning at 38 d of age, corn silage was available to calves ad libitum. Milk production at 42, 98, 126, and 180 d postpartum was measured using the weigh-suckle-weigh technique. At 190 d of age, calves were slaughtered and body composition estimated using 9-10-11th-rib section to obtain energy deposition. Regression of BW change on daily ME intake (MEI) was used to estimate MEI at zero BW change. Increase in percentage Bos taurus had a significant effect on daily ME requirements (Mcal/d) during pregnancy (P < 0.01) and lactation (P < 0.01). Percentage Bos taurus had a positive linear effect on maintenance requirements of pregnant (P = 0.07) and lactating (P < 0.01) cows; during pregnancy, the ME requirements were 91 and 86% of those in lactation (131 +/- 3.5 vs. 145 +/- 3.4 Mcal x kg(-0.75) x d(-1)) for the 0 and 50% B. taurus groups, respectively. The 50% B. taurus cows, ANL and SNL, suckling crossbred calves had greater total MEI (4,319 +/- 61 Mcal; P < 0.01) than 0% B. taurus cows suckling NL (3,484 +/- 86 Mcal) or ANL calves (3,600 +/- 91 Mcal). The 0% B. taurus cows suckling ANL calves were more efficient (45

  11. 普通话可接受噪声级的复测信度分析%Test-retest reliability of Mandarin acceptable noise level

    Institute of Scientific and Technical Information of China (English)

    吴丹; 张华; 陈建勇; 王硕; 陈静; 吴燕君; 李玉玲; 任丹丹

    2013-01-01

    Objective:To evaluate test-retest reliability of Mandarin acceptable noise leveKM-ANL) test materials. Method:M-ANL was evaluated during three test sessions approximately one week apart, by testing 30 Mandarin-speaking people aged from 21 to 28 with normal aural/oral communicational abilities. The participants completed the preference for background noise questionnaire before the first session. Analysis of the test-retest results were administered by SPSS 17. 0 (Statistically Package for the Social Sciences Software Version 17. 0). Result: ANLs in the three sessions were(8. 1 ± 2. 9) , (7. 4±2. 2), (7. 6 ± 2. 5)dB S/N,respectively. The correlation coefficients were 0. 722,0. 746 and 0. 849 between two of the three sessions. The correlation coefficients of the ANL and 7 questions of the questionnaire were below 0. 3. Conclusion:M-ANL test materials are found to have good test-retest reliability. Listeners' preference for background noise is not related to their acceptance of background noise. Listeners cannot accurately assess their ability to accept background noise.%目的:通过对普通话可接受噪声级(M-ANL)材料进行复测信度评估,分析正常人的ANL与对噪声耐受的关系.方法:选取听力言语正常的21~28岁青年受试者30例,对其进行M-ANL测试,再分别于1周及2周后,以同样的测试条件进行第2次复测.每位受试者于第1次测试前填写1份对噪声耐受问卷.使用SPSS17.0软件对结果进行统计学分析.结果:3次ANL值分别为(8.1±2.9)dB S/N、(7.4±2.2)dB S/N、(7.6±2.5)dB S/N,两两配对t检验及Pearson相关分析,P=0.079、0.147、0.588,r=0.722、0.746、0.849.ANL与问卷中7个问题得分均r<0.3.结论:M-ANL测试具有较好的复测信度;个体对噪声的耐受与ANL无关,其并不能正确地自我判断实际对噪声的接受能力.

  12. Effect of Antioxidases on Color of Brown Cotton%抗氧化酶对棕色棉色泽的影响

    Institute of Scientific and Technical Information of China (English)

    苏翔; 孙旭; 李廷春; 凌磊; 林毅; 蔡永萍

    2009-01-01

    以棕色棉和白色棉为材料,测定发育期种皮与纤维中抗氧化酶及色素合成相关物质含量的变化,初步探讨抗氧化酶对棕色棉色泽的影响.结果表明:纤维次生壁沉积期(25~45 DPA),棕色棉种皮颜色显著加深;次生壁沉积后期(35~45 DPA),棕色棉纤维颜色加深明显.花后28~35 d,浅棕ANL-2种皮缩合单宁和总酚含量下降,棕色素积累;花后35~42 d,深棕ANL-1纤维缩合单宁含量降低,总酚含量上升,纤维颜色变化最深.花后28~35 d,浅棕ANL-2种皮POD活性下降;花后35~42 d,棕色棉纤维POD活性降低;SOD与CAT对棕色棉色泽影响不大;POD在次生壁沉积后期(35~45 DPA)参与棕色素的形成.%Brown and white cotton cultivars were used as materials, the change of the content of related substances to pigment synthesis and the activities of antioxidases both in the fiber and the seed capsule during the development were investigated, and the effect of antioxidases on color of brown cotton was studied. The results indicated that the color of the seed capsule darkened apparently during the secondary cell wall thickening period(25~45 DPA);the color of the fiber darkened obviously during the secondary cell wall thickening period(35~45 DPA).The content of condensed tannin and the phenol in the seed capsule of light brown ANL-2 decreased and pigments accumulated from 28 to 35 DPA; the content of condensed tannin in the fiber of dark brown ANL-1 decreased ,while the content of the phenol increased ,and the color of the fiber became darkest from 35 to 42 DPA. The activity of POD in the seed capsule of light brown ANL-2 from 28 to 35 DPA decreased, and the activity of POD in the fiber of brown cotton decreased from 35 to 42 DPA; the effect of SOD and CAT on color of brown cotton was small. POD participated in the formation of pigments during the secondary cell wall thickening period(35~45 DPA).

  13. Evaluation of safety parameters for GHARR-1 after nineteen (19) years of operation

    International Nuclear Information System (INIS)

    Evaluation of safety parameters of GHARR-1 after nineteen years of operation were performed and are presented herein. This work serves as an input into periodic evaluations of safety parameters. Due to fuel depletion, the excess reactivity for GHARR-1 drops to the allowed lower limit of 2.3 mk from 4 mk in about 2 years. Beryllium is added to the top shim tray of the core to compensate for reactivity loss. The addition of beryllium to the top of the core requires evaluations of safety parameters. The objective for this work was to evaluate the safety parameters of GHARR-1 after 19 years of operation and compare them with those provided in the SAR and other literature. Four codes namely; REBUS/ANL, MCNP, PARET/ANL and PLTEMP/ANL were used in this work. The REBUS/ANL code was used to generate an inventory of isotopes in the fuel after 19 years of operation. The masses for the isotopes were used to update the material card in the MCNP model for GHARR-1 and 9 mm of beryllium was also added to the top shim tray in the model. The MCNP code was used to predict neutronics and kinetic parameters of GHARR-1. The neutron generation time, delayed neutron fraction, axial power peaking factors, fuel temperature reactivity coefficient, moderator temperature coefficient and the moderator void coefficient were used in the PARET/ANL code to predict the transient and steady state parameters of the reactor. The existing PLTEMP/ANL input deck was updated with the axial and radial power peaking factors obtained from the MCNP simulations. The code was used to predict the steady state parameters; DNBR, ONBR, FIR, saturation and ONB temperatures respectively. The delayed neutron fraction, neutron generation time, moderator reactivity coefficient were predicted as; 8.17507×10-3 Δκ/κ, 8.147×10-5s,-0.1218 mk which compared with those provided in the SAR as 8.08× 10-3Δκ/κ, 8.12 ×10-5s ,-0.13 mk. The maximum power peaking factor was predicted as 1.3522 compared to 1.3525 for the clean

  14. Acceleration of epithelial cell syndecan-1 shedding by anthrax hemolytic virulence factors

    Directory of Open Access Journals (Sweden)

    Chandhoke Vikas

    2006-02-01

    Full Text Available Abstract Background It has been recently reported that major pathogens Staphylococcus aureus and Pseudomonas aeruginosa accelerate a normal process of cell surface syndecan-1 (Synd1 ectodomain shedding as a mechanism of host damage due to the production of shedding-inducing virulence factors. We tested if acceleration of Synd1 shedding takes place in vitro upon treatment of epithelial cells with B. anthracis hemolysins, as well as in vivo during anthrax infection in mice. Results The isolated anthrax hemolytic proteins AnlB (sphingomyelinase and AnlO (cholesterol-binding pore-forming factor, as well as ClnA (B. cereus homolog of B. anthracis phosphatidyl choline-preferring phospholipase C cause accelerated shedding of Synd1 and E-cadherin from epithelial cells and compromise epithelial barrier integrity within a few hours. In comparison with hemolysins in a similar range of concentrations, anthrax lethal toxin (LT also accelerates shedding albeit at slower rate. Individual components of LT, lethal factor and protective antigen are inactive with regard to shedding. Inhibition experiments favor a hypothesis that activities of tested bacterial shedding inducers converge on the stimulation of cytoplasmic tyrosine kinases of the Syk family, ultimately leading to activation of cellular sheddase. Both LT and AnlO modulate ERK1/2 and p38 MAPK signaling pathways, while JNK pathway seems to be irrelevant to accelerated shedding. Accelerated shedding of Synd1 also takes place in DBA/2 mice challenged with Bacillus anthracis (Sterne spores. Elevated levels of shed ectodomain are readily detectable in circulation after 24 h. Conclusion The concerted acceleration of shedding by several virulence factors could represent a new pathogenic mechanism contributing to disruption of epithelial or endothelial integrity, hemorrhage, edema and abnormal cell signaling during anthrax infection.

  15. Chemical Technology Division Annual Report 2000

    International Nuclear Information System (INIS)

    The Chemical Technology Division (CMT) is one of eight engineering research divisions within Argonne National Laboratory (ANL), one of the U.S. government's oldest and largest research laboratories. The University of Chicago oversees the laboratory on behalf of the U.S. Department of Energy (DOE). Argonne's mission is to conduct basic scientific research, to operate national scientific facilities, to enhance the nation's energy resources, and to develop better ways to manage environmental problems. Argonne has the further responsibility of strengthening the nation's technology base through developing industrial technology and transferring that technology to industry. The Chemical Technology Division is a diverse early-stage engineering organization, specializing in the treatment of spent nuclear fuel, development of advanced power sources, and management of both high- and low-level nuclear wastes. Although this work is often indistinguishable from basic research, our efforts are directed toward the practical devices and processes that are covered by ANL's mission. Additionally, the Division operates the Analytical Chemistry Laboratory, which provides a broad range of analytical services to ANL and other organizations. The Division is multi-disciplinary. Its people have formal training as ceramists; physicists; material scientists; electrical, mechanical, chemical, and nuclear engineers; and chemists. They have experience working in academia, urban planning, and the petroleum, aluminum, and automotive industries. Their skills include catalysis, ceramics, electrochemistry, metallurgy, nuclear magnetic resonance spectroscopy, and petroleum refining, as well as the development of nuclear waste forms, batteries, and high-temperature superconductors. In this annual report we present an overview of the technical programs together with representative highlights. The report is not intended to be comprehensive or encyclopedic, but to serve as an indication of the condition

  16. NRC Job Code V6060: Extended in-situ and real time monitoring. Task 4: Detection and monitoring of leaks at nuclear power plants external to structures

    Energy Technology Data Exchange (ETDEWEB)

    Sheen, S. H. (Nuclear Engineering Division)

    2012-08-01

    In support of Task 4 of the NRC study on compliance with 10 CFR part 20.1406, minimization of contamination, Argonne National Laboratory (ANL) conducted a one-year scoping study, in concert with a parallel study performed by NRC/NRR staff, on monitoring for leaks at nuclear power plants (NPPs) external to structures. The objective of this task-4 study is to identify and assess those sensors and monitoring techniques for early detection of abnormal radioactive releases from the engineered facility structures, systems and components (SSCs) to the surrounding underground environment in existing NPPs and planned new reactors. As such, methods of interest include: (1) detection of anomalous water content of soils surrounding SSCs, (2) radionuclides contained in the leaking water, and (3) secondary signals such as temperature. ANL work scope includes mainly to (1) identify, in concert with the nuclear industry, the sensors and techniques that have most promise to detect radionuclides and/or associated chemical releases from SSCs of existing NPPs and (2) review and provide comments on the results of the NRC/NRR staff scoping study to identify candidate technologies. This report constitutes the ANL deliverable of the task-4 study. It covers a survey of sensor technologies and leak detection methods currently applied to leak monitoring at NPPs. The survey also provides a technology evaluation that identifies their strength and deficiency based on their detection speed, sensitivity, range and reliability. Emerging advanced technologies that are potentially capable of locating releases, identifying the radionuclides, and estimating their concentrations and distributions are also included in the report along with suggestions of required further research and development.

  17. Comparison of the FRM-II HEU design with an alternative LEU design. Attachment

    International Nuclear Information System (INIS)

    After presentation of the foregoing paper by Dr. Nelson Hanan of Argonne National Laboratory (ANL) proposing an alternative LEU core with one fuel ring and a power level of 33 MW, a presentation was made by Dr. Klaus Boning of the Technical University of Munich comparing the FRM-II HEU design with an LEU design by Tlm that had two fuel rings and a power level of 40 MW. Dr. Boning raised the following issues concerning the use of LEU fuel in FRM-H reactor designs: (1) qualification of HEU and LEU silicide fuels, (2) gamma heating in the heavy water reflector, (3) the radiological consequences of hypothetical accidents, and (4) cost and schedule. These issues are addressed in this Attachment. In his presentation, Dr. Hanan mentioned that ANL was also investigating other LEU designs. This work led to a second alternative LEU design that has the same neutron flux performance (8 x 1014 n/cm2/s peak neutron flux in the reflector) and the same fuel lifetime (50 full power days) as the HEU design, but uses LEU silicide fuel with a uranium density of only 4.5 g/cm3. This design was achieved by using a fuel plate that has a fuel meat thickness of 0.76 mm, a cladding thickness of 0.38 mm, and a water channel gap of 2.2 mm. A comparison is shown of the main characteristics of this second alternative LEU design with those of the FRM-II HEU design. The ANL core again has one fuel ring with the same dimensions. With this LEU design, a two stage process is no longer necessary because LEU silicide fuel with a uranium density of 4.5 g/cm3 is fully qualified, licensable, and available now for use in a high flux reactor such as the FRM-II

  18. Planning for closure and deactivation of the EBR-II complex

    International Nuclear Information System (INIS)

    In January 1994, DOE terminated the Integral Fast Reactor (IFR) Program. Argonne National Laboratory-West (ANL-W) prepared a detailed plan to put Experimental Breeder Reactor-II (EBR-II) in a safe condition, including removal of irradiated fueled subassemblies from the plant, transfer of subassemblies, and removal and stabilization of primary and secondary sodium liquid heat transfer metal. The goal of deactivation is to stabilize the EBR-II complex until decontamination and decommissioning (D ampersand D) is implemented, thereby minimizing maintenance and surveillance. Deactivation of a sodium cooled reactor presents unique concerns. Residual sodium in the primary and secondary systems must be either reacted or inerted to preclude concerns with explosive sodium-air reactions. Also, residual sodium on components will effectively solder these items in place, making removal unfeasible. Several special cases reside in the primary system, including primary cold traps, a cesium trap, a cover gas condenser, and systems containing sodium-potassium alloy. The sodium or sodium-potassium alloy in these components must be reacted in place or the components removed. The Sodium Components Maintenance Shop at ANL-W provides the capability for washing primary components, removing residual quantities of sodium while providing some decontamination capacity. Considerations need to be given to component removal necessary for providing access to primary tank internals for D ampersand D activities, removal of hazardous materials, and removal of stored energy sources. ANL-W's plan for the deactivation of EBR-II addresses these issues, providing for an industrially and radiologically safe complex, requiring minimal surveillance during the interim period between deactivation and D ampersand D. Throughout the deactivation and closure of the EBR-II complex, federal environmental concerns will be addressed, including obtaining the proper permits for facility condition and waste processing

  19. Preliminary Study of the Supercritical CO2 Hybrid Cycle for the HTGR Application

    International Nuclear Information System (INIS)

    This study was conducted to explore the potential of Supercritical Carbon Dioxide (S-CO2) Brayton cycle for the HTGR application. The S-CO2 cycle is being considered as a PCS due to its high thermal efficiency, simplicity, compactness and so on. Generally, the S-CO2 Brayton cycle is characterized as a highly recuperated cycle which means that to achieve high thermal efficiency, the cycle requires a highly effective recuperator. Argonne National Laboratory (ANL) showed that direct application of the standard S-CO2 recompressing Brayton cycle to the HTGR or the Very High Temperature Reactor (VHTR) is difficult to achieve high thermal efficiency due to the mismatch of the temperature difference between the temperature drop of helium as the primary reactor coolant and the temperature rise of CO2 as the PCS coolant through an Intermediate Heat Exchanger (IHX). Therefore, our research team suggests a novel S-CO2 cycle configuration, the S-CO2 Brayton and Rankine hybrid cycle, to solve this limitation. This S-CO2 hybrid concept is utilizing the waste heat of the S-CO2 Brayton cycle as heat input to the S-CO2 Rankine cycle. Dividing the thermal capacity of the heat source in to the Brayton cycle part and Rankine cycle part of the S-CO2 hybrid cycle appropriately, the temperature difference at the IHX could be reduced, therefore the net system performance and operating range can be improved. In this study, the ANL research is reviewed by the in-house cycle analysis codes developed by the Korea Advanced Institute of Science and Technology (KAIST) research team. And the S-CO2 Brayton and Rankine hybrid cycle is studied as a PCS for the VHTR condition which was utilized by ANL research team; it was assumed that the core outlet temperature to be 850 .deg. C and the core inlet temperature of 400 .deg. C

  20. Results of performance and emission testing when co-firing blends of dRDF/COAL in a 440 MWe cyclone fired combustor

    International Nuclear Information System (INIS)

    Argonne National Laboratory (ANL) together with the University of North Texas (UNT) have developed an improved method for converting refuse (residential, commercial and institutional waste) into an environmentally safe and economical fuel. In this method, recyclable metals, glass, and some plastic products are separated from the refuse. The remaining fraction, consisting primarily of cellulosic materials is then combined with a calcium hydroxide binding additive and formed into cylindrical pellets. These pellets are dense and odorless, can be stored for extended periods of time without biological or chemical degradation, and due to their increased bulk density are more durable and can be more easily conveyed, handled, and transported than other types of waste-derived fuel pellets. Laboratory and pilot-scale research studies, followed by full-scale combustion tests undertaken by DOE, ANL and UNT, in June--July of 1987 have indicated that binder-enhanced dRDF pellets can be successfully cofired with high sulfur coal in spreader-stoker combustors. The results of these combustion tests indicated significant reductions of SO2, NOx and CO2 in the flue gases, and the reduction of heavy metals and organics in the ash residue. Dioxins and furans, both in the flue gas and in the ash residues were below detectable levels. Additional commercial-scale combustion tests have recently been conducted by DOE, NREL, ANL and several industrial participants including Otter Tail Power Company, Reuter, Inc., XL Recycling and Marblehead Lime Company, under a collaborative research and development agreement (CRADA). A large 440 MWe cyclone-fired combustor was tested at Big Stone City, South Dakota on October 26--27, 1992. This paper describes the cyclone-fired combustion tests, the flue gas emission and ash samples that were collected, the analyses that were performed on these samples, and the final test results

  1. U-Si and U-Si-Al dispersion fuel alloy development for research and test reactors

    International Nuclear Information System (INIS)

    As part of the National Reduced Enrichment Research and Test Reactor Program, Argonne National Laboratory (ANL) is engaged in a fuel alloy development project. The reduction of the 235U enrichment from above 90% to below 20% for such fuels would lessen the risk of diversion of the fuel for nonpeaceful uses. Fuel alloy powder prepared with low-enrichment uranium (235U) is dispersed in an aluminum matrix, and metallurgically roll bonded within a cladding of 6061 aluminum alloy. Miniplates with up to 55 vol% fuel alloy (up to 7.0 g total U/cm3) have been successfully fabricated. Fifty-five of these plates have been or are being irradiated in the Oak Ridge Research Reactor. Three fuel alloys have been used in the ANL miniplates: U3Si (U + 4 wt% Si), U3Si2 (U + 7.5 wt% Si), and ''U3SiAl'' (U + 3.5 wt% Si + 1.5 wt% Al). All are candidates for permitting higher fuel loadings and thus lower enrichments of 235U than would be possible with either UAl /SUB x/ or U3O8, the current fuels for plate-type elements. A target loading of up to 7.0 g U/cm3 in the fuel zone was selected. To date the fabrication and irradiation results with the silicide fuels have been encouraging, and as an adjunct to the development effort, ANL is engaged in the early stages of technology transfer with commercial fabricators of fuel elements for research reactors. Continuing effort also involves the development of a technology for full-sized plate fabrication and the irradiation of miniplates to a burnup of about 90% 235U depletion

  2. U-Si and U-Si-Al dispersion, fuel alloy development for research and test reactors

    International Nuclear Information System (INIS)

    As part of the National Reduced Enrichment Research and Test Reactor Program, Argonne National Laboratory (ANL) is engaged in a fuel alloy development project. The reduction of the 235U enrichment from above 90% to below 20% for such fuels would lessen the risk of diversion of the fuel for nonpeaceful uses. Fuel alloy powder prepared with low-enrichment uranium (235U) is dispersed in an aluminum matrix, and metallurgically roll bonded within a cladding of 6061 aluminum alloy. Miniplates with up to 55 vol% fuel alloy (up to 7.0 g total U/cm3) have been successfully fabricated. Fifty-five of these plates have been or are being irradiated in the Oak Ridge Research Reactor. Three fuel alloys have been used in the ANL miniplates: U3Si(U + 4 wt% Si), U3Si2(U + 7.5 wt% Si), and ''U3SiAl'' (U + 3.5 wt% Si + 1.5 wt% Al). All are candidates for permitting higher fuel loadings and thus lower enrichments of 235U than would be possible with either UAl/SUB x/ or U3O8, the current fuels for plate-type elements. A target loading of up to 7.0 g U/cm3 in the fuel zone was selected. To date the fabrication and irradiation results with the silicide fuels have been encouraging, and as an adjunct to the development effort, ANL is engaged in the early stages of technology transfer with commercial fabricators of fuel elements for research reactors. Continuing effort also involves the development of a technology for full-sized plate fabrication and the irradiation of miniplates to a burnup of about 90% 235U depletion

  3. IPNS upgrade: A feasibility study

    International Nuclear Information System (INIS)

    Many of Argonne National Laboratory's (ANL's) scientific staff members were very active in R ampersand D work related to accelerator-based spoliation sources in the 1970s and early 1980s. In 1984, the Seitz/Eastman Panel of the National Academy of Sciences reviewed U.S. materials science research facilities. One of the recommendations of this panel was that the United States build a reactor-based steady-state source, the Advanced Neutron Source (ANS), at Oak Ridge National Laboratory. Subsequently, R ampersand D activities related to the design of an accelerator-based source assumed a lower priority. The resumption of pulsed-source studies in this country started simultaneously with design activities in Europe aimed at the European Spallation Source (ESS). The European Community funded a workshop in September 1991 to define the parameters of the ESS. Participants in this workshop included both accelerator builders and neutron source users. A consortium of European countries has proposed to build a 5-MW pulsed source, and a feasibility study is currently under way. Soon after the birth of the ESS, a small group at ANL set about bringing themselves up to date on pulsed-source information since 1984 and studied the feasibility of upgrading ANL's Intense Pulsed Neutron Source (IPNS) to 1 MW by means of a rapidly cycling synchrotron that could be housed, along with its support facilities, in existing buildings. In early 1993, the Kohn panel recommended that (1) design and construction of the ANS should be completed according to the proposed project schedule and (2) development of competitive proposals for cost-effective design and construction of a 1-MW pulsed spallation source should be authorized immediately

  4. Direct containing heating experiments in Zion Nuclear Power Plant Geometry using prototypic core materials, the U1A and U1B tests

    International Nuclear Information System (INIS)

    Direct Containment Heating (DCH) experiments have been performed which utilize prototypic core materials. The experiments reported on here are a continuation of the Integral Effects Testing (IET) DCH program. The IET series of tests primarily addressed the effect of scale on DCH phenomena. This was accomplished by completing a series of counterpart tests in 1/40 and 1/10th linear scale DCH facilities at Argonne National Laboratory (ANL) and Sandia National Laboratories (SNL), respectively. The IET experiments modeled the Zion Nuclear Power Plant Geometry. The scale models included representations of the primary system volume, RPV lower head, cavity and instrument tunnel, and the lower containment structures. The experiments were steam driven at nominally 6.2 MPa. Iron-alumina thermite with chromium was used as a core melt simulant in the IET experiments. While the IET experiments at ANL and SNL provided useful data on the effect of scale on DCH phenomena, a significant question concerns the potential experiment distortions introduced by the use of non-prototypic iron/alumina thermite. Therefore, further testing with prototypic materials has been carried out at ANL. A prototypic core melt was produced for the experiments by first mixing powders of uranium, zirconium, iron oxide (Fe2O3), and chromium trioxide (CrO3). When ignited the powders react exothermically to produce a molten mixture. The amounts of each powder were selected to produce the anticipated composition for a core melt following a station blackout: 57.8 mass% UO2 10.5 mass% ZrO2 14.3 mass% Fe, 13.7 mass% Zr, and 3.7 mass% Cr. Development tests measured the initial melt temperature to be approximately 2700 K. The total thermal specific energy content of the melt at 2700 K is 1.2 MJ/kg compared to 2.25 MJ/kg for the iron-alumina simulant at its measured initial temperature of 2500 K

  5. Alkaline-Side Extraction of Cesium from Savannah River Tank Waste Using a Calixarene-Crown Ether Extractant

    Energy Technology Data Exchange (ETDEWEB)

    Bonnesen, P.V.; Delmau, L.H.; Haverlock, T.J.; Moyer, B.A.

    1998-12-01

    Results are presented supporting the viability of the alkaline-side CSEX process as a potential replacement for the In-Tank Precipitation process for removal of cesium from aqueous high-level waste (HLW) at the Savannah River Site (SRS). Under funding from the USDOE Efficient Separations and Crosscutting program, a flowsheet was suggested in early June of 1998, and in the following four months, this flowsheet underwent extensive testing, both in batch tests at ORNL and ANL and in two centrifugal-contactor tests at ANL. To carry out these tests, the initial ESP funding was augmented by direct funds from Westinghouse Savannah River Corporation. The flowsheet employed a solvent containing a calixarene-crown hybrid compound called BoBCalixC6 that was invented at ORNL and can now be obtained commercially for government use from IBC Advanced Technologies. This special extractant is so powerful and selective that it can be used at only 0.01 M, compensating for its expense, but a modifier is required for use in an aliphatic diluent, primarily to increase the cesium distribution ratio D{sub Cs} in extraction. The modifier selected is a relatively economical fluorinated alcohol called Cs3, invented at ORNL and so far available. only from ORNL. For the flowsheet, the modifier is used at 0.2 M in the branched aliphatic kerosene Isopar{reg_sign} L. Testing at ORNL and ANL involved simulants of the SRS HLW. After extraction of the Cs from the waste simulant, the solvent is scrubbed with 0.05 M HNO{sub 3} and stripped with a solution comprised of 0.0005 M HNO{sub 3} and 0.0001 M CsNO{sub 3}. The selection of these conditions is justified in this report, both on the basis of experimental data and underlying theory.

  6. 239 240Pu in Lake Michigan: 1971 to 1978

    International Nuclear Information System (INIS)

    The plutonium concentration data presented previously have consisted primarily of results from studies of short-term variations, i.e., the annual plutonium cycle conducted at Lake Michigan station ANL-5, 12 km SW of Grand Haven, Michigan. In this report, mean annual concentrations of total plutonium in unfiltered water from far off-shore (> 30 km) stations for the period 1971 through 1977, and from station ANL-5 (1975 through 1978) are summarized to establish the long-term trend in plutonium concentration in Lake Michigan. The results presented show that the mean annual concentration in the water column is similar at ANL-5 and at offshore stations and has decreased at the rate of only 6% per year during the period 1972 through 1978. The nearly constant concentration indicates that steady-state equilibria exist between plutonium inputs to the lake and the loss of plutonium from the water column. Observations suggest the existence of an active redox cycle for Pu in Lake Michigan. In this cycle, Pu IV atoms in solution are continually taken up by particulate materials but may be oxidized within microzones of the particles such as freshly deposited manganese coatings and also in solution by agents such as dissolved oxygen. In turn, the concentration of Pu VI in solution may be limited by reaction with reducing constituents of the coloidal-sized fraction (or decomposer organisms such as bacteria or fungi, which might have been present after filtration) and with planktonic organisms in the environment to produce Pu IV and thus maintain the cycle

  7. Recycle of LWR [Light Water Reactor] actinides to an IFR [Integral Fast Reactor

    International Nuclear Information System (INIS)

    A large quantity of actinide elements is present in irradiated Light Water Reactor (LWR) fuel that is stored throughout the world. Because of the high fission-to-capture ratio for the transuranium (TRU) elements with the high-energy neutrons in the metal-fueled Integral Fast Reactor (IFR), that reactor can consume these elements effectively. The stored fuel represents a valuable resource for an expanding application of fast power reactors. In addition, removal of the TRU elements from the spent LWR fuel has the potential for increasing the capacity of a high-level waste facility by reducing the heat loads and increasing the margin of safety in meeting licensing requirements. Argonne National Laboratory (ANL) is developing a pyrochemical process, which is compatible with the IFR fuel cycle, for the recovery of TRU elements from LWR fuel. The proposed product is a metallic actinide ingot, which can be introduced into the electrorefining step of the IFR process. The major objective of the LWR fuel recovery process is high TRU element recovery, with decontamination a secondary issue, because fission product removal is accomplished in the IFR process. The extensive pyrochemical processing studies of the 1960s and 1970s provide a basis for the design of possible processes. Two processes were selected for laboratory-scale investigation. One is based on the Salt Transport Process studied at ANL for mixed-oxide fast reactor fuel, and the other is based on the blanket processing studies done for ANL's second Experimental Breeder Reactor (EBR-2). This paper discusses the two processes and is a status report on the experimental studies. 5 refs., 2 figs., 2 tabs

  8. Tectonic evolution and paleogeography of the Kırşehir Block and the Central Anatolian Ophiolites, Turkey

    Science.gov (United States)

    Hinsbergen, Douwe J. J.; Maffione, Marco; Plunder, Alexis; Kaymakcı, Nuretdin; Ganerød, Morgan; Hendriks, Bart W. H.; Corfu, Fernando; Gürer, Derya; Gelder, Giovanni I. N. O.; Peters, Kalijn; McPhee, Peter J.; Brouwer, Fraukje M.; Advokaat, Eldert L.; Vissers, Reinoud L. M.

    2016-04-01

    In Central and Western Anatolia two continent-derived massifs simultaneously underthrusted an oceanic lithosphere in the Cretaceous and ended up with very contrasting metamorphic grades: high pressure, low temperature in the Tavşanlı zone and the low pressure, high temperature in the Kırşehir Block. To assess why, we reconstruct the Cretaceous paleogeography and plate configuration of Central Anatolia using structural, metamorphic, and geochronological constraints and Africa-Europe plate reconstructions. We review and provide new 40Ar/39Ar and U/Pb ages from Central Anatolian metamorphic and magmatic rocks and ophiolites and show new paleomagnetic data on the paleo-ridge orientation in a Central Anatolian Ophiolite. Intraoceanic subduction that formed within the Neotethys around 100-90 Ma along connected N-S and E-W striking segments was followed by overriding oceanic plate extension. Already during suprasubduction zone ocean spreading, continental subduction started. We show that the complex geology of central and southern Turkey can at first order be explained by a foreland-propagating thrusting of upper crustal nappes derived from a downgoing, dominantly continental lithosphere: the Kırşehir Block and Tavşanlı zone accreted around 85 Ma, the Afyon zone around 65 Ma, and Taurides accretion continued until after the middle Eocene. We find no argument for Late Cretaceous subduction initiation within a conceptual "Inner Tauride Ocean" between the Kırşehir Block and the Afyon zone as widely inferred. We propose that the major contrast in metamorphic grade between the Kırşehir Block and the Tavşanlı zone primarily results from a major contrast in subduction obliquity and the associated burial rates, higher temperature being reached upon higher subduction obliquity.

  9. Carnosine decreased neuronal cell death through targeting glutamate system and astrocyte mitochondrial bioenergetics in cultured neuron/astrocyte exposed to OGD/recovery.

    Science.gov (United States)

    Ouyang, Li; Tian, Yueyang; Bao, Yun; Xu, Huijuan; Cheng, Jiaoyan; Wang, Bingyu; Shen, Yao; Chen, Zhong; Lyu, Jianxin

    2016-06-01

    Previously, we showed that carnosine upregulated the expression level of glutamate transporter 1 (GLT-1), which has been recognized as an important participant in the astrocyte-neuron lactate shuttle (ANLS), with ischemic model in vitro and in vivo. This study was designed to investigate the protective effect of carnosine on neuron/astrocyte co-cultures exposed to OGD/recovery, and to explore whether the ANLS or any other mechanism contributes to carnosine-induced neuroprotection on neuron/astrocyte. Co-cultures were treated with carnosine and exposed to OGD/recovery. Cell death and the extracellular levels of glutamate and GABA were measured. The mitochondrial respiration and glycolysis were detected by Seahorse Bioscience XF96 Extracellular Flux Analyzer. Results showed that carnosine decreased neuronal cell death, increased extracellular GABA level, and abolished the increase in extracellular glutamate and reversed the mitochondrial energy metabolism disorder induced by OGD/recovery. Carnosine also upregulated the mRNA level of neuronal glutamate transporter EAAC1 at 2h after OGD. Dihydrokainate, a specific inhibitor of GLT-1, decreased glycolysis but it did not affect mitochondrial respiration of the cells, and it could not reverse the increase in mitochondrial OXPHOS induced by carnosine in the co-cultures. The levels of mRNAs for monocarboxylate transporter1, 4 (MCT1, 4), which were expressed in astrocytes, and MCT2, the main neuronal MCT, were significantly increased at the early stage of recovery. Carnosine only partly reversed the increased expression of astrocytic MCT1 and MCT4. These results suggest that regulating astrocytic energy metabolism and extracellular glutamate and GABA levels but not the ANLS are involved in the carnosine-induced neuroprotection. PMID:27040711

  10. Hydrological conditions at the 317/319 Area at Argonne National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Patton, T.L.; Pearl, R.H.; Tsai, S.Y.

    1990-08-01

    This study examined the hydrological conditions of the glacial till underlying the 317/319 Area at Argonne National Laboratory (ANL) near Lemont, Illinois. The study's purpose was to review and summarize hydrological data collected by ANL's Environment, Safety, and Health Department and to characterize, based on these data, the groundwater movement and migration of potential contaminants in the area. Recommendations for further study have been made based on the findings of this review. The 317/319 Area is located between Meridian Road and the southern border of ANL. The 317 Area was commissioned in the late 1940s for the temporary storage of radioactive waste. Low- and high-level solid radioactive waste is stored in partially buried concrete vaults. Low-level radioactive waste awaiting shipment for off-site disposal is stored in aboveground steel bins north of the vaults. The 319 Area is an inactive landfill, located east of the 317 Area that was used for the disposal of general refuse, demolition debris, and laboratory equipment. Fluorescent light bulbs, chemical containers, and suspect waste were also placed in the landfill. Liquid chemical wastes were disposed of at each site in gravel-filled trenches called French drains.'' The 317/319 Area is underlain by a silty clay glacial till. Dolomite bedrock underlies the till at an average depth of about 19.5m. Organic contaminants and radionuclides have been detected in groundwater samples from wells completed in the till. Fractures in the clay as well as sand and gravel lenses present in the till could permit these contaminants to migrate downward to the dolomite aquifer. At the time of this report, no chemical quality analyses had been made on groundwater samples from the dolomite. The study found that existing information about subsurface characteristics at the site is inadequate to identify potential pathways for contaminant migration. 14 refs., 13 figs., 6 tabs.

  11. NRC Job Code V6060: Extended in-situ and real time monitoring. Task 4: Detection and monitoring of leaks at nuclear power plants external to structures

    International Nuclear Information System (INIS)

    In support of Task 4 of the NRC study on compliance with 10 CFR part 20.1406, minimization of contamination, Argonne National Laboratory (ANL) conducted a one-year scoping study, in concert with a parallel study performed by NRC/NRR staff, on monitoring for leaks at nuclear power plants (NPPs) external to structures. The objective of this task-4 study is to identify and assess those sensors and monitoring techniques for early detection of abnormal radioactive releases from the engineered facility structures, systems and components (SSCs) to the surrounding underground environment in existing NPPs and planned new reactors. As such, methods of interest include: (1) detection of anomalous water content of soils surrounding SSCs, (2) radionuclides contained in the leaking water, and (3) secondary signals such as temperature. ANL work scope includes mainly to (1) identify, in concert with the nuclear industry, the sensors and techniques that have most promise to detect radionuclides and/or associated chemical releases from SSCs of existing NPPs and (2) review and provide comments on the results of the NRC/NRR staff scoping study to identify candidate technologies. This report constitutes the ANL deliverable of the task-4 study. It covers a survey of sensor technologies and leak detection methods currently applied to leak monitoring at NPPs. The survey also provides a technology evaluation that identifies their strength and deficiency based on their detection speed, sensitivity, range and reliability. Emerging advanced technologies that are potentially capable of locating releases, identifying the radionuclides, and estimating their concentrations and distributions are also included in the report along with suggestions of required further research and development.

  12. A comparative assessment of independent thermal-hydraulic models for research reactors: The RSG-GAS case

    Energy Technology Data Exchange (ETDEWEB)

    Chatzidakis, S., E-mail: schatzid@purdue.edu [Purdue University, School of Nuclear Engineering, West Lafayette, IN 47907 (United States); Hainoun, A. [Atomic Energy Commission of Syria (AECS), Nuclear Engineering Department, P.O. Box 6091, Damascus (Syrian Arab Republic); Doval, A. [Nuclear Engineering Department, Av. Cmdt. Luis Piedrabuena 4950, C.P. 8400, San Carlos de Bariloche, Rio Negro (Argentina); Alhabet, F. [Atomic Energy Commission of Syria (AECS), Nuclear Engineering Department, P.O. Box 6091, Damascus (Syrian Arab Republic); Francioni, F. [Nuclear Engineering Department, Av. Cmdt. Luis Piedrabuena 4950, C.P. 8400, San Carlos de Bariloche, Rio Negro (Argentina); Ikonomopoulos, A. [Institute of Nuclear and Radiological Sciences, Energy, Technology and Safety, National Center for Scientific Research ‘Demokritos’, 15130, Aghia Paraskevi, Athens (Greece); Ridikas, D. [Department of Nuclear Sciences and Applications, International Atomic Energy Agency, Vienna International Centre, A-1400 Vienna (Austria)

    2014-03-15

    Highlights: • Increased use of thermal-hydraulic codes requires assessment of important phenomena in RRs. • Three independent modeling teams performed analysis of loss of flow transient. • Purpose of this work is to examine the thermal-hydraulic codes response. • To perform benchmark analysis comparing the different codes with experimental measurements. • To identify the impact of the user effect on the computed results, performed with the same codes. - Abstract: This study presents the comparative assessment of three thermal-hydraulic codes employed to model the Indonesian research reactor (RSG-GAS) and simulate the reactor behavior under steady state and loss of flow transient (LOFT). The RELAP5/MOD3, MERSAT and PARET-ANL thermal-hydraulic codes are used by independent research groups to perform benchmark analysis against measurements of coolant and clad temperatures, conducted on an instrumented fuel element inside RSG-GAS core. The results obtained confirm the applicability of RELAP5/MOD3, MERSAT and PARET-ANL on the modeling of loss of flow transient in research reactors. In particular, the three codes are able to simulate flow reversal from downward forced to upward natural convection after pump trip and successful reactor scram. The benchmark results show that the codes predict maximum clad temperature of hot channel conservatively with a maximum overestimation of 27% for RELAP5/MOD3, 17% for MERSAT and 8% for PARET-ANL. As an additional effort, the impact of user effect on the simulation results has been assessed for the code RELAP5/MOD3, where the main differences among the models are presented and discussed.

  13. Practical superconductor development for electrical power applications: Quarterly report for the period ending December 31, 1999

    International Nuclear Information System (INIS)

    This is a multiyear experimental research program focused on improving relevant material properties of high-Tc superconductors (HTSS) and on development of fabrication methods that can be transferred to industry for production of commercial conductors. The development of teaming relationships through agreements with industrial partners is a key element of the Argonne (ANL) program. Recent results on substrate deposition for coated conductors, vortex studies, development of hardened Ag-alloy sheaths for powder-in-tube conductors, and sol-gel processing of NdBa2Cu3Ox (Nd-123) are presented

  14. Die Verständlichkeit von deutschen Fachtexten am Beispiel der SP

    DEFF Research Database (Denmark)

    Ditlevsen, Marianne Grove

    2000-01-01

    I bidraget henvises der til elementer i det tyske substantivsyntagme, som kunne have en negativ indflydelse på receptionen hos tysk-studerende med dansk som modersmål. Der anvendes en morfo-syntaktisk tilgang under inddragelse af leksikalske parametre. Eftersom det er problemer i receptionssituat...... receptionssituationen, der står i centrum, anlægges der i beskrivelsen et receptivt perspektiv. Derfor tages der i større grad end sædvanligt hensyn til signaler på overfladeplanet. Afslutningsvist behandles evt. konsekvenser for undervisningen i tysk som fremmedsprog....

  15. Tjetjenien-konflikten - Hvorfor?

    OpenAIRE

    Pedersen, Lars Barsalej; Rohde, Jeppe; Stukan, Anastassia; Strarup, Mads

    2005-01-01

    Rapporten beskæftiger sig med Tjetjenien-konflikten. Formålet med rapporten er først og fremmest at forstå konflikten. For dette er en politologisk og sociologisk vinkel blevet valgt. Vi beskæftiger os med etnicitet og sikkerhedsdynamikker, idet vi ønsker at undersøge om Tjetjenien har anlæg for selvstændighed, samt om dette er en politisk mulighed. Den sociologiske vinkel er repræsenteret ved Anthony Smiths ethnie-begreb og Benedict Anderson, som bliver sat op imod Smith. Den politologis...

  16. Die Asyldebatte in Deutschland : 20 Jahre nach dem "Asylkompromiss"

    OpenAIRE

    Cremer, Hendrik

    2013-01-01

    Der anlässlich des Weltflüchtlingstags am 20. Juni 2013 erschienene Essay kritisiert den Populismus in der Asyldebatte. Staatliche Akteure und die demokratischen Parteien in Bund, Ländern sowie Kommunen sollten sich dringend darauf verständigen, auch in der politischen Diskussion die menschen- und flüchtlingsrechtlichen Verpflichtungen zu beachten und keinesfalls Flüchtlinge pauschal zu verdächtigen und zu diskriminieren. Der Autor blickt auf die Asyldebatte Anfang der 1990er Jahre zurück und...

  17. Compilation of current high-energy-physics experiments

    International Nuclear Information System (INIS)

    This is the third edition of a compilation of current high energy physics experiments. It is a collaborative effort of the Berkeley Particle Data Group, the SLAC library, and ten participating laboratories: Argonne (ANL), Brookhaven (BNL), CERN, DESY, Fermilab (FNAL), the Institute for Nuclear Study, Tokyo (INS), KEK, Rutherford (RHEL), Serpukhov (SERP), and SLAC. The compilation includes summaries of all high energy physics experiments at the above laboratories that (1) were approved (and not subsequently withdrawn) before about January 1980, and (2) had not completed taking of data by 1 January 1976

  18. Compilation of current high-energy physics experiments

    International Nuclear Information System (INIS)

    This is the fourth edition of the compilation of current high energy physics experiments. It is a collaborative effort of the Berkeley Particle Data Group, the SLAC library, and nine participating laboratories: Argonne (ANL), Brookhaven (BNL), CERN, DESY, Fermilab (FNAL), the Institute for Nuclear Study, Tokyo (INS), KEK, Serpukhov (SERP), and SLAC. The compilation includes summaries of all high energy physics experiments at the above laboratories that (1) were approved (and not subsequently withdrawn) before about April 1981, and (2) had not completed taking of data by 1 January 1977. Only approved experiments are included

  19. Effects of Formvar coating and copper-nickel outer sheath on the ac losses of multi-strand subsize cables

    International Nuclear Information System (INIS)

    Ac losses of two subcables, one with Formvar coating on the strands of the BNL 12-ml NbTi/Cu/CuNi conductor and another without the coating, were measured using the ANL Subcable Test Facility. The results indicate that couplings among the strands with and without the Formvar coating were quite weak. Weak coupling of the bare strands is due to the high resistance of the copper-nickel outer sheath. In the regime of B(dot) = 0 approx. 1.2 T/s and B = 0 approx. 4 T, the magnetic diffusion time constant was (3.8 - 5.7) x 10-3 s

  20. Laser pulse amplification and dispersion compensation in an effectively extended optical cavity containing Bose-Einstein condensates

    OpenAIRE

    Sennaroğlu, Alphan; Müstecaplıoğlu, Özgür Esat; Tarhan, D.

    2013-01-01

    Laser pulse amplification and dispersion compensation in effectively extended optical cavity containing Bose-Einstein condensates D Tarhan1, A Sennaroglu2, ¨O E M¨ustecaplıo˘glu2 1Harran University, Department of Physics, 63300, S¸anlıurfa, Turkey 2Ko¸c University, Department of Physics, 34450, Sarıyer, Istanbul, Turkey E-mail: Abstract. We review and critically evaluate our proposal of a pulse amplification scheme based on two Bose-Einstein cond...