WorldWideScience

Sample records for facility investigation program

  1. Facilities Programming.

    Science.gov (United States)

    Bullis, Robert V.

    1992-01-01

    A procedure for physical facilities management written 17 years ago is still worth following today. Each of the steps outlined for planning, organizing, directing, controlling, and evaluating must be accomplished if school facilities are to be properly planned and constructed. However, lessons have been learned about energy consumption and proper…

  2. Investigating the Optimal Management Strategy for a Healthcare Facility Maintenance Program

    National Research Council Canada - National Science Library

    Gaillard, Daria

    2004-01-01

    ...: strategic partnering with an equipment management firm. The objective of this study is to create a decision-model for selecting the optimal management strategy for a healthcare organization's facility maintenance program...

  3. Surplus Facilities Management Program

    International Nuclear Information System (INIS)

    Coobs, J.H.

    1983-01-01

    This is the second of two programs that are concerned with the management of surplus facilities. The facilities in this program are those related to commercial activities, which include the three surplus experimental and test reactors [(MSRE, HRE-2, and the Low Intensity Test Reactor (LITR)] and seven experimental loops at the ORR. The program is an integral part of the Surplus Facilities Management Program, which is a national program administered for DOE by the Richland Operations Office. Very briefly reported here are routine surveillance and maintenance of surplus radioactively contaminated DOE facilities awaiting decommissioning

  4. Hanford Surplus Facilities Program plan

    International Nuclear Information System (INIS)

    Hughes, M.C.; Wahlen, R.K.; Winship, R.A.

    1989-09-01

    The Hanford Surplus Facilities Program is responsible for the safe and cost-effective surveillance, maintenance, and decommissioning of surplus facilities at the Hanford Site. The management of these facilities requires a surveillance and maintenance program to keep them in a safe condition and development of a plan for ultimate disposition. Criteria used to evaluate each factor relative to decommissioning are based on the guidelines presented by the US Department of Energy-Richland Operations Office, Defense Facilities Decommissioning Program Office, and are consistent with the Westinghouse Hanford Company commitment to decommission the Hanford Site retired facilities in the safest and most cost-effective way achievable. This document outlines the plan for managing these facilities to the end of disposition

  5. WIPP facility representative program plan

    International Nuclear Information System (INIS)

    1994-01-01

    This plan describes the Department of Energy (DOE), Carlsbad Area Office (CAO) facility representative (FR) program at the Waste Isolation Pilot Plant (WIPP). It provides the following information: (1) FR and support organization authorities and responsibilities; (2) FR program requirements; and (3) FR training and qualification requirements

  6. Investigation - Derived Waste Program

    International Nuclear Information System (INIS)

    Beardsley, C.; Anderson, R.

    1998-06-01

    The Investigation-Derived Waste Program is a software application that was developed to identify the groundwater monitoring wells at the Savannah River Site that require containerization and treatment for purge water generated during sampling

  7. A Program Management Framework for Facilities Managers

    Science.gov (United States)

    King, Dan

    2012-01-01

    The challenge faced by senior facility leaders is not how to execute a single project, but rather, how to successfully execute a large program consisting of hundreds of projects. Senior facilities officers at universities, school districts, hospitals, airports, and other organizations with extensive facility inventories, typically manage project…

  8. A research program to reduce interior noise in general aviation airplanes: Investigation of the characteristics of an acoustic panel test facility

    Science.gov (United States)

    Grosveld, F.; Vanaken, J.

    1978-01-01

    Sound pressure levels in the test facility were studied that are caused by varying: (1) microphone positions; (2) equalizer setting; and (3) panel clamping forces. Measurements were done by using a Beranek tube or this Beranek tube in combinations with an extension tube and a special test section. In all configurations tests were executed with and without a test panel installed. The influence of the speaker back panel and the back panel of the Beranek tube on the sound pressure levels inside the test tube were also investigated. It is shown that the definition of noise reduction is more useful in relation to this test facility than transmission loss.

  9. PANDA: A Multipurpose Integral Test Facility for LWR Safety Investigations

    International Nuclear Information System (INIS)

    Paladino, D.; Dreier, J.

    2012-01-01

    The PANDA facility is a large scale, multicompartmental thermal hydraulic facility suited for investigations related to the safety of current and advanced LWRs. The facility is multipurpose, and the applications cover integral containment response tests, component tests, primary system tests, and separate effect tests. Experimental investigations carried on in the PANDA facility have been embedded in international projects, most of which under the auspices of the EU and OECD and with the support of a large number of organizations (regulatory bodies, technical dupport organizations, national laboratories, electric utilities, industries) worldwide. The paper provides an overview of the research programs performed in the PANDA facility in relation to BWR containment systems and those planned for PWR containment systems.

  10. ORNL Isotopes Facilities Shutdown Program Plan

    International Nuclear Information System (INIS)

    Gibson, S.M.; Patton, B.D.; Sears, M.B.

    1990-10-01

    This plan presents the results of a technical and economic assessment for shutdown of the Oak Ridge National Laboratory (ORNL) isotopes production and distribution facilities. On December 11, 1989, the Department of Energy (DOE), Headquarters, in a memorandum addressed to DOE Oak Ridge Operations Office (DOE-ORO), gave instructions to prepare the ORNL isotopes production and distribution facilities, with the exception of immediate facility needs for krypton-85, tritium, and yttrium-90, for safe shutdown. In response to the memorandum, ORNL identified 17 facilities for shutdown. Each of these facilities is located within the ORNL complex with the exception of Building 9204-3, which is located at the Y-12 Weapons Production Plant. These facilities have been used extensively for the production of radioactive materials by the DOE Isotopes Program. They currently house a large inventory of radioactive materials. Over the years, these aging facilities have inherited the problems associated with storing and processing highly radioactive materials (i.e., facilities' materials degradation and contamination). During FY 1990, ORNL is addressing the requirements for placing these facilities into safe shutdown while maintaining the facilities under the existing maintenance and surveillance plan. The day-to-day operations associated with the surveillance and maintenance of a facility include building checks to ensure that building parameters are meeting the required operational safety requirements, performance of contamination control measures, and preventative maintenance on the facility and facility equipment. Shutdown implementation will begin in FY 1993, and shutdown completion will occur by the end of FY 1994

  11. Four critical facilities: their capabilities and programs

    International Nuclear Information System (INIS)

    Whitesides, G.E.

    1980-01-01

    Information is presented on the critical experiments facilities at Babcock and Wilcox, Lynchburg, Virginia; at Battelle Pacific Northwest Laboratory in Hanford, Washington; at Rockwell-International in Rocky Flats, Colorado; and at Los Alamos Scientific Laboratory in New Mexico. It is noted that the critical mass facilities which still exist in this country represent a bare minimum for maintaining a measurement program sufficient for meeting data requirements

  12. Quadrant I RCRA Facility Investigation Work Plan

    International Nuclear Information System (INIS)

    1990-01-01

    The objective of this Facility Investigation (FRI) at the Portsmouth Gaseous Diffusion Plant (PORTS) is to acquire, analyze and interpret data which will: (1) characterize the environmental setting including ground water, surface water and sediment, soil and air; (2) define and characterize sources of contamination; (3) characterize the vertical and horizontal extent and degree of contamination of the environment; (4) assess the risk to human health and the environment resulting from possible exposure to contaminants; and, (5) support the Corrective Measures Study (CMS) which will follow the RFI. Investigations to characterize the environmental setting, sources of contamination, and vertical and horizontal extent and degree of contamination will be conducted relative to individual potential sources which have been identified in the Quadrant I Description of Current Conditions. These unit investigations will follow the systematic approach which is outlined below

  13. INDICTORS OF RESTORATION OF PROGRAM FACILITY OF MECHATRONICS SYSTEM

    Directory of Open Access Journals (Sweden)

    V. Frolov

    2009-01-01

    Full Text Available The determination of reliability indictors of program facilities of mechatronic systems are offered. The defaillance modes of program facilities are represent. A short review of model reliability of program facility is presented. The indictors of restoration, their mathematical determinations and application for the characteristics of program facility restoration are offered.

  14. The NRU blowdown test facility commissioning program

    Energy Technology Data Exchange (ETDEWEB)

    Walsworth, J A; Zanatta, R J; Yamazaki, A R; Semeniuk, D D; Wong, W; Dickson, L W; Ferris, C E; Burton, D H [Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs.

    1990-12-31

    A major experimental program has been established at the Chalk River Nuclear Laboratories (CRL) that will provide essential data on the thermal and mechanical behaviour of nuclear fuel under abnormal reactor operating conditions and on the transient release, transport and deposition of fission product activity from severely degraded fuel. A number of severe fuel damage (SFD) experiments will be conducted within the Blowdown Test Facility (BTF) at CRL. A series of experiments are being conducted to commission this new facility prior to the SFD program. This paper describes the features and the commissioning program for the BTF. A development and testing program is described for critical components used on the reactor test section. In-reactor commissioning with a fuel assembly simulator commenced in 1989 June and preliminary results are given. The paper also outlines plans for future all-effects, in-reactor tests of CANDU-designed fuel. (author). 11 refs., 3 tabs., 7 figs.

  15. Clinical Investigation Program.

    Science.gov (United States)

    1985-10-01

    Tracheoesophageal Fistula: Diagnosis with CT. Pediatr Radiol 15:134-135, 1985 Sueoka BL, Johnson JF, Enzenauer RW, Kolina JS: Infantile Infectious Sacroiliitis...C) Stokes WS: Spontaneous Diabetes Mellitus in a Baboon (Papio anubis). 35th Annual Session, American Association for Laboratory Animal Science...Summary Sheet Prot No: 21H/85 Status: Ongoing TITLE: Efficacy of Cholestyramine in Acute Infantile Diarrhea Principal Investigator: CPT George M. Maher

  16. BWR Full Integral Simulation Test (FIST) program: facility description report

    International Nuclear Information System (INIS)

    Stephens, A.G.

    1984-09-01

    A new boiling water reactor safety test facility (FIST, Full Integral Simulation Test) is described. It will be used to investigate small breaks and operational transients and to tie results from such tests to earlier large-break test results determined in the TLTA. The new facility's full height and prototypical components constitute a major scaling improvement over earlier test facilities. A heated feedwater system, permitting steady-state operation, and a large increase in the number of measurements are other significant improvements. The program background is outlined and program objectives defined. The design basis is presented together with a detailed, complete description of the facility and measurements to be made. An extensive component scaling analysis and prediction of performance are presented

  17. The DOE/EM facility transition program

    International Nuclear Information System (INIS)

    Bixby, W.

    1994-01-01

    The mission of EM-60 is to plan, implement, and manage receipt of surplus facilities resulting from downsizing of the DOE Weapons Complex facilities and DOE operating program offices to EM, and to ensure prompt deactivation of such facilities in order to reach a minimum surveillance and maintenance condition. The revised organizational structure of EM-60 into four offices (one at headquarters, and the other three at field sites), reflects increased operating functions associated with deactivation, surveillance, and maintenance of facilities. EM-60's deactivation and transition role concerns technical, socioeconomic, institutional, and administrative issues. The primary objective of the deactivation process is to put facilities in the lowest surveillance and maintenance condition safely and quickly by driving down the open-quotes mortgageclose quotes costs of maintaining them until final disposition. EM-60's three key activities are: (1) Inventory of surplus facilities - The 1993 Surplus Facility Inventory and Assessment (SFIA) serves as a planning tool to help the Department and EM-60 determine optimal transition phasing, with safety and cost-effectiveness remaining a priority. (2) Management of accelerated facility life cycle transition - Transitions currently underway illustrate site issues. These include addressing the interests of federal and state regulatory agencies as well as interests of local stakeholders, safe management of large amounts of production residues, and options for treatment, storage, transportation, and disposal. Of equal importance in the transition process is planning the optimal transition of the labor force. (3) Economic development - to address the socio-economic impacts on affected communities of the severe and rapid downsizing of the DOE Weapons Complex, DOE is pursuing an approach that uses the land, equipment, technology assets, and highly skilled local workforces as a basis for alternative economic development

  18. The organization of ALARA program at a DOE facility

    International Nuclear Information System (INIS)

    Setaro, J.A.

    1992-01-01

    The organization of an ALARA Program at a DOE Facility (Oak Ridge National Laboratory), it's relationship with laboratory management, facility operators, and the radiation protection program is described. The use of chartered ALARA committees at two distinct levels is discussed

  19. Evaluation of Nuclear Facility Decommissioning Projects program

    International Nuclear Information System (INIS)

    Baumann, B.L.

    1983-01-01

    The objective of the Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program is to provide the NRC licensing staff with data which will allow an assessment of radiation exposure during decommissioning and the implementation of ALARA techniques. The data will also provide information to determine the funding level necessary to ensure timely and safe decommissioning operations. Actual decommissioning costs, methods and radiation exposures are compared with those estimated by the Battelle-PNL and ORNL NUREGs on decommissioning. Exposure reduction techniques applied to decommissioning activities to meet ALARA objectives are described. The lessons learned concerning various decommissioning methods are evaluated

  20. Critical experiments facility and criticality safety programs at JAERI

    International Nuclear Information System (INIS)

    Kobayashi, Iwao; Tachimori, Shoichi; Takeshita, Isao; Suzaki, Takenori; Miyoshi, Yoshinori; Nomura, Yasushi

    1985-10-01

    The nuclear criticality safety is becoming a key point in Japan in the safety considerations for nuclear installations outside reactors such as spent fuel reprocessing facilities, plutonium fuel fabrication facilities, large scale hot alboratories, and so on. Especially a large scale spent fuel reprocessing facility is being designed and would be constructed in near future, therefore extensive experimental studies are needed for compilation of our own technical standards and also for verification of safety in a potential criticality accident to obtain public acceptance. Japan Atomic Energy Research Institute is proceeding a construction program of a new criticality safety experimental facility where criticality data can be obtained for such solution fuels as mainly handled in a reprocessing facility and also chemical process experiments can be performed to investigate abnormal phenomena, e.g. plutonium behavior in solvent extraction process by using pulsed colums. In FY 1985 detail design of the facility will be completed and licensing review by the government would start in FY 1986. Experiments would start in FY 1990. Research subjects and main specifications of the facility are described. (author)

  1. National Ignition Facility Project Site Safety Program

    International Nuclear Information System (INIS)

    Dun, C

    2003-01-01

    This Safety Program for the National Ignition Facility (NIF) presents safety protocols and requirements that management and workers shall follow to assure a safe and healthful work environment during activities performed on the NIF Project site. The NIF Project Site Safety Program (NPSSP) requires that activities at the NIF Project site be performed in accordance with the ''LLNL ES and H Manual'' and the augmented set of controls and processes described in this NIF Project Site Safety Program. Specifically, this document: (1) Defines the fundamental NIF site safety philosophy. (2) Defines the areas covered by this safety program (see Appendix B). (3) Identifies management roles and responsibilities. (4) Defines core safety management processes. (5) Identifies NIF site-specific safety requirements. This NPSSP sets forth the responsibilities, requirements, rules, policies, and regulations for workers involved in work activities performed on the NIF Project site. Workers are required to implement measures to create a universal awareness that promotes safe practice at the work site and will achieve NIF management objectives in preventing accidents and illnesses. ES and H requirements are consistent with the ''LLNL ES and H Manual''. This NPSSP and implementing procedures (e.g., Management Walkabout, special work procedures, etc.,) are a comprehensive safety program that applies to NIF workers on the NIF Project site. The NIF Project site includes the B581/B681 site and support areas shown in Appendix B

  2. LBM program at the LOTUS facility

    International Nuclear Information System (INIS)

    File, J.; Haldy, P.A.; Jassby, D.L.; Leo, W.R.; Tsang, F.Y.

    1986-01-01

    The Ecole Polytechnique Federale de Lausanne's (EPFL's) LOTUS facility in Lausanne, Switzerland, consists of a point-neutron deuterium-tritium (D-T) source in a shielded room designed specifically for neutronics experiments with fusion blanket modules. In 1985 the Electric Power Research Institute and EPFL initiated an experimental neutron transport program using irradiation of the Lithium Blanket Module (LBM) by the LOTUS neutron source. The principal objectives of this program are: (a) to test the capability of present-day neutron transport codes to predict the neutronic performance, including tritium breeding, of a reactor-representative blanket module in a relatively simple fast-neutron field and (b) to develop and verify the measurement and data processing procedures that will be used eventually with the LBM experiments at the Tokamak Fusion Test Reactor (TFTR) at Princeton Plasma Physics Lab. (PPPL)

  3. The Pinellas Plant RCRA facility investigation - A case study

    International Nuclear Information System (INIS)

    Kilbury, Richard; Keshian, Berg; Farley, Dwain; Meyer, David; Ingle, David; Biedermann, Charles

    1992-01-01

    Under the direction of the U.S. Department of Energy Albuquerque Field Office Environmental Restoration Program, a Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) was completed at the Pinellas Plant to fulfill requirements of the Hazardous and Solid Waste Amendments of 1984 (HSWA) permit issued on February 9, 1990 by the U.S. Environmental Protection Agency (EPA). This RFI addressed potential contaminant releases and environmental conditions at 15 solid waste management units (SWMUs). The RFI characterization program began in April 1990 and was completed in May 1991. The scope of RFI data collection activities is presented in the Pinellas Plant RFI Workplan issued in May 1990 and approved by EPA on April 16, 1991. An RFI Report was submitted to EPA on September 1, 1991. This paper presents a summary of RFI results and conclusions. Primary environmental concerns at the Pinellas Plant are emphasized. (author)

  4. Review of the Advanced Toroidal Facility program

    International Nuclear Information System (INIS)

    Lyon, J.F.; Murakami, M.

    1987-01-01

    This report summarizes the history and design goals of the Advanced Toroidal Facility (ATF). The ATF is nearing completion at ORNL with device completion expected in May 1987 and first useful plasma operation in June/July 1987. ATF is a moderate-aspect-ratio torsatron, the world's largest stellarator facility with R = 2.1 m, α bar = 0.3 m and B = 2 T (5-s pulse) or 1 T (steady-state capability). It has been specifically designed to support the US tokamak program by studying important toroidal confinement issues in a similar magnetic geometry that allows external control of the magnetic configuration properties and their radial profiles: transform, shear, well depth, shaping, axis topology, etc. ATF will operate in a current-free model which allows separation of current-driven and pressure-driven plasma behavior. It also complements the world stellarator program in its magnetic configuration (between Heliotron-E and W VII-AS) and its capabilities (large size, good access, steady state capability, second stability access, etc.). For both roles ATF will require high-power long-pulse heating to carry out its physics goals since the high power NBI pulse is limited to 0.3 s. The ATF program focuses on demonstrating the principles of high-beta, steady-state operation in toroidal geometry through its study of: (1) scaling of beta limits with magnetic configuration properties and the plasma behavior in the second stability regime; (2) transport scaling at low collisionality and the role/control of electric field; (3) control of plasma density and impurities using divertors; (4) plasma heating with NBI, ECH, ICH, and plasma fueling with gas puffing and pellet injection; and (5) optimization of the magnetic configuration

  5. Investigation of analytical and experimental behavior of nuclear facility ventilation systems

    International Nuclear Information System (INIS)

    Smith, P.R.; Ricketts, C.I.; Andrae, R.W.; Bolstad, J.W.; Horak, H.L.; Martin, R.A.; Tang, P.K.; Gregory, W.S.

    1979-01-01

    The behavior of nuclear facility ventilation systems subjected to both natural and man-caused accidents is being investigated. The purpose of the paper is to present a program overview and highlight recent results of the investigations. The program includes both analytical and experimental investigations. Computer codes for predicting accident-induced gas dynamics and test facilities to obtain supportive experimental data to define structural integrity and confinement effectiveness of ventilation system components are described. A unique test facility and recently obtained structural limits for high efficiency particulate air filters are reported

  6. Molecular Contamination Investigation Facility (MCIF) Capabilities

    Science.gov (United States)

    Soules, David M.

    2013-01-01

    This facility was used to guide the development of ASTM E 1559 center dot Multiple Quartz Crystal Microbalances (QCMs), large sample and spectral effects capability center dot Several instrumented, high vacuum chamber systems are used to evaluate the molecular outgassing characteristics of materials, flight components and other sensitive surfaces. Test materials for spacecraft/instrument selection center.Test flight components for acceptable molecular outgas levels center dot Determine time/temperature vacuum bake-out requirements center. Data used to set limits for use of materials and specific components center. Provide Input Data to Contamination Transport Models -Applied to numerous flight projects over the past 20 years.

  7. 77 FR 55843 - Office of Facilities Management and Program Services; Submission for OMB Review; Background...

    Science.gov (United States)

    2012-09-11

    ... of Facilities Management and Program Services; Submission for OMB Review; Background Investigations for Child Care Workers AGENCY: Office of Facilities Management and Program Services, Public Building... Act, the Regulatory Secretariat will be submitting to the Office of Management and Budget (OMB) a...

  8. Experimental program at the LOTUS facility

    International Nuclear Information System (INIS)

    Azam, S.; Haldy, P.A.; Kumar, A.; Leo, W.R.; Sahraoui, C.; Schneeberger, J.P.; Tsang, F.; Green, L.

    1986-01-01

    The objectives of the LOTUS experimental program are to study, from a neutronics point of view, blanket modules having features representative of conceptual fusion reactor blanket designs. Such small-scale generic experiments should help to eliminate possible blind alleys, and thus save much time and money later when commercial-size devices will be constructed. At present, two different types of blanket designs are being studied at the LOTUS facility. The first one represents a hybrid fission-suppressed blanket developed at IGA. It is a parallelepiped-shaped assembly, with a fissile breeding zone made of aluminum-clad thorium oxide rods, and a tritium breeding zone simulated by lithium carbonate compressed powder in aluminum boxes. The second blanket that is currently being tested at IGA is the Lithium Blanket Module (LBM) developed by PPPL under the sponsorship of the Electric Power Research Institute. Essentially, the same kind of experiments will be carried out in all the blanket modules. Measurement of foil activities as well as tritium production in the blanket are the primary diagnostic means in the current LOTUS experimental program. Preanalyses of the experimental data have been carried out at IGA with the help of the two-dimensional discrete ordinates transport code DOT3.5 coupled to the GRTUNCL first collision routine. For the experiments described above, the agreement between experimental and computed results is generally fair

  9. Experimental facilities for plate-out investigations and future work

    International Nuclear Information System (INIS)

    Muenchow, K.; Dederichs, H.; Iniotakis, N.; Sackmann, B.

    1981-01-01

    The safety of HTR under normal operation and accident conditions, the possibility of inspection, maintenance and repair or decontamination of single primary components as well as the safety of maintenance personnel are essentially determined by the transport- and deposition behaviour of the non gaseous fission - and activation products in the primary loop of the reactor. A comprehensive program has been started in 1969 in KFA in collaboration with various industrial firms and foreign institutions to investigate these problems. The program includes in-pile and out-pile experiments, simulating reactor conditions and also different laboratory experiments and extensive theoretical investigations. The aim of these efforts is to test experimentally the models and computercodes, which are used for prediction of transport and deposition behaviour of fission products for HTR's as well under normal as under accident conditions. Further more a verified dataset is to be established. In this paper a survey is given of the experimental facilities carried out by KFA or in cooperation with KFA

  10. 200 Area Liquid Effluent Facilities -- Quality assurance program plan

    International Nuclear Information System (INIS)

    Fernandez, L.

    1995-01-01

    This Quality Assurance Program Plan (QAPP) describes the quality assurance and management controls used by the 200 Area Liquid Effluent Facilities (LEF) to perform its activities in accordance with DOE Order 5700.6C. The 200 Area LEF consists of the following facilities: Effluent Treatment Facility (ETF); Treated Effluent Disposal Facility (TEDF); Liquid Effluent Retention facility (LERF); and Truck Loading Facility -- (Project W291). The intent is to ensure that all activities such as collection of effluents, treatment, concentration of secondary wastes, verification, sampling and disposal of treated effluents and solids related with the LEF operations, conform to established requirements

  11. Review of biological monitoring programs at nuclear facilities

    International Nuclear Information System (INIS)

    Quintana, L.R.; Oakes, T.W.; Shank, K.E.

    Biological monitoring programs, as well as relevant radioecological research studies, are reviewed at specific Department of Energy facilities; the program at Oak Ridge National Laboratory is discussed in detail. The biological measurements that are being used for interpreting the impact of a facility on its surrounding environment and nearby population are given. Suggestions which could facilitate interlaboratory comparison studies are presented

  12. Facility certification program for coal miners pneumoconiosis

    International Nuclear Information System (INIS)

    Trout, E.D.; Kelley, J.P.; Larson, V.L.; Herbert, G.L.

    1976-01-01

    Public Law 91-173, often referred to as the Black Lung Law, called for a chest radiograph of all active coal miners at stated intervals. The National Institute for Occupational Safety and Health was responsible for carrying out the provisions of the law. Among other requirements was a provision for certification of radiological facilities where radiological examinations would be provide. A test object to be radiographed by each such facility was designed and sent to those facilities applying for certification. To date, 284 facilities have applied for certification of which 215 have been approved. A record has been kept of the number of times any approved facility submitted radiographs before approval. A complete listing of the types of equipment used, personnel qualifications and other pertinent data will be reported

  13. Feasibility Investigation for a Solar Power Generation Facility

    Science.gov (United States)

    Nathan, Lakshmi

    2010-01-01

    The Energy Policy Act of 2005 states that by fiscal year 2013, at least 7.5% of the energy consumed by the government must be renewable energy. In an effort to help meet this goal, Johnson Space Center (JSC) is considering installing a solar power generation facility. The purpose of this project is to conduct a feasibility investigation for such a facility. Because Kennedy Space Center (KSC) has a solar power generation facility, the first step in this investigation is to learn about KSC's facility and obtain information on how it was constructed. After collecting this information, the following must be determined: the amount of power desired, the size of the facility, potential locations for it, and estimated construction and maintenance costs. Contacts with JSC's energy provider must also be established to determine if a partnership would be agreeable to both parties. Lastly, all of this data must be analyzed to decide whether or not JSC should construct the facility. The results from analyzing the data collected indicate that a 200 kW facility would provide enough energy to meet 1% of JSC's energy demand. This facility would require less than 1 acre of land. In the map below, potential locations are shown in green. The solar power facility is projected to cost $2 M. So far, the information collected indicates that such a facility could be constructed. The next steps in this investigation include contacting JSC's energy provider, CenterPoint Energy, to discuss entering a partnership; developing a life cycle cost analysis to determine payback time; developing more detailed plans; and securing funding.

  14. Fast reactor test facilities in the US safety program

    International Nuclear Information System (INIS)

    Avery, R.; Dickerman, C.E.; Lennox, D.H.; Rose, D.

    1979-01-01

    The needs for safety information derivable from in-pile programs are reviewed, and the correlation made with existing and planned capability. In view of the current status of the U.S. breeder program, emphasis is given in the review to the impact of different fast breeder options on the required program and facilities. It is concluded that facility needs are somewhat independent of specific fast breeder concept, even though the relative emphasis on the various safety issues will differ. 8 refs

  15. The role of SANRAD facility in quantitative and morphological investigation

    International Nuclear Information System (INIS)

    Nshimirimana, Robert; Beer, Frikkie de; Radebe, Mabuti

    2011-01-01

    The SANRAD (South African Neutron Radiography) facility hosts a neutron/X-ray tomography system, which is extensively being utilized in non-destructive examination experiments where it is necessary to determine the properties (e.g. size, porosity, permeability and morphology) of samples. Those properties have a great importance in a variety of fields such as nuclear shielding, paleontology, geosciences, anatomy and reverse engineering studies. Quantitative and morphological investigations require a tomography system capable of producing tomograms with a high spatial resolution and free of artefacts where specialized imaging software is applied in the investigations. The SANRAD facility is used by the scientific and engineering communities in their qualitative, quantitative and morphological investigations. The capability of the SANRAD facility to investigate qualitatively and quantitatively the internal structure of several objects non-destructively is demonstrated with special emphasis on the precision and accuracy of the system.

  16. Effective flow-accelerated corrosion programs in nuclear facilities

    International Nuclear Information System (INIS)

    Esselman, Thomas C.; McBrine, William J.

    2004-01-01

    Piping Flow-Accelerated Corrosion Programs in nuclear power generation facilities are classically comprised of the selection of inspection locations with the assistance of a predictive methodology such as the Electric Power Research Institute computer codes CHECMATE or CHECWORKS, performing inspections, conducting structural evaluations on the inspected components, and implementing the appropriate sample expansion and corrective actions. Performing such a sequence of steps can be effective in identifying thinned components and implementing appropriate short term and long term actions necessary to resolve flow-accelerated corrosion related problems. A maximally effective flow-accelerated corrosion (FAC) program requires an understanding of many programmatic details. These include the procedural control of the program, effective use of historical information, managing the activities performed during a limited duration outage, allocating resources based on risk allocation, having an acute awareness of how the plant is operated, investigating components removed from the plant, and several others. This paper will describe such details and methods that will lead to a flow-accelerated corrosion program that effectively minimizes the risk of failure due to flow-accelerated corrosion and provide full and complete documentation of the program. (author)

  17. RCRA Facility Investigation/Remedial Investigation Report for the Grace Road Site (631-22G)

    Energy Technology Data Exchange (ETDEWEB)

    Palmer, E.

    1998-10-02

    This report summarizes the activities and documents the results of a Resource Conservation and Recovery Act Facility Investigation/Remedial Investigation conducted at Grace Road Site on the Savannah River Site near Aiken, South Carolina.

  18. RCRA Facility Investigation/Remedial Investigation Report for the Grace Road Site (631-22G)

    International Nuclear Information System (INIS)

    Palmer, E.

    1998-01-01

    This report summarizes the activities and documents the results of a Resource Conservation and Recovery Act Facility Investigation/Remedial Investigation conducted at Grace Road Site on the Savannah River Site near Aiken, South Carolina

  19. Measurement control program at model facility

    International Nuclear Information System (INIS)

    Schneider, R.A.

    1984-01-01

    A measurement control program for the model plant is described. The discussion includes the technical basis for such a program, the application of measurement control principles to each measurement, and the use of special experiments to estimate measurement error parameters for difficult-to-measure materials. The discussion also describes the statistical aspects of the program, and the documentation procedures used to record, maintain, and process the basic data

  20. FY11 Facility Assessment Study for Aeronautics Test Program

    Science.gov (United States)

    Loboda, John A.; Sydnor, George H.

    2013-01-01

    This paper presents the approach and results for the Aeronautics Test Program (ATP) FY11 Facility Assessment Project. ATP commissioned assessments in FY07 and FY11 to aid in the understanding of the current condition and reliability of its facilities and their ability to meet current and future (five year horizon) test requirements. The principle output of the assessment was a database of facility unique, prioritized investments projects with budgetary cost estimates. This database was also used to identify trends for the condition of facility systems.

  1. Liquid Metal Fast Breeder Reactor Program: Argonne facilities

    International Nuclear Information System (INIS)

    Stephens, S.V.

    1976-09-01

    The objective of the document is to present in one volume an overview of the Argonne National Laboratory test facilities involved in the conduct of the national LMFBR research and development program. Existing facilities and those under construction or authorized as of September 1976 are described. Each profile presents brief descriptions of the overall facility and its test area and data relating to its experimental and testing capability. The volume is divided into two sections: Argonne-East and Argonne-West. Introductory material for each section includes site and facility maps. The profiles are arranged alphabetically by title according to their respective locations at Argonne-East or Argonne-West. A glossary of acronyms and letter designations in common usage to describe organizations, reactor and test facilities, components, etc., involved in the LMFBR program is appended

  2. Environmental restoration plan for the transfer of surplus facilities to the Facility Transition Program at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    1995-08-01

    This report will provide guidance on management, coordination, and integration of plans to transition facilities to the Facility Transition Program and activities as related to the Oak Ridge National Laboratory (ORNL) Environmental Restoration Program facilities. This report gives (1) guidance on the steps necessary for identifying ORNL surplus facilities, (2) interfaces of Surveillance and Maintenance (S and M) and Isotope Facility Deactivation program managers, (3) roles and responsibilities of the facility managers, and (4) initial S and M requirements upon acceptance into the Facility Transition Program

  3. 5 CFR 1636.150 - Program accessibility: Existing facilities.

    Science.gov (United States)

    2010-01-01

    ... fundamental alteration in the nature of a program or activity or in undue financial and administrative burdens... facilities. 1636.150 Section 1636.150 Administrative Personnel FEDERAL RETIREMENT THRIFT INVESTMENT BOARD ENFORCEMENT OF NONDISCRIMINATION ON THE BASIS OF HANDICAP IN PROGRAMS OR ACTIVITIES CONDUCTED BY THE FEDERAL...

  4. 12 CFR 410.150 - Program accessibility: Existing facilities.

    Science.gov (United States)

    2010-01-01

    ... 12 Banks and Banking 4 2010-01-01 2010-01-01 false Program accessibility: Existing facilities. 410.150 Section 410.150 Banks and Banking EXPORT-IMPORT BANK OF THE UNITED STATES ENFORCEMENT OF NONDISCRIMINATION ON THE BASIS OF HANDICAP IN PROGRAMS OR ACTIVITIES CONDUCTED BY EXPORT-IMPORT BANK OF THE UNITED...

  5. 45 CFR 2490.150 - Program accessibility: Existing facilities.

    Science.gov (United States)

    2010-10-01

    ... 45 Public Welfare 4 2010-10-01 2010-10-01 false Program accessibility: Existing facilities. 2490.150 Section 2490.150 Public Welfare Regulations Relating to Public Welfare (Continued) JAMES MADISON... ACTIVITIES CONDUCTED BY THE JAMES MADISON MEMORIAL FELLOWSHIP FOUNDATION § 2490.150 Program accessibility...

  6. 49 CFR 28.150 - Program accessibility: Existing facilities.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 1 2010-10-01 2010-10-01 false Program accessibility: Existing facilities. 28.150 Section 28.150 Transportation Office of the Secretary of Transportation ENFORCEMENT OF NONDISCRIMINATION ON THE BASIS OF HANDICAP IN PROGRAMS OR ACTIVITIES CONDUCTED BY THE DEPARTMENT OF TRANSPORTATION § 28...

  7. Risk management program for the 283-W water treatment facility

    International Nuclear Information System (INIS)

    Green, W.E.

    1999-01-01

    This Risk Management (RM) Program covers the 283-W Water Treatment Facility (283W Facility), located in the 200 West Area of the Hanford Site. A RM Program is necessary for this facility because it stores chlorine, a listed substance, in excess of or has the potential to exceed the threshold quantities defined in Title 40 of the Code of Federal Regulations (CFR) Part 68 (EPA, 1998). The RM Program contains data that will be used to prepare a RM Plan, which is required by 40 CFR 68. The RM Plan is a summary of the RM Program information, contained within this document, and will be submitted to the U.S. Environmental Protection Agency (EPA) ultimately for distribution to the public. The RM Plan will be prepared and submitted separately from this document

  8. Study on Nuclear Facility Cyber Security Awareness and Training Programs

    International Nuclear Information System (INIS)

    Lee, Jung-Woon; Song, Jae-Gu; Lee, Cheol-Kwon

    2016-01-01

    Cyber security awareness and training, which is a part of operational security controls, is defined to be implemented later in the CSP implementation schedule. However, cyber security awareness and training is a prerequisite for the appropriate implementation of a cyber security program. When considering the current situation in which it is just started to define cyber security activities and to assign personnel who has responsibilities for performing those activities, a cyber security awareness program is necessary to enhance cyber security culture for the facility personnel to participate positively in cyber security activities. Also before the implementation of stepwise CSP, suitable education and training should be provided to both cyber security teams (CST) and facility personnel who should participate in the implementation. Since such importance and urgency of cyber security awareness and training is underestimated at present, the types, trainees, contents, and development strategies of cyber security awareness and training programs are studied to help Korean nuclear facilities to perform cyber security activities more effectively. Cyber security awareness and training programs should be developed ahead of the implementation of CSP. In this study, through the analysis of requirements in the regulatory standard RS-015, the types and trainees of overall cyber security training programs in nuclear facilities are identified. Contents suitable for a cyber security awareness program and a technical training program are derived. It is suggested to develop stepwise the program contents in accordance with the development of policies, guides, and procedures as parts of the facility cyber security program. Since any training programs are not available for the specialized cyber security training in nuclear facilities, a long-term development plan is necessary. As alternatives for the time being, several cyber security training courses for industrial control systems by

  9. Study on Nuclear Facility Cyber Security Awareness and Training Programs

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jung-Woon; Song, Jae-Gu; Lee, Cheol-Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    Cyber security awareness and training, which is a part of operational security controls, is defined to be implemented later in the CSP implementation schedule. However, cyber security awareness and training is a prerequisite for the appropriate implementation of a cyber security program. When considering the current situation in which it is just started to define cyber security activities and to assign personnel who has responsibilities for performing those activities, a cyber security awareness program is necessary to enhance cyber security culture for the facility personnel to participate positively in cyber security activities. Also before the implementation of stepwise CSP, suitable education and training should be provided to both cyber security teams (CST) and facility personnel who should participate in the implementation. Since such importance and urgency of cyber security awareness and training is underestimated at present, the types, trainees, contents, and development strategies of cyber security awareness and training programs are studied to help Korean nuclear facilities to perform cyber security activities more effectively. Cyber security awareness and training programs should be developed ahead of the implementation of CSP. In this study, through the analysis of requirements in the regulatory standard RS-015, the types and trainees of overall cyber security training programs in nuclear facilities are identified. Contents suitable for a cyber security awareness program and a technical training program are derived. It is suggested to develop stepwise the program contents in accordance with the development of policies, guides, and procedures as parts of the facility cyber security program. Since any training programs are not available for the specialized cyber security training in nuclear facilities, a long-term development plan is necessary. As alternatives for the time being, several cyber security training courses for industrial control systems by

  10. Program of radiological monitoring environmental a nuclear facility in latency

    International Nuclear Information System (INIS)

    Blas, A. de; Riego, A.; Batalla, E.; Tapia, C.; Garcia, R.; Sanchez, J.; Toral, J.

    2013-01-01

    This paper presents the Radiological Environmental Monitoring program of the Vandellos I nuclear power plant in the latency period. This facility was dismantled to level 2, as defined by the International Atomic Energy Agency. The program is an adaptation of the implanted one during the dismantling, taking into account the isotopes that may be present, as well as the main transfer routes. Along with the description of the program the results obtained in the latent period from 2005 until 2012 are presented.

  11. Nuclear criticality safety program at the Fuel Cycle Facility

    International Nuclear Information System (INIS)

    Lell, R.M.; Fujita, E.K.; Tracy, D.B.; Klann, R.T.; Imel, G.R.; Benedict, R.W.; Rigg, R.H.

    1994-01-01

    The Fuel Cycle Facility (FCF) is designed to demonstrate the feasibility of a novel commercial-scale remote pyrometallurgical process for metallic fuels from liquid metal-cooled reactors and to show closure of the Integral Fast Reactor (IFR) fuel cycle. Requirements for nuclear criticality safety impose the most restrictive of the various constraints on the operation of FCF. The upper limits on batch sizes and other important process parameters are determined principally by criticality safety considerations. To maintain an efficient operation within appropriate safety limits, it is necessary to formulate a nuclear criticality safety program that integrates equipment design, process development, process modeling, conduct of operations, a measurement program, adequate material control procedures, and nuclear criticality analysis. The nuclear criticality safety program for FCF reflects this integration, ensuring that the facility can be operated efficiently without compromising safety. The experience gained from the conduct of this program in the Fuel cycle Facility will be used to design and safely operate IFR facilities on a commercial scale. The key features of the nuclear criticality safety program are described. The relationship of these features to normal facility operation is also described

  12. Environmental monitoring program for nuclear facilities

    International Nuclear Information System (INIS)

    Roenick, R.G.; Kreter, R.N.

    1984-01-01

    The programs aims to determine the area of largest environmental impact, taking into consideration the various installations in the Resende Industrial Complex. In the present work a mathematical model is applied based on regional data, and after the study of the use of land and waster resources in the area. The work, begin two years before the operation of the installation, has been subsequently modified by the environmental analyses obtained. The background levels of integrated dose are determined, and all the pollutents existing in the air, land and water have been classified, with the object of characterizing the region 20 Kilometers around the nuclear installation. (Author) [pt

  13. RCRA Facility Investigation/Remedial Investigation Report with Baseline Risk Assessment for the Fire Department Hose Training Facility (904-113G)

    Energy Technology Data Exchange (ETDEWEB)

    Palmer, E. [Westinghouse Savannah River Company, AIKEN, SC (United States)

    1997-04-01

    This report documents the Resource Conservation and Recovery Act (RCRA) Facility Investigation/Remedial Investigation/Baseline Risk Assessment (RFI/RI/BRA) for the Fire Department Hose Training Facility (FDTF) (904-113G).

  14. 77 FR 31017 - Office of Facilities Management and Program Services; Information Collection; Background...

    Science.gov (United States)

    2012-05-24

    ... 3090-0287, Background Investigations for Child Care Workers. Instructions: Please submit comments only... request for review and approval for background check investigations of child care workers, form GSA 176C... Child Care Workers AGENCY: Office of Facilities Management and Program Services, Public Building Service...

  15. Investigating the Importance of Sports Facilities & Staff for Football Fans

    Directory of Open Access Journals (Sweden)

    Pinelopi Athanasopoulou

    2012-01-01

    Full Text Available (a Purpose: This study seeks to investigate the importance of facilities and staff for football fans in Greece. (b Design/methodology/approach: A survey was carried out during two matches of Superleague games with a convenience sample of 312 spectators. A structured questionnaire was used with scales based on previous research. (c Findings: Factor analysis revealed four reliable factor dimensions: facilities design; staff; facilities maintenance, and quick & easy access. Staff and quick & easy access are shown to be the most important dimensions for respondents followed by the other two. Results also indicated that there are significant differences in the importance assigned to these 4 factor dimensions among different levels of age; education; income, and marital status. (d Research limitations/implications: This study is limited to one sport and on a convenience sample of football fans. Future research can validate further these findings and increase their generalisability. (e Practical implications: The results of this study challenge sport managers to manage effectively the design of the stadium; the processes of entry and exit of fans; the environment of the game; and the quality of stadium facilities.

  16. Hanford Site waste tank farm facilities design reconstitution program plan

    International Nuclear Information System (INIS)

    Vollert, F.R.

    1994-01-01

    Throughout the commercial nuclear industry the lack of design reconstitution programs prior to the mid 1980's has resulted in inadequate documentation to support operating facilities configuration changes or safety evaluations. As a result, many utilities have completed or have ongoing design reconstitution programs and have discovered that without sufficient pre-planning their program can be potentially very expensive and may result in end-products inconsistent with the facility needs or expectations. A design reconstitution program plan is developed here for the Hanford waste tank farms facility as a consequence of the DOE Standard on operational configuration management. This design reconstitution plan provides for the recovery or regeneration of design requirements and basis, the compilation of Design Information Summaries, and a methodology to disposition items open for regeneration that were discovered during the development of Design Information Summaries. Implementation of this plan will culminate in an end-product of about 30 Design Information Summary documents. These documents will be developed to identify tank farms facility design requirements and design bases and thereby capture the technical baselines of the facility. This plan identifies the methodology necessary to systematically recover documents that are sources of design input information, and to evaluate and disposition open items or regeneration items discovered during the development of the Design Information Summaries or during the verification and validation processes. These development activities will be governed and implemented by three procedures and a guide that are to be developed as an outgrowth of this plan

  17. Forensic investigation of suicide cases in major Greek correctional facilities.

    Science.gov (United States)

    Sakelliadis, E I; Vlachodimitropoulos, D G; Goutas, N D; Panousi, P I; Logiopoulou, A-P I; Delicha, E M; Spiliopoulou, C A

    2013-11-01

    According to Greek legislation the medico-legal investigation of deaths occurring in prisons is mandatory. Furthermore, in cases of suicide or of suspected suicide the contribution of medico-legal investigation is of grave importance. The current paper addresses the medico-legal investigation of suicide cases in Greek correctional facilities and aims to describe the current situation. Our study consists of the meticulous research in the data records of major Greek correctional facilities, for the time period 1999-2010. Official permission was obtained by the Hellenic Ministry of Justice, which provided us the access to the records. Data was also collected from the Piraeus Forensic Service, from the Department of Pathological Anatomy of the University of Athens and finally from our own records. Measures were taken to respect the anonymity of the cases. Data was collected for the social, penal, medical history as well as for the medico-legal investigation. It appears that 85.7% of suicide cases were transferred to the Prisoner's Hospital (p < 0.0001), the forensic pathologist who conducted the PME did not perform scene investigation in none of the 70 suicide cases. In a total of 70 cases, histopathological examination, was requested only in 30 cases (42.9%). Hanging was the preferred method for those who committed suicide, followed by the poisoning due to psychoactive substances. Understanding the mistakes made during the forensic investigation of suicide cases inside correctional facilities is necessary, in order to prevent them from occurring again in the future, by implementing appropriate new policies and guidelines. Crown Copyright © 2013. Published by Elsevier Ltd. All rights reserved.

  18. Developing a model lifeline protection program for DOE facilities

    International Nuclear Information System (INIS)

    Lowing, A.N.

    1996-01-01

    A National Lifeline Standard Development Program is currently being conducted by FEMA and NIST. The Department of Energy is following these developments and supplementing them to meet Life-Safety and mission requirements for all DOE facilities as part of the Natural Phenomena Hazards Mitigation Plan. The task will be overseen by a DOE management team with technical guidance provided by a Steering Group of management and operating contractor representatives. The DOE will participate in the federal program by conducting a workshop on lifeline protection issues, developing an overall plan, organizing a Steering Group, and conducting a pilot study at a DOE facility

  19. Transuranic waste management program and facilities

    International Nuclear Information System (INIS)

    Clements, T.L. Jr.; Cook, L.A.; Stallman, R.M.; Hunter, E.K.

    1986-01-01

    Since 1954, defense-generated transuranic (TRU) waste has been received at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). Prior to 1970, approximately 2.2 million cubic feet of transuranic waste were buried in shallow-land trenches and pits at the RWMC. Since 1970, an additional 2.1 million cubic feet of waste have been retrievably stored in aboveground engineered confinement. A major objective of the Department of Energy (DOE) Nuclear Waste Management Program is the proper management of defense-generated transuranic waste. Strategies have been developed for managing INEL stored and buried transuranic waste. These strategies have been incorporated in the Defense Waste Management Plan and are currently being implemented with logistical coordination of transportation systems and schedules for the Waste Isolation Pilot Plant (WIPP). The Stored Waste Examination Pilot Plant (SWEPP) is providing nondestructive examination and assay of retrievably stored, contact-handled TRU waste. Construction of the Process Experimental Pilot Plant (PREPP) was recently completed, and PREPP is currently undergoing system checkout. The PRFPP will provide processing capabilities for contact-handled waste not meeting WIPP-Waste Acceptance Criteria (WAC). In addition, ongoing studies and technology development efforts for managing the TRU waste such as remote-handled and buried TRU waste, are being conducted

  20. Transuranic Waste Management Program and Facilities

    International Nuclear Information System (INIS)

    Clements, T.L. Jr.; Cook, L.A.; Stallman, R.M.; Hunter, E.K.

    1986-02-01

    Since 1954, defense-generated transuranic (TRU) waste has been received at the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). Prior to 1970, approximately 2.2 million cubic feet of transuranic waste were buried in shallow-land trenches and pits at the RWMC. Since 1970, an additional 2.1 million cubic feet of waste have been retrievably stored in aboveground engineered confinement. A major objective of the Department of Energy (DOE) Nuclear Waste Management Program is the proper management of defense-generated transuranic waste. Strategies have been developed for managing INEL stored and buried transuranic waste. These strategies have been incorporated in the Defense Waste Management Plan and are currently being implemented with logistical coordination of transportation systems and schedules for the Waste Isolation Pilot Plant (WIPP). The Stored Waste Examination Pilot Plant (SWEPP) is providing nondestructive examination and assay of retrievably stored, contact-handled TRU waste. Construction of the Process Experimental Pilot Plant (PREPP) was recently completed, and PREPP is currently undergoing system checkout. The PREPP will provide processing capabilities for contact-handled waste not meeting WIPP-Waste Acceptance Criteria (WAC). In addition, ongoing studies and technology development efforts for managing the TRU waste such as remote-handled and buried TRU waste, are being conducted

  1. A simulation based research on chance constrained programming in robust facility location problem

    Directory of Open Access Journals (Sweden)

    Kaijun Leng

    2017-03-01

    Full Text Available Since facility location decisions problem include long-term character and potential parameter variations, it is important to consider uncertainty in its modeling. This paper examines robust facility location problem considering supply uncertainty, in which we assume the supply of the facility in the actual operation is not equal to the supply initially established, the supply is subject to random fluctuation. The chance constraints are introduced when formulating the robust facility location model to make sure the system operate properly with a certain probability while the supply fluctuates. The chance constraints are approximated safely by using Hoeffding’s inequality and the problem is transformed to a general deterministic linear programming. Furthermore, how the facility location cost change with confidence level is investigated through a numerical example. The sensitivity analysis is conducted for important parameters of the model and we get the main factors that affect the facility location cost.

  2. Characterization of mixed waste for shipment to TSD Facilities Program

    International Nuclear Information System (INIS)

    Chandler, K.; Goyal, K.

    1995-01-01

    In compliance with the Federal Facilities Compliance Agreement, Los Alamos National Laboratory (LANL) is striving to ship its low-level mixed waste (LLMW) off-site for treatment and disposal. In order to ship LLMW off site to a commercial facility, LANL must request exemption from the DOE Order 5820.2A requirement that LLMW be shipped only to Department of Energy facilities. Because the process of obtaining the required information and approvals for a mixed waste shipment campaign can be very expensive, time consuming, and frustrating, a well-planned program is necessary to ensure that the elements for the exemption request package are completed successfully the first time. LANL has developed such a program, which is cost- effective, quality-driven, and compliance-based. This program encompasses selecting a qualified analytical laboratory, developing a quality project-specific sampling plan, properly sampling liquid and solid wastes, validating analytical data, documenting the waste characterization and decision processes, and maintaining quality records. The products of the program are containers of waste that meet the off-site facility's waste acceptance criteria, a quality exemption request package, documentation supporting waste characterization, and overall quality assurance for the process. The primary goal of the program is to provide an avenue for documenting decisions, procedures, and data pertinent to characterizing waste and preparing it for off-site treatment or disposal

  3. Investigation on calibration parameter of mammography calibration facilities at MINT

    International Nuclear Information System (INIS)

    Asmaliza Hashim; Wan Hazlinda Ismail; Md Saion Salikin; Muhammad Jamal Md Isa; Azuhar Ripin; Norriza Mohd Isa

    2004-01-01

    A mammography calibration facility has been established in the Medical Physics Laboratory, Malaysian Institute for Nuclear Technology Research (MINT). The calibration facility is established at the national level mainly to provide calibration services for radiation measuring test instruments or test tools used in quality assurance programme in mammography, which is being implemented in Malaysia. One of the accepted parameters that determine the quality of a radiation beam is the homogeneity coefficient. It is determined from the values of the 1 st and 2 nd Half Value Layer (HVL). In this paper, the consistency of the mammography machine beam qualities that is available in MINT, is investigated and presented. For calibration purposes, five radiation qualities namely 23, 25, 28, 30 and 35 kV, selectable from the control panel of the X-ray machine is used. Important parameters that are set for this calibration facility are exposure time, tube current, focal spot to detector distance (FDD) and beam size at specific distance. The values of homogeneity coefficient of this laboratory for the past few years tip to now be presented in this paper. Backscatter radiations are also considered in this investigation. (Author)

  4. CEBAF [Continuous Electron Beam Accelerator Facility] scientific program

    International Nuclear Information System (INIS)

    Gross, F.

    1986-01-01

    The principal scientific mission of the Continuous Electron Beam Facility (CEBAF) is to study collective phenomena in cold (or normal) nucler matter in order to understand the structure and behavior of macroscopic systems constructed from nuclei. This document discusses in broad popular terms those issues which the CEBAF experimental and theoretical program are designed to address. Specific experimental programs currently planned for CEBAF are also reivewed. 35 refs., 19 figs

  5. Gas storage facilities. Investigation of their social value. Supplement

    International Nuclear Information System (INIS)

    1997-02-01

    The socio-economic factors resulting from location of gas storage facilities are evaluated. Various alternatives to the existing projects are estimated, for instance 11 new pipelines, in some cases combined with new production capacity, LNG facilities, differentiated tariffs, reconstruction of decentralized heat/power plants etc. Theoretical considerations and models, among others involving gas storage abroad, are presented. Seasonal storage, emergency storage, storage controlled by economic optimization (profitable purchases, sales at highest market) are described for various types of facilities, like aquifers, caverns and LNG-stores. Natural gas supplies in Europe, infrastructure and resources are compared to the Danish conditions. Sensitivity of the Danish heating market for natural gas consumption is investigated. Reduction in energy use for space heating by 2005 will change the needs of storage of 740 Mm 3 gas to 650 Mm 3 . Extra consumption by the decentralized power/heat plants is not accounted for in this estimation. Dynamic models of the future gas consumption are based on the EU 'European Energy 2020'. (EG)

  6. Gas storage facilities. Investigation of their social value

    International Nuclear Information System (INIS)

    1997-02-01

    The socio-economic factors resulting from location of gas storage facilities are evaluated. Various alternatives to the existing projects are estimated, for instance 11 new pipelines, in some cases combined with new production capacity, LNG facilities, differentiated tariffs, reconstruction of decentralized heat/power plants etc. Theoretical considerations and models, among others involving gas storage abroad, are presented. Seasonal storage, emergency storage, storage controlled by economic optimization (profitable purchases, sales at highest market) are described for various types of facilities, like aquifers, caverns and LNG-stores. Natural gas supplies in Europe, infrastructure and resources are compared to the Danish conditions. Sensitivity of the Danish heating market for natural gas consumption is investigated. Reduction in energy use for space heating by 2005 will change the needs of storage of 740 Mm 3 gas to 650 Mm 3 . Extra consumption by the decentralized power/heat plants is not accounted for in this estimation. Dynamic models of the future gas consumption are based on the EU 'European Energy 2020'. (EG)

  7. Progress and problems in the Formerly Utilized Sites Remedial Action Program and Surplus Facilities Management Program

    International Nuclear Information System (INIS)

    Fiore, J.J.; Turi, G.P.

    1988-01-01

    The Formerly Utilized Sites Remedial Action Program (FUSRAP) was established in 1974 to identify, evaluate, and as appropriate, conduct remedial actions at sites used in the early years of nuclear energy development by the Manhattan Engineer District and the Atomic Energy Commission (AEC). This program currently has 29 sites and is evaluating 350 other sites for possible inclusion in the program. Another remedial action program in the Department of Energy's (DOE) Division of Facility and Site Decommissioning Projects is the Surplus Facilities Management Program (SFMP). The SFMP involves the safe management, decontamination and disposal of surplus DOE contaminated facilities which were not related to defense activities. There are currently 33 projects at 15 different sites in the program. These two programs have made steady progress over the last 10 or so years in cleaning up sites so that they can be reused or released for unrestricted use. Work has been completed at 8 of the FUSRAP sites and three of the SFMP sites

  8. Radiologic safety program for ionizing radiation facilities in Parana, Brazil

    International Nuclear Information System (INIS)

    Schmidt, M.F.S.; Tilly Junior, J.G.

    1997-01-01

    A radiologic safety program for inspection, licensing and control of the use of ionizing radiation in medical, industrial and research facilities in Parana, Brazil is presented. The program includes stages such as: 1- division into implementation phases considering the activity development for each area; 2-use of the existing structure to implement and to improve services. The development of the program will permit to evaluate the improvement reached and to correct operational strategic. As a result, a quality enhancement at the services performed, a reduction for radiation dose exposure and a faster response for emergency situations will be expected

  9. Site investigations for the disposal of spent fuel - investigation program

    International Nuclear Information System (INIS)

    Aeikaes, Timo

    1985-11-01

    The Industrial Power Company Ltd (TVO) is making preparations for the final disposal of spent nuclear fuel into the Finnish bedrock. The revised site investigation program for the years 1986-2010 is presented in this report. The objectives and activities in the near future are described in more detail. The main objectives and frame programs for the investigations in the more distant future are described. The program planning of these investigations are being developed in the preceding site investigations. The investigations for the site selection are divided into four phases: 1983-1985 selection of the investigation areas, preparations for the field investigations, drilling and investigations in a deep test borehole; 1986-1992 preliminary site investigations in 5-10 investigation areas; 1993-2000 detailed site investigations in 2-3 investigation areas. Site selection in the year 2000; 2001-2010 complementary investigations on the selected site. The first investigation phase will be carried out as planned. In this phase a 1001 m deep test borehole was drilled at Lavia in western Finland. With the investigations in the borehole and related development work, preparations were made for the future field investigations. The equipment and investigation methods are being developed during the site investigations. The equipment for taking groundwater samples and the unit for hydraulic testing have been developed. In the future the emphasis in the work will be in developing equipment for monitoring of the hydraulic head and measuring the volumetric flow. In groundwater sampling the present procedure can be improved by adding the test for the in-situ measurements. The results of the field investigations will be stored and processed in a centralized data base. The data base will transmit the results for the interpretation and then the interpreted results transmitted for model calculations and reporting. The cost estimate for the investigations in 1986-2010 is 110-125 million

  10. Intense neutron source facility for the fusion energy program

    International Nuclear Information System (INIS)

    Armstrong, D.D.; Emigh, C.R.; Meier, K.L.; Meyer, E.A.; Schneider, J.D.

    1975-01-01

    The intense neutron source is based on the ability of a supersonic flow of gas to dissipate an enormous quantity of heat generated in the neutron-producing target by multiple Coulomb collisions. A description is given of the principles involved in forming the supersonic jet, in forming the intense tritium-ion beam, in the vacuum systems, and in the tritium handling systems. An overview of the entire facility is included. It is believed that the facility can be operated with high reliability, ensuring a productive radiation damage program. (U.S.)

  11. Microdosimetric investigations at the fast neutron therapy facility at Fermilab

    International Nuclear Information System (INIS)

    Langen, K.M.

    1997-01-01

    Microdosimetry was used to investigate three issues at the neutron therapy facility (NTF) at Fermilab. Firstly, the conversion factor from absorbed dose in A-150 tissue equivalent plastic to absorbed dose in ICRU tissue was determined. For this, the effective neutron kerma factor ratios, i.e., oxygen tissue equivalent plastic and carbon to A-150 tissue equivalent plastic, were measured in the neutron beam. An A-150 tissue equivalent plastic to ICRU tissue absorbed dose conversion factor of 0.92 ± 0.04 was determined. Secondly, variations in the radiobiological effectiveness (RBE) in the beam were mapped by determining variations in two related quantities, e * and R, with field size and depth in tissue. Maximal variation in e * and R of 9% and 15% respectively were determined. Lastly, the feasibility of utilizing the boron neutron capture reaction on boron-10 to selectively enhance the tumor dose in the NTF beam was investigated

  12. Clinical Investigation Program Annual Progress Report

    Science.gov (United States)

    1993-09-30

    The assigned staff of the Molecular Biology Service are Dr. Anthony G. Gutierrez , Chef , GSl3, Ph. D. in Molecular Genetics, and Ms. Judith O’Brien...Node-Negative Breast Cancer Patients Using a Panel of Prognostic Factors. A Companion Protocol to SWOG 8897 ................................ . 103 91...of Prog- nostic Factors. A companion protocol to 8897 (5) Start Date: 1991 (6) Est Compl Date: (7) Principal Investigator: (8) Facility: FAMC Thomas

  13. Waste immobilization demonstration program for the Hanford Site's Mixed Waste Facility

    International Nuclear Information System (INIS)

    Burbank, D.A.; Weingardt, K.M.

    1994-05-01

    This paper presents an overview of the Waste Receiving and Processing facility, Module 2A> waste immobilization demonstration program, focusing on the cooperation between Hanford Site, commercial, and international participants. Important highlights of the development and demonstration activities is discussed from the standpoint of findings that have had significant from the standpoint of findings that have had significant impact on the evolution of the facility design. A brief description of the future direction of the program is presented, with emphasis on the key aspects of the technologies that call for further detailed investigation

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

    International Nuclear Information System (INIS)

    Majka, Z.

    2011-01-01

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

  15. Full-scale mark II CRT program facility description report

    International Nuclear Information System (INIS)

    Namatame, Ken; Kukita, Yutaka; Ito, Hideo; Yamamoto, Nobuo; Shiba, Masayoshi

    1980-03-01

    Started in fiscal year 1977, the Full-Scale Mark II CRT (Containment Response Test) Program is proceeding for the period of five years. The primary objective of the CRT Program is to provide a data base for evaluation of the pressure suppression pool hydrodynamic loads associated with a postulated loss-of-coolant accident in the BWR Mark II containment system. The test facility was designed and constructed from fiscal year 1977 to 1978, and completed in March 1979. It is 1/18 in volume and has a wetwell which is a full-scale replica of one 20 0 -sector of that of a reference Mark II. This report describes design concepts, dimensions and constructions of the test facility, as well as specifications, locations and installation schemes of the measuring equipments. Results of soil structure inspection, vacuum breaker test and shaker test of the containment shell are given in the appendices. (author)

  16. Use of the UFTR facilities for precollege nuclear education programs

    International Nuclear Information System (INIS)

    Vernetson, W.G.

    1992-01-01

    The University of Florida Training Reactor (UFTR) is a 100-kW light water-cooled, graphite- and light water-moderated modified Argonaut-type reactor, which currently utilizes high enriched (93%) fuel. Since first being licensed to operate at 10 kW in 1959, this facility has had major involvement in college and university level education and research programs both at the University of Florida and at other post-secondary schools around the state of Florida. Utility operator training programs were also a major facility involvement until recent years when the advent of site-specific simulators reduced UFTR usage for such training. Although sometimes not user friendly for innovative research and maintenance programs, the UFTR is an excellent educational and training tool. Service work for outside vendors representing a full spectrum of the nuclear industry has also been significant, especially in the last 15 yr. In contrast, there was little UFTR involvement in precollege education programs prior to 1984. Since that time, the US Dept. of Energy's University Reactor Sharing Program has been a catalyst for developing diverse utilization of the UFTR by both outside educational institutions throughout the state of Florida and faculty members within the University of Florida. With a decline in usage in the early 1980s, the UFTR was in danger of going the way of so many university reactor facilities. The availability of the Reactor Sharing Program has contributed significantly to educational and research opportunities at all levels around the state. Initially, those uses were almost exclusively at the college level. However, the synergistic effects of the internal and external user communities are primarily responsible for the resurgence in usage of the UFTR over the past 8 yr, despite a steady decline in utility operator training

  17. Dosimetry program for characterization of the FMIT facility

    International Nuclear Information System (INIS)

    Gold, R.; McElroy, W.N.; Fuller, J.L.; Sheen, E.M.; Dierckx, R.

    1979-01-01

    The environmental characterization program for the Fusion Materials Irradiaton Test (FMIT) facility is presented. Requirements for the development and testing of Magnetic Fusion Energy (MFE) materials together with the complexity of the FMIT (d,Li) generated radiation field warrant a multifaceted dosimetric approach. Specific passive, active and calculational dosimetry efforts comprising this multifaceted approach are described. Special emphasis is given to those dosimetry capabilities uniquely required to characterize FMIT

  18. `Climate wise` program at the Cosmair, Inc. Clark Manufacturing Facility

    Energy Technology Data Exchange (ETDEWEB)

    Kraly, K.

    1997-12-31

    Viewgraphs from the conference presentation are reproduced in this paper, which outlines energy efficiency improvements and emissions reductions at a hair care products manufacturing facility. Program management focuses on employee involvement in internal audits, utility tracking, public relations, and preventative maintenance. Energy savings, cost savings, and emission reductions are presented for 1996 and projected to the year 2000. Other program aspects outlined include a summary of utility costs; solid waste; chilled water system modifications; lighting modifications; boiler upgrades; and heating, ventilating, and air conditioning improvements.

  19. Laser programs facility management plan for environment, safety, and health

    International Nuclear Information System (INIS)

    Cruz, G.E.

    1996-01-01

    The Lawrence Livermore National Laboratory's (LLNL) Laser Programs ES ampersand H policy is established by the Associate Director for Laser Programs. This FMP is one component of that policy. Laser Programs personnel design, construct and operate research and development equipment located in various Livermore and Site 300 buildings. The Programs include a variety of activities, primarily laser research and development, inertial confinement fusion, isotope separation, and an increasing emphasis on materials processing, imaging systems, and signal analysis. This FMP is a formal statement of responsibilities and controls to assure operational activities are conducted without harm to employees, the general public, or the environment. This plan identifies the hazards associated with operating a large research and development facility and is a vehicle to control and mitigate those hazards. Hazards include, but are not limited to: laser beams, hazardous and radioactive materials, criticality, ionizing radiation or x rays, high-voltage electrical equipment, chemicals, and powered machinery

  20. YALINA facility a sub-critical Accelerator- Driven System (ADS) for nuclear energy research facility description and an overview of the research program (1997-2008).

    Energy Technology Data Exchange (ETDEWEB)

    Gohar, Y.; Smith, D. L.; Nuclear Engineering Division

    2010-04-28

    The YALINA facility is a zero-power, sub-critical assembly driven by a conventional neutron generator. It was conceived, constructed, and put into operation at the Radiation Physics and Chemistry Problems Institute of the National Academy of Sciences of Belarus located in Minsk-Sosny, Belarus. This facility was conceived for the purpose of investigating the static and dynamic neutronics properties of accelerator driven sub-critical systems, and to serve as a neutron source for investigating the properties of nuclear reactions, in particular transmutation reactions involving minor-actinide nuclei. This report provides a detailed description of this facility and documents the progress of research carried out there during a period of approximately a decade since the facility was conceived and built until the end of 2008. During its history of development and operation to date (1997-2008), the YALINA facility has hosted several foreign groups that worked with the resident staff as collaborators. The participation of Argonne National Laboratory in the YALINA research programs commenced in 2005. For obvious reasons, special emphasis is placed in this report on the work at YALINA facility that has involved Argonne's participation. Attention is given here to the experimental program at YALINA facility as well as to analytical investigations aimed at validating codes and computational procedures and at providing a better understanding of the physics and operational behavior of the YALINA facility in particular, and ADS systems in general, during the period 1997-2008.

  1. Russian Federal nuclear center facilities for nuclear spectroscopy investigations

    International Nuclear Information System (INIS)

    Ilkaev, R.I.; Punin, V.T.; Abramovich, S.N.

    2001-01-01

    Russian Federal Nuclear Center facilities for Spectroscopy investigation in the field of nuclear spectroscopy are described. Here are discussed basic properties of used radiation sources, facilities and technologies for target material production and manufacture of targets from rare, high-toxic or radioactive materials. Here are also reported basic features of complex detector systems and technologies for manufacture of scintillation detectors with special properties VNIIEF was founded as a weapons laboratory. The development of nuclear and thermonuclear bombs was followed by a wide complex of nuclear-physics investigations. Naturally, data on nuclear-physics properties of active and structure materials being part of nuclear weapons were of greatest interest.At the initial stage of work on the development of nuclear weapons the information on nuclear constants of materials including the most important neutron ones was rather scant. Data published in scientific literature had low exactness and were insecure. Results of measurements sometimes differed greatly by various groups of investigators. At the same time it was clear that, for example, a 1,5-times mistake in the fission cross-section could cause a several times mistake in the choice of uranium or plutonium mass, which is necessary for the bomb development. These circumstances determined importance of the nuclear-physics investigations. Demands on knowledge of process details occurring inside the nuclei conditioned by a problem of developing and improving of nuclear weapons and atomic power are rather limited. However, the further development of nuclear industry has proved a well-known point that this knowledge being accumulated forms a critical mass that leads to an explosive situation in the elaboration both of ideological and technological aspects of these problems. It is the tendency of inside development of nuclear science that has conditioned preparedness of knowledge about intranuclear processes for

  2. Assessment of the facilities on Jackass Flats and other Nevada Test Site facilities for the new nuclear rocket program

    International Nuclear Information System (INIS)

    Chandler, G.; Collins, D.; Dye, K.; Eberhart, C.; Hynes, M.; Kovach, R.; Ortiz, R.; Perea, J.; Sherman, D.

    1992-01-01

    Recent NASA/DOE studies for the Space Exploration Initiative have demonstrated a critical need for the ground-based testing of nuclear rocket engines. Experience in the ROVER/NERVA Program, experience in the Nuclear Weapons Testing Program, and involvement in the new nuclear rocket program has motivated our detailed assessment of the facilities used for the ROVER/NERVA Program and other facilities located at the Nevada Test Site (NTS). The ROVER/NERVA facilities are located in the Nevada Research L, Development Area (NRDA) on Jackass Flats at NTS, approximately 85 miles northwest of Las Vegas. To guide our assessment of facilities for an engine testing program we have defined a program goal, scope, and process. To execute this program scope and process will require ten facilities. We considered the use of all relevant facilities at NTS including existing and new tunnels as well as the facilities at NRDA. Aside from the facilities located at remote sites and the inter-site transportation system, all of the required facilities are available at NRDA. In particular we have studied the refurbishment of E-MAD, ETS-1, R-MAD, and the interconnecting railroad. The total cost for such a refurbishment we estimate to be about $253M which includes additional contractor fees related to indirect, construction management, profit, contingency, and management reserves. This figure also includes the cost of the required NEPA, safety, and security documentation

  3. Investigations concerning fire-induced accidents in nuclear facilities

    International Nuclear Information System (INIS)

    Lamuth, P.; Lernout, L.A.; Bonneval, F.; Cottaz, M.

    1996-01-01

    In the context of fire protection in technical buildings of French nuclear facilities, three principles have been adopted: prevention, detection and fire-fighting. Their implementation makes it possible on the one hand to limit the fire ignition and the fire growth, and on the other hand to prevent fire extent which would lead to unavailability of several safety related equipment. Although progress has been made in this direction, the fire risks have still not been eliminated. It is therefore essential to evaluate the fire effects and to assess their consequences. To this end, three main R and D programs have been conducted into fires. Part I sets out the fire PSA methodology used for a 900 MWe PWR. Part II gives an outline of two fire and ventilation computer codes useful for the fire PSA. Finally, part III gives an outline of the tests already performed and those currently under way in the two laboratories of the Institut de Protection et de Surete Nucleaire (IPSN) in order to qualify the codes and provide useful information for the safety assessment. (author)

  4. Radiation safety program in a high dose rate brachytherapy facility

    International Nuclear Information System (INIS)

    Rodriguez, L.V.; Hermoso, T.M.; Solis, R.C.

    2001-01-01

    The use of remote afterloading equipment has been developed to improve radiation safety in the delivery of treatment in brachytherapy. Several accidents, however, have been reported involving high dose-rate brachytherapy system. These events, together with the desire to address the concerns of radiation workers, and the anticipated adoption of the International Basic Safety Standards for Protection Against Ionizing Radiation (IAEA, 1996), led to the development of the radiation safety program at the Department of Radiotherapy, Jose R. Reyes Memorial Medical Center and at the Division of Radiation Oncology, St. Luke's Medical Center. The radiation safety program covers five major aspects: quality control/quality assurance, radiation monitoring, preventive maintenance, administrative measures and quality audit. Measures for evaluation of effectiveness of the program include decreased unnecessary exposures of patients and staff, improved accuracy in treatment delivery and increased department efficiency due to the development of staff vigilance and decreased anxiety. The success in the implementation required the participation and cooperation of all the personnel involved in the procedures and strong management support. This paper will discuss the radiation safety program for a high dose rate brachytherapy facility developed at these two institutes which may serve as a guideline for other hospitals intending to install a similar facility. (author)

  5. The BNL Accelerator Test Facility and experimental program

    International Nuclear Information System (INIS)

    Ben-Zvi, I.; State Univ. of New York, Stony Brook, NY

    1992-01-01

    The Accelerator Test Facility (ATF) at BNL is a users' facility for experiments in Accelerator and Beam Physics. The ATF provides high brightness electron beams and high-power laser pulses synchronized to the electron beam, suitable for studies of new methods of high-gradient acceleration and state-of-the-art Free-Electron Lasers. The electrons are produced by a laser photocathode rf gun and accelerated to 50 MeV by two traveling wave accelerator sections. The lasers include a 10 mJ, 10 ps ND:YAG laser and a 500 mJ, 10 to 100 ps C0 2 laser. A number of users from National Laboratories, universities and industry take part in experiments at the ATF. The experimental program includes various laser acceleration schemes, Free-Electron Laser experiments and a program on the development of high-brightness electron beams. The ATF's experimental program commenced in early 1991 at an energy of about 4 MeV. The full program, with 50 MeV and the high-power laser will begin operation this year

  6. The BNL Accelerator Test Facility and experimental program

    International Nuclear Information System (INIS)

    Ben-Zvi, I.; State Univ. of New York, Stony Brook, NY

    1991-01-01

    The Accelerator Test Facility (ATF) at BNL is a users' facility for experiments in Accelerator and Beam Physics. The ATF provides high brightness electron beams and high power laser pulses synchronized to the electron beam, suitable for studies of new methods of high gradient acceleration and state of the art free electron lasers. The electrons are produced by a laser photocathode rf gun and accelerated to 50 to 100 MeV by two traveling wave accelerator sections. The lasers include a 10 mJ, 10 ps Nd:YAG laser and a 100 mJ, 10 ps CO 2 laser. A number of users from National Laboratories, universities and industry take part in experiments at the ATF. The experimental program includes various acceleration schemes, Free-Electron Laser experiments and a program on the development of high brightness electron beams. The AFT's experimental program commenced in early 1991 at an energy of about 4 MeV. The full program, with 50 MeV and the High power laser will begin operation this year. 28 refs., 4 figs

  7. 75 FR 18850 - National Protection and Programs Directorate; Chemical Facility Anti-Terrorism Standards...

    Science.gov (United States)

    2010-04-13

    ... Directorate; Chemical Facility Anti-Terrorism Standards Personnel Surety Program AGENCY: National Protection...-terrorism Vulnerability Information (CVI), Sensitive Security Information (SSI), or Protected Critical... . SUPPLEMENTARY INFORMATION: Program Description The Chemical Facility Anti-Terrorism Standards (CFATS), 6 CFR...

  8. An Empirical Investigation into Programming Language Syntax

    Science.gov (United States)

    Stefik, Andreas; Siebert, Susanna

    2013-01-01

    Recent studies in the literature have shown that syntax remains a significant barrier to novice computer science students in the field. While this syntax barrier is known to exist, whether and how it varies across programming languages has not been carefully investigated. For this article, we conducted four empirical studies on programming…

  9. Practical approaches to implementing facility wide equipment strengthening programs

    International Nuclear Information System (INIS)

    Kincaid, R.H.; Smietana, E.A.

    1989-01-01

    Equipment strengthening programs typically focus on components required to ensure operability of safety related equipment or to prevent the release of toxic substances. Survival of non-safety related equipment may also be crucial to ensure rapid recovery and minimize business interruption losses. Implementing a strengthening program for non-safety related equipment can be difficult due to the large amounts of equipment involved and limited budget availability. EQE has successfully implemented comprehensive equipment strengthening programs for a number of California corporations. Many of the lessons learned from these projects are applicable to DOE facilities. These include techniques for prioritizing equipment and three general methodologies for anchoring equipment. Pros and cons of each anchorage approach are presented along with typical equipment strengthening costs

  10. 235U Holdup Measurement Program in support of facility shutdown

    International Nuclear Information System (INIS)

    Thomason, R.S.; Griffin, J.C.; Lien, O.G.; McElroy, R.D.

    1991-01-01

    In 1989, the Department of Energy directed shutdown of an enriched uranium processing facility at Savannah River Site. As part of the shutdown requirements, deinventory and cleanout of process equipment and nondestructive measurement of the remaining 235 U holdup were required. The holdup measurements had safeguards, accountability, and nuclear criticality safety significance; therefore, a technically defensible and well-documented holdup measurement program was needed. Appropriate standards were fabricated, measurement techniques were selected, and an aggressive schedule was followed. Early in the program, offsite experts reviewed the measurement program, and their recommendations were adopted. Contact and far-field methods were used for most measurements, but some process equipment required special attention. All holdup measurements were documented, and each report was subjected to internal peer review. Some measured values were checked against values obtained by other methods; agreement was generally good

  11. 25 CFR 170.803 - What facilities are eligible under the BIA Road Maintenance Program?

    Science.gov (United States)

    2010-04-01

    ... AND WATER INDIAN RESERVATION ROADS PROGRAM BIA Road Maintenance § 170.803 What facilities are eligible under the BIA Road Maintenance Program? (a) The following public transportation facilities are eligible for maintenance under the BIA Road Maintenance Program: (1) BIA transportation facilities listed in...

  12. Unsaturated zone investigation at the radioactive waste storage facility site

    Energy Technology Data Exchange (ETDEWEB)

    Skuratovic, Zana; Mazeika, Jonas; Petrosius, Rimantas; Jakimaviciute-Maseliene, Vaidote [Nature Research Centre, Akademijos St. 2, LT-08412, Vilnius (Lithuania); Klizas, Petras; Mokrik, Robert [Vilnius University, M.K. Ciurlionio St. 21/27, LT-03101 Vilnius (Lithuania)

    2014-07-01

    Unsaturated zone is an important part of water circulation cycle and an integral part of many hydrological and hydrogeological factors and processes. The soils of unsaturated zone are regarded as the first natural barrier to a large extent able to limit the spread of contaminants. Nuclear waste disposal site (Maisiagala radioactive waste storage facility site) was analysed in terms of the moisture movement through the unsaturated zone. Extensive data sets of the hydraulic properties, water content and isotope composition have been collected and summarized. The main experimental and observational tasks included the collection of soil samples; determination of the physical properties and the hydraulic conductivity values of soil samples, moisture extraction from the soil sample for isotopic studies; observation of the groundwater dynamics at the Maisiagala piezometer; groundwater sampling for isotopic analysis ({sup 3}H, {sup 18}O/{sup 16}O, {sup 2}H/{sup 1}H ); and monthly precipitation isotopic analysis. Distribution features of globally widespread radionuclide tritium ({sup 3}H) and the water molecule tracer isotopes in precipitation, unsaturated zone soil moisture profiles and groundwater were determined. It was used the well-known unsaturated flow and transport model of HYDRUS-1D (Simunek et al., 2008). In this study, van Genuchten equations for the retention and conductivity estimations have been used. The retention characteristics and van Genuchten model parameters were estimated internally by HYDRUS based on the empirical equations involved in the program. Basic inputs of the tritium transport simulation are the tritium input function and meteorological variables (precipitation and potential evapotranspiration). In order to validate the representativeness of the hydraulic parameters, the model has been used to estimate the tritium distribution in the unsaturated zone, which properly represents the dynamics of the unsaturated zone. The uniformity of the daily

  13. Radiation protection program at an accelerator facility complex

    International Nuclear Information System (INIS)

    Ramanuja, Jaya

    2007-01-01

    Broad aspects of Radiation Protection Program at the Tyco Healthcare/Mallinckrodt Inc. will be presented with emphasis on Occupational dose, Public dose and ALARA program. Regulatory requirements, compliance and radio nuclides of concern for external exposure and internal contamination will be discussed. The facility is subject to in depth annual inspections by the Nuclear Regulatory Commission (NRC) to ensure compliance with regulations and operating license requirements. The facility is required to have an emergency contingency plan in place. A simulated emergency drill scenario is witnessed and graded by the NRC and state inspectors, with full participation by the fire department and the local hospital. Radiation Safety Officer (RSO) is in charge of all radiological aspects of the facility, and reports to the plant manager directly. The RSO or any of his staff has the authority to stop a job if there is a radiological concern. The Radiation protection organization interfaces with Production, QA and Engineering and ensures there is no conflict with Industrial Safety, OSHA and FDA requirements. Any employee has the right to call the regulatory officials if he/she has a concern. Operational aspects of Radiation protection program such as radiological survey, contamination control and limits, air sample survey, radio active waste processing and record retention requirements are per plant procedures and regulatory requirements. Shielding and administrative requirements for designing a modification to an existing design or a new lab/hot cell is subject to in-depth review and approval by Radiation Safety Committee. Each department has a Dose Reduction Subcommittee which meets periodically to discuss if any changes in procedures or facility can be made to decrease the dose. The subcommittee also trends the dose to ensure it is trending downward. Even though 99 Mo/ 99m TC generators are manufactured at the facility, majority of the dose is from cyclotron maintenance

  14. US DOE surplus facilities management program (SFMP). International technology exchange activities

    International Nuclear Information System (INIS)

    Broderick, J.

    1986-01-01

    The Surplus Facilities Management Program is one of five remedial action programs established by the US Department of Energy (DOE) to eliminate potential hazards to the public and environment from radioactive contamination. These programs provide remedial actions at various facilities and sites previously used by the US Government in national atomic energy programs. Included are uranium ore milling sites, nuclear materials production plants, and research and development facilities. The DOE's five remedial action programs are: the Grand Junction Remedial Action Project; the Formerly Utilized Sites Remedial Action Project; the West Valley Demonstration Project; and the Surplus Facilities Management Program. The Surplus Facilities Management Program (SWMP) was established by DOE in 1978. There are presently over 300 shutdown facilities in the SFMP located at sites across the United States and in Puerto Rico. In some cases, remedial action involves decontaminating and releasing a facility for some other use. In other instances, facilities are completely demolished and removed from the site

  15. The LBM program at the EPFL/LOTUS Facility

    International Nuclear Information System (INIS)

    File, J.; Jassby, D.L.; Tsang, F.Y.; Haldy, P.A.; Leo, W.R.; Woodruff, G.

    1986-01-01

    An experimental program of neutron transport studies of the Lithium Blanket Module (LBM) is being carried out with the LOTUS point-neutron source facility at Ecole Polytechnique Federale de Lausanne (EPFL), Switzerland. Preliminary experiments use passive neutron dosimetry within the fuel rods in the LBM central zone, as well as, both thermal extraction and dissolution methods to assay tritium bred in Li/sub 2/O diagnostic wafers and LBM pellets. These measurements are being compared and reconciled with each other and with the predictions of two-dimensional discrete-ordinates and continuous-energy Monte-Carlo analyses of the Lotus/LBM system

  16. DOE standard: Filter test facility quality program plan

    International Nuclear Information System (INIS)

    1999-02-01

    This standard was developed primarily for application in US Department of Energy programs. It contains specific direction for HEPA filter testing performed at a DOE-accepted HEPA Filter Test Facility (FTF). Beneficial comments (recommendations, additions, deletions) and any pertinent data that may improve this document should be sent to the Office of Nuclear Safety Policy and Standards (EH-31), US Department of Energy, Washington, DC 20585, by letter or by using the self-addressed Document Improvement Proposal form (DOE F 1300.3) appearing at the end of this document

  17. Thermohydraulic investigations of nuclear power facilities (to the 60-th anniversary of the First NPP start)

    International Nuclear Information System (INIS)

    Rachkov, V.I.; Efanov, A.D.; Zhukov, A.V.; Kalyakin, S.G.; Sorokin, A.P.

    2014-01-01

    The investigations conducting in SSC RF - IPPE are aimed to develop theory and create calculational programs which allow to obtain the detailed description of coolant velocity fields and temperatures in any channels and equipment units of nuclear power facilities. Specially developed sensors for measuring various parameters are used in the experiments. Mathematical models and numerical methods are generalized for description and numerical solution of compressible fluids, multiphase and multifluid systems. The programs which allow to determine hydrodynamic and thermotechnical characteristics with account for melting, solidification, boiling processes are established. The obtained data is the base for creating the two-phase media flow theory. The study of the processes of impurity formation, transport and precipitation in liquid metal coolants has been allowed to develop the methods of impurity mass transfer simulation in circuits. For solving the fast reactor safety problem the series of investigations on liquid metals physics, boiling and condensation have been carried out [ru

  18. Training and research reactor facility longevity extension program

    International Nuclear Information System (INIS)

    Carriveau, G.W.

    1991-01-01

    Since 1943, over 550 training and research reactors have been in operation. According to statistics from the International Atomic Energy Agency, ∼325 training and research reactors are currently in service. This total includes a wide variety of designs covering a range of power and research capabilities located virtually around the world. A program has been established at General Atomics (GA) that is dedicated to the support of extended longevity of training and research reactor facilities. Aspects of this program include the following: (1) new instrumentation and control systems; (2) improved and upgraded nuclear monitoring and control channels; (3) facility testing, repair and upgrade services that include (a) pool or tank integrity, (b) cooling system, and (c) water purification system; (4) fuel element testing procedures and replacement; (5) control rod drive rebuilding and upgrades; (6) control and monitoring system calibration and repair service; (7) training services, including reactor operations, maintenance, instrumentation calibration, and repair; and (8) expanded or new uses such as neutron radiography and autoradiography, isotope production, nuclear medicine, activation analysis, and material properties modification

  19. Investigating walking environments in and around assisted living facilities: a facility visit study.

    Science.gov (United States)

    Lu, Zhipeng

    2010-01-01

    This study explores assisted living residents' walking behaviors, locations where residents prefer to walk, and walking environments in and around assisted living facilities. Regular walking is beneficial to older adults' physical and psychological health. Yet frail older residents in assisted living are usually too sedentary to achieve these benefits. The physical environment plays an important role in promoting physical activity. However, there is little research exploring this relationship in assisted living settings. The researcher visited 34 assisted living facilities in a major Texas city. Methods included walk-through observation with the Assisted Living Facility Walking Environment Checklist, and interviews with administrators by open- and close-ended questions. The data from 26 facilities were analyzed using descriptive statistics (for quantitative data) and content analysis (for qualitative data). The results indicate that (a) residents were walking both indoors and outdoors for exercise or other purposes (e.g., going to destinations); (b) assisted living facility planning and design details-such as neighborhood sidewalk conditions, facility site selection, availability of seating, walking path configuration (e.g., looped/nonlooped path), amount of shading along the path, presence of handrails, existence of signage, etc.-may influence residents' walking behaviors; and (c) current assisted living facilities need improvement in all aspects to make their environments more walkable for residents. Findings of the study provide recommendations for assisted living facilities to improve the walkability of environments and to create environmental interventions to promote regular walking among their residents. This study also implies several directions for future research.

  20. Recommendations for quality assurance programs in nuclear medicine facilities. Radiation recommendations series

    International Nuclear Information System (INIS)

    Segal, P.; Hamilton, D.R.

    1984-10-01

    The publication provides the elements that should be considered by nuclear medicine facilities to improve their existing programs or develop new quality assurance programs. The important administrative aspects of quality assurance programs are stressed. Each facility is encouraged to adopt those elements of the recommended program that are appropriate to its individual needs and resources

  1. TMI-2 Vessel Investigation Project Metallurgical Program

    International Nuclear Information System (INIS)

    Diercks, D.R.; Neimark, L.A.

    1990-01-01

    The TMI-2 [Three Mile Island unit 2] Vessel Investigation Project Metallurgical Program at Argonne National Laboratory is a part of the international TMI-2 Vessel Investigation Project being conducted jointly by the U.S. Nuclear Regulatory Commission and the Organization for Economic Co-operation and Development (OECD). The overall project consists of three phases, namely (1) recovery of material samples from the lower head of the TMI-2 reactor, (2) examination and analysis of the lower head samples and the preparation and testing of archive material subjected to a similar thermal history, and (3) procurement, examination, and analysis of companion core material located adjacent to or near the lower head material. The specific objectives of the ANL Metallurgical Program, which accounts for a major portion of Phase 2, are to prepare metallographic and mechanical test specimen blanks from the TMI-2 lower head material, prepare similar test specimen blanks from suitable archive material subjected to the appropriate thermal processing, determine the mechanical properties of the lower vessel head and archive materials under the conditions of the core-melt accident, and assess the lower head integrity and margin-to-failure during the accident. The ANL work consists of three tasks: (1) archive materials program, (2) fabrication of metallurgical and mechanical test specimens from the TMI-2 pressure vessel samples, and (3) mechanical property characterization of TMI-2 lower pressure vessel head and archive material

  2. Phase II Investigation at the Former CCC/USDA Grain Storage Facility in Savannah, Missouri

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, Lorraine M. [Argonne National Lab. (ANL), Argonne, IL (United States). Environmental Science Division. Applied Geosciences and Environmental Management Section

    2012-05-01

    contamination potentially associated with a number of former CCC/USDA grain storage facilities in Missouri. The site characterization at Savannah is being conducted on behalf of the CCC/USDA by the Environmental Science Division of Argonne National Laboratory. The investigation is being conducted in phases, so that information obtained and interpretations developed during each incremental stage can be used most effectively to guide subsequent phases of the program. Phase II objectives: Investigate the more detailed characteristics of groundwater flow in the vicinity of the former CCC/USDA facility and the contaminated Morgan and MoDOT private wells; Obtain additional information on the vertical and lateral distribution and concentrations of carbon tetrachloride in groundwater in the vicinity of the former CCC/USDA facility and the contaminated Morgan and MoDOT private wells; Investigate further for possible evidence of carbon tetrachloride in the subsurface (vadose zone) and deeper soils beneath the former CCC/USDA facility, as well as in the vicinity of the contaminated MoDOT private well.

  3. Test facility for investigation of heat transfer of promising coolants for the nuclear power industry

    Science.gov (United States)

    Belyaev, I. A.; Sviridov, V. G.; Batenin, V. M.; Biryukov, D. A.; Nikitina, I. S.; Manchkha, S. P.; Pyatnitskaya, N. Yu.; Razuvanov, N. G.; Sviridov, E. V.

    2017-11-01

    The results are presented of experimental investigations into liquid metal heat transfer performed by the joint research group consisting of specialist in heat transfer and hydrodynamics from NIU MPEI and JIHT RAS. The program of experiments has been prepared considering the concept of development of the nuclear power industry in Russia. This concept calls for, in addition to extensive application of water-cooled, water-moderated (VVER-type) power reactors and BN-type sodium cooled fast reactors, development of the new generation of BREST-type reactors, fusion power reactors, and thermonuclear neutron sources. The basic coolants for these nuclear power installations will be heavy liquid metals, such as lead and lithium-lead alloy. The team of specialists from NRU MPEI and JIHT RAS commissioned a new RK-3 mercury MHD-test facility. The major components of this test facility are a unique electrical magnet constructed at Budker Nuclear Physics Institute and a pressurized liquid metal circuit. The test facility is designed for investigating upward and downward liquid metal flows in channels of various cross-sections in a transverse magnetic field. A probe procedure will be used for experimental investigation into heat transfer and hydrodynamics as well as for measuring temperature, velocity, and flow parameter fluctuations. It is generally adopted that liquid metals are the best coolants for the Tokamak reactors. However, alternative coolants should be sought for. As an alternative to liquid metal coolants, molten salts, such as fluorides of lithium and beryllium (so-called FLiBes) or fluorides of alkali metals (so-called FLiNaK) doped with uranium fluoride, can be used. That is why the team of specialists from NRU MPEI and JIHT RAS, in parallel with development of a mercury MHD test facility, is designing a test facility for simulating molten salt heat transfer and hydrodynamics. Since development of this test facility requires numerical predictions and verification

  4. 10 CFR 611.202 - Advanced Technology Vehicle Manufacturing Facility Award Program.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 4 2010-01-01 2010-01-01 false Advanced Technology Vehicle Manufacturing Facility Award... TECHNOLOGY VEHICLES MANUFACTURER ASSISTANCE PROGRAM Facility/Funding Awards § 611.202 Advanced Technology Vehicle Manufacturing Facility Award Program. DOE may issue, under the Advanced Technology Vehicle...

  5. Quality Assurance of ARM Program Climate Research Facility Data

    Energy Technology Data Exchange (ETDEWEB)

    Peppler, RA; Kehoe, KE; Sonntag, KL; Bahrmann, CP; Richardson, SJ; Christensen, SW; McCord, RA; Doty, DJ; Wagener, Richard [BNL; Eagan, RC; Lijegren, JC; Orr, BW; Sisterson, DL; Halter, TD; Keck, NN; Long, CN; Macduff, MC; Mather, JH; Perez, RC; Voyles, JW; Ivey, MD; Moore, ST; Nitschke, DL; Perkins, BD; Turner, DD

    2008-03-01

    This report documents key aspects of the Atmospheric Radiation Measurement (ARM) Climate Research Facility (ACRF) data quality assurance program as it existed in 2008. The performance of ACRF instruments, sites, and data systems is measured in terms of the availability, usability, and accessibility of the data to a user. First, the data must be available to users; that is, the data must be collected by instrument systems, processed, and delivered to a central repository in a timely manner. Second, the data must be usable; that is, the data must be inspected and deemed of sufficient quality for scientific research purposes, and data users must be able to readily tell where there are known problems in the data. Finally, the data must be accessible; that is, data users must be able to easily find, obtain, and work with the data from the central repository. The processes described in this report include instrument deployment and calibration; instrument and facility maintenance; data collection and processing infrastructure; data stream inspection and assessment; the roles of value-added data processing and field campaigns in specifying data quality and haracterizing the basic measurement; data archival, display, and distribution; data stream reprocessing; and engineering and operations management processes and procedures. Future directions in ACRF data quality assurance also are presented.

  6. Quality Assurance of ARM Program Climate Research Facility Data

    International Nuclear Information System (INIS)

    Peppler, R.A.; Kehoe, K.E.; Sonntag, K.L.; Bahramann, C.P.; Richardson, S.J.; Christensen, S.W.; McCord, R.A.; Doty, D.J.; Wagener, R.; Eagan, R.C.; Lijegren, J.C.; Orr, B.W.; Sisterson, D.L.; Halter, T.D.; Keck, N.N.; Long, C.N.; Macduff, M.C.; Mather, J.H.; Perez, R.C.; Voyles, J.W.; Ivey, M.D.; Moore, S.T.; Nitschke, D.L.; Perkins, B.D.; Turner, D.D.

    2008-01-01

    This report documents key aspects of the Atmospheric Radiation Measurement (ARM) Climate Research Facility (ACRF) data quality assurance program as it existed in 2008. The performance of ACRF instruments, sites, and data systems is measured in terms of the availability, usability, and accessibility of the data to a user. First, the data must be available to users; that is, the data must be collected by instrument systems, processed, and delivered to a central repository in a timely manner. Second, the data must be usable; that is, the data must be inspected and deemed of sufficient quality for scientific research purposes, and data users must be able to readily tell where there are known problems in the data. Finally, the data must be accessible; that is, data users must be able to easily find, obtain, and work with the data from the central repository. The processes described in this report include instrument deployment and calibration; instrument and facility maintenance; data collection and processing infrastructure; data stream inspection and assessment; the roles of value-added data processing and field campaigns in specifying data quality and characterizing the basic measurement; data archival, display, and distribution; data stream reprocessing; and engineering and operations management processes and procedures. Future directions in ACRF data quality assurance also are presented

  7. 75 FR 70013 - Medicare Program; Inpatient Rehabilitation Facility Prospective Payment System for Federal Fiscal...

    Science.gov (United States)

    2010-11-16

    ... 0938-AP89 Medicare Program; Inpatient Rehabilitation Facility Prospective Payment System for Federal... the July 22, 2010 Federal Register entitled, ``Inpatient Rehabilitation Facility Prospective Payment System for Federal Fiscal Year 2011.'' DATES: Effective Date. This correction is effective for IRF...

  8. Microdosimetric investigation at the therapeutic proton beam facility of CATANA.

    Science.gov (United States)

    De Nardo, L; Moro, D; Colautti, P; Conte, V; Tornielli, G; Cuttone, G

    2004-01-01

    Proton beams (62 Mev) are used by the Laboratori Nazionali del Sud of the Italian Institute of Nuclear Physics to treat eye melanoma tumours at the therapeutic facility called CATANA. A cylindrical slim tissue-equivalent proportional counter (TEPC) of 2.7 mm external diameter has been used to compare the radiation quality of two spread-out Bragg peaks (SOBP) at the CATANA proton beam.

  9. Microdosimetric investigation at the therapeutic proton beam facility of Catana

    International Nuclear Information System (INIS)

    De Nardo, L.; Moro, D.; Colautti, P.; Conte, V.; Tornielli, G.; Cuttone, G.

    2004-01-01

    Proton beams (62 Mev) are used by the Laboratori Nazionali del Sud of the Italian Inst. of Nuclear Physics to treat eye melanoma tumours at the therapeutic facility called CATANA. A cylindrical slim tissue-equivalent proportional counter (TEPC) of 2.7 mm external diameter has been used to compare the radiation quality of two spread-out Bragg peaks (SOBP) at the CATANA proton beam. (authors)

  10. Program for studying fundamental interactions at the PIK reactor facilities

    International Nuclear Information System (INIS)

    Serebrov, A. P.; Vassiljev, A. V.; Varlamov, V. E.; Geltenbort, P.; Gridnev, K. A.; Dmitriev, S. P.; Dovator, N. A.; Egorov, A. I.; Ezhov, V. F.; Zherebtsov, O. M.; Zinoviev, V. G.; Ivochkin, V. G.; Ivanov, S. N.; Ivanov, S. A.; Kolomensky, E. A.; Konoplev, K. A.; Krasnoschekova, I. A.; Lasakov, M. S.; Lyamkin, V. A.; Martemyanov, V. P.

    2016-01-01

    A research program aimed at studying fundamental interactions by means of ultracold and polarized cold neutrons at the GEK-4-4′ channel of the PIK reactor is presented. The apparatus to be used includes a source of cold neutrons in the heavy-water reflector of the reactor, a source of ultracold neutrons based on superfluid helium and installed in a cold-neutron beam extracted from the GEK-4 channel, and a number of experimental facilities in neutron beams. An experiment devoted to searches for the neutron electric dipole moment and an experiment aimed at a measurement the neutron lifetime with the aid of a large gravitational trap are planned to be performed in a beam of ultracold neutrons. An experiment devoted to measuring neutron-decay asymmetries with the aid of a superconducting solenoid is planned in a beam of cold polarized neutrons from the GEK-4′ channel. The second ultracold-neutron source and an experiment aimed at measuring the neutron lifetime with the aid of a magnetic trap are planned in the neutron-guide system of the GEK-3 channel. In the realms of neutrino physics, an experiment intended for sterile-neutrino searches is designed. The state of affairs around the preparation of the experimental equipment for this program is discussed.

  11. Program for studying fundamental interactions at the PIK reactor facilities

    Energy Technology Data Exchange (ETDEWEB)

    Serebrov, A. P., E-mail: serebrov@pnpi.spb.ru; Vassiljev, A. V.; Varlamov, V. E. [National Research Center Kurchatov Institute, Petersburg Nuclear Physics Institute (Russian Federation); Geltenbort, P. [Institut Laue-Langevin (France); Gridnev, K. A. [St. Petersburg State University (Russian Federation); Dmitriev, S. P.; Dovator, N. A. [Russian Academy of Sciences, Ioffe Physical-Technical Institute (Russian Federation); Egorov, A. I.; Ezhov, V. F.; Zherebtsov, O. M.; Zinoviev, V. G.; Ivochkin, V. G.; Ivanov, S. N.; Ivanov, S. A.; Kolomensky, E. A.; Konoplev, K. A.; Krasnoschekova, I. A.; Lasakov, M. S.; Lyamkin, V. A. [National Research Center Kurchatov Institute, Petersburg Nuclear Physics Institute (Russian Federation); Martemyanov, V. P. [National Research Center Kurchatov Institute (Russian Federation); and others

    2016-05-15

    A research program aimed at studying fundamental interactions by means of ultracold and polarized cold neutrons at the GEK-4-4′ channel of the PIK reactor is presented. The apparatus to be used includes a source of cold neutrons in the heavy-water reflector of the reactor, a source of ultracold neutrons based on superfluid helium and installed in a cold-neutron beam extracted from the GEK-4 channel, and a number of experimental facilities in neutron beams. An experiment devoted to searches for the neutron electric dipole moment and an experiment aimed at a measurement the neutron lifetime with the aid of a large gravitational trap are planned to be performed in a beam of ultracold neutrons. An experiment devoted to measuring neutron-decay asymmetries with the aid of a superconducting solenoid is planned in a beam of cold polarized neutrons from the GEK-4′ channel. The second ultracold-neutron source and an experiment aimed at measuring the neutron lifetime with the aid of a magnetic trap are planned in the neutron-guide system of the GEK-3 channel. In the realms of neutrino physics, an experiment intended for sterile-neutrino searches is designed. The state of affairs around the preparation of the experimental equipment for this program is discussed.

  12. [Design of an HACCP program for a cocoa processing facility].

    Science.gov (United States)

    López D'Sola, Patrizia; Sandia, María Gabriela; Bou Rached, Lizet; Hernández Serrano, Pilar

    2012-12-01

    The HACCP plan is a food safety management tool used to control physical, chemical and biological hazards associated to food processing through all the processing chain. The aim of this work is to design a HACCP Plan for a Venezuelan cocoa processing facility.The production of safe food products requires that the HACCP system be built upon a solid foundation of prerequisite programs such as Good Manufacturing Practices (GMP) and Sanitation Standard Operating Procedures (SSOP). The existence and effectiveness of these prerequisite programs were previously assessed.Good Agriculture Practices (GAP) audit to cocoa nibs suppliers were performed. To develop the HACCP plan, the five preliminary tasks and the seven HACCP principles were accomplished according to Codex Alimentarius procedures. Three Critical Control Points (CCP) were identified using a decision tree: winnowing (control of ochratoxin A), roasting (Salmonella control) and metallic particles detection. For each CCP, Critical limits were established, the Monitoring procedures, Corrective actions, Procedures for Verification and Documentation concerning all procedures and records appropriate to these principles and their application was established. To implement and maintain a HACCP plan for this processing plant is suggested. Recently OchratoxinA (OTA) has been related to cocoa beans. Although the shell separation from the nib has been reported as an effective measure to control this chemical hazard, ochratoxin prevalence study in cocoa beans produced in the country is recommended, and validate the winnowing step as well

  13. Atomics International fuel fabrication facility and low enrichment program [contributed by T.A. Moss, AI

    International Nuclear Information System (INIS)

    Moss, T.A.

    1993-01-01

    The AI facility is approximately 30,000 square feet in area and consists of four general areas. One area is devoted to the production of UAl x powder. It consists of a series of arc melting furnaces, crushing lines, glove boxes, and compacting presses. The second area is used for the rolling of fuel plates. The third area is used for the machining of the plates to final size and also the machining of the fuel elements. In the fourth area the fuel plates are swaged into assemblies, and all welding and inspection operations are performed. As part of the lower enrichment program we are scheduled to put a second UAl x powder line into operation and we have had to expand some of our storage area. Under the low enrichment program the AI fuel facility will be modified to accommodate a separate low enrichment Al x production line and compacting line. This facility modification should be done by the end of the fiscal year. We anticipate producing fuel with an enrichment slightly less than 20% We anticipate powder being available for plate production shortly after the facility is completed. Atomics International is scheduled to conduct plate LEU verification work using fully enriched material in the June-July time period, at which time we will investigate what level of uranium loadings we can go to using the current process. It is anticipated that 55 volume percent uranium compound in our fuel form can be achieved

  14. Atmospheric Radiation Measurement Program facilities newsletter, February 2001.; TOPICAL

    International Nuclear Information System (INIS)

    Holdridge, D. J.

    2001-01-01

    This newsletter consists of the following: (1) ARM Science Team Meeting Scheduled-The 11th Annual ARM Science Team meeting is scheduled for March 19-23, 2001, in Atlanta, Georgia. Members of the science team will exchange research results achieved by using ARM data. The science team is composed of working groups that investigate four topics: instantaneous radiative flux, cloud parameterizations and modeling, cloud properties, and aerosols. The annual meeting brings together the science team's 150 members to discuss issues related to ARM and its research. The members represent universities, government laboratories and research facilities, and independent research companies. (2) Communications to Extended Facilities Upgraded-New communications equipment has been installed at all of the SGP extended facilities. Shelters were installed to house the new equipment used to transfer data from instruments via the Internet to the site data system at the central facility. This upgrade has improved data availability from the extended facilities to 100% and reduced telephone costs greatly. (3) SGP Goes ''Buggy''-Steve Sekelsky, a researcher from the University of Massachusetts, is planning to bring a 95-GHz radar to the SGP central facility for deployment in March-October 2001. The radar will help to identify signals due to insects flying in the air. The ARM millimeter cloud radar, which operates at 35 GHz, is sensitive to such insect interference. Testing will also be performed by using a second 35-GHz radar with a polarized radar beam, which can differentiate signals from insects versus cloud droplets. (4) Winter Fog-Fog can add to hazards already associated with winter weather. Common types of fog formation include advection, radiation, and steam. Advection fog: An advection fog is a dense fog that forms when a warm, moist air mass moves into an area with cooler ground below. For example, fog can form in winter when warmer, water-saturated air from the south (associated with

  15. Seismic qualification program plan for continued operation at DOE-SRS nuclear material processing facilities

    International Nuclear Information System (INIS)

    Talukdar, B.K.; Kennedy, W.N.

    1991-01-01

    The Savannah River Facilities for the most part were constructed and maintained to standards that were developed by Du Pont and are not rigorously in compliance with the current General Design Criteria (GDC); DOE Order 6430.IA requirements. In addition, many of the facilities were built more than 30 years ago, well before DOE standards for design were issued. The Westinghouse Savannah River Company (WSRC) his developed a program to address the evaluation of the Nuclear Material Processing (NMP) facilities to GDC requirements. The program includes a facility base-line review, assessment of areas that are not in compliance with the GDC requirements, planned corrective actions or exemptions to address the requirements, and a safety assessment. The authors from their direct involvement with the Program, describe the program plan for seismic qualification including other natural phenomena hazards,for existing NMP facility structures to continue operation Professionals involved in similar effort at other DOE facilities may find the program useful

  16. Overview of the Defense Programs Research and Technology Development Program for fiscal year 1993. Appendix II research laboratories and facilities

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-30

    This document contains summaries of the research facilities that support the Defense Programs Research and Technology Development Program for FY 1993. The nine program elements are aggregated into three program clusters as follows: (1) Advanced materials sciences and technologies; chemistry and materials, explosives, special nuclear materials (SNM), and tritium. (2) Design sciences and advanced computation; physics, conceptual design and assessment, and computation and modeling. (3) Advanced manufacturing technologies and capabilities; system engineering science and technology, and electronics, photonics, sensors, and mechanical components. Section I gives a brief summary of 23 major defense program (DP) research and technology facilities and shows how these major facilities are organized by program elements. Section II gives a more detailed breakdown of the over 200 research and technology facilities being used at the Laboratories to support the Defense Programs mission.

  17. Atmospheric Radiation Measurement Program facilities newsletter, January 2001.; TOPICAL

    International Nuclear Information System (INIS)

    Holdridge, D. J.

    2001-01-01

    In the realm of global climate modeling, numerous variables affect the state of the atmosphere and climate. One important area is soil moisture and temperature. The ARM Program uses several types of instruments to gather soil moisture information. An example is the soil water and temperature system (SWATS). A SWATS is located at each of 21 extended facility sites within the CART site boundary. Each system is configured to measure soil moisture and temperature at eight distinct subsurface levels. A special set of probes used in the SWATS measures soil temperature, soil-water potential, and volumetric water content. Sensors are placed at eight different depths below the soil surface, starting at approximately 5 cm (2 in.) below the surface and ending as deep as 175 cm (69 in.). Each site has two identical sets of probes buried 1 m (3.3 ft) apart, to yield duplicate measurements as a quality control measure. At some sites, impenetrable soil or rock layers prevented installation of probes at the deeper levels. The sensors are connected to an electronic data logger that collects and stores the data. Communication equipment transfers data from the site. All of the electronic equipment is housed in a weatherproof enclosure mounted on a concrete slab

  18. Investigation of plasma–surface interaction at plasma beam facilities

    Energy Technology Data Exchange (ETDEWEB)

    Kurnaev, V., E-mail: kurnaev@plasma.mephi.ru [National Research Nuclear University MEPhI (Moscow Engineering Physics Institute), Kashirskoe sh. 31, 115409 Moscow (Russian Federation); Vizgalov, I.; Gutorov, K. [National Research Nuclear University MEPhI (Moscow Engineering Physics Institute), Kashirskoe sh. 31, 115409 Moscow (Russian Federation); Tulenbergenov, T.; Sokolov, I.; Kolodeshnikov, A.; Ignashev, V.; Zuev, V.; Bogomolova, I. [Institute of Atomic Energy, National Nuclear Center the Republic of Kazakhstan, Street Krasnoarmejsky, 10, 071100 Kurchatov (Kazakhstan); Klimov, N. [SRC RF TRINITI, ul. Pushkovykh, vladenie 12, Troitsk, 142190 Moscow (Russian Federation)

    2015-08-15

    The new Plasma Beam Facility (PBF) has been put into operation for assistance in testing of plasma faced components at Material Science Kazakhstan Tokamak (KTM). PBF includes a powerful electron gun (up to 30 kV, 1 A) and a high vacuum chamber with longitudinal magnetic field coils (up to 0.2 T). The regime of high vacuum electron beam transportation is used for thermal tests with power density at the target surface up to 10 GW/m{sup 2}. The beam plasma discharge (BPD) regime with a gas-puff is used for generation of intensive ion fluxes up to 3 ⋅ 10{sup 22} m{sup −2} s{sup −1}. Initial tests of the KTM PBF’s capabilities were carried out: various discharge regimes, carbon deposits cleaning, simultaneous thermal and ion impacts on radiation cooled refractory targets. With a water-cooled target the KTM PBF could be used for high heat flux tests of materials (validated by the experiment with W mock-up at the PR-2 PBF)

  19. Investigation for the ecology in areas nearby a nuclear facility

    International Nuclear Information System (INIS)

    Qin Suyun; Zhou Caiyun; Zhou Zirong; Chen Wenying; Zhen Zhijiang

    1995-03-01

    Studies were undertaken for the general ecological environment around the evaporating ponds and Gobi desert areas receiving the low and very low level radioactive waste water from a nuclear facility and for the transport of radionuclides in food chains were undertaken. On basis of obtained results the following conclusions were made: (1) In consequence of controlled releases of low level radioactive waste water, a steady specific ecosystem had formed. (2) Concentration of radionuclides in sediments, soils, terrestrial and aquatic wild plants and animals, agricultural products irrigated with very low level radioactive waste water, and tissues of sheep pastured in very low level radioactive water drainage areas, were higher significantly than that of non-contaminated areas. (3) Radioactive waste water discharging might result in potential exposure to members of residents. The critical radionuclide was 137 Cs, and the critical pathway was ingesting polluted waterfowls of evaporating pond. On basis of very conservative assessing the maximum intake of 137 Cs of individual of local resident was 1.0 x 10 4 Bq·a -1 corresponding to 50% of ALI of individual of population. Maximum amount of redistribution of radioactive material as a result of carrying by migrating birds under extreme conditions might be about 10 7 Bq·a -1 . (16 refs., 9 tabs., 1 fig.)

  20. Investigation for the ecology in areas nearby a nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Suyun, Qin; Caiyun, Zhou; Zirong, Zhou; Wenying, Chen; Zhijiang, Zhen [Ministry of Nuclear Industry, Taiyuan, SX (China). Inst. of Radiation Protection

    1995-03-01

    Studies were undertaken for the general ecological environment around the evaporating ponds and Gobi desert areas receiving the low and very low level radioactive waste water from a nuclear facility and for the transport of radionuclides in food chains were undertaken. On basis of obtained results the following conclusions were made: (1) In consequence of controlled releases of low level radioactive waste water, a steady specific ecosystem had formed. (2) Concentration of radionuclides in sediments, soils, terrestrial and aquatic wild plants and animals, agricultural products irrigated with very low level radioactive waste water, and tissues of sheep pastured in very low level radioactive water drainage areas, were higher significantly than that of non-contaminated areas. (3) Radioactive waste water discharging might result in potential exposure to members of residents. The critical radionuclide was {sup 137}Cs, and the critical pathway was ingesting polluted waterfowls of evaporating pond. On basis of very conservative assessing the maximum intake of {sup 137}Cs of individual of local resident was 1.0 x 10{sup 4} Bq{center_dot}a{sup -1} corresponding to 50% of ALI of individual of population. Maximum amount of redistribution of radioactive material as a result of carrying by migrating birds under extreme conditions might be about 10{sup 7} Bq{center_dot}a{sup -1}. (16 refs., 9 tabs., 1 fig.).

  1. Syrinx - a research program for the pulsed power radiation facility

    International Nuclear Information System (INIS)

    Etlicher, B.; Chuvatin, A.S.; Choi, P.

    1996-01-01

    Syrinx is a targeted research program with the objective to study, through practical examples, the fundamentals necessary to define the details of all parts which will be required for a new powerful plasma radiation source. The current level of activities of Syrinx is in the design and construction of a multi-megajoule class IES based pulsed power driver which will use long conduction Plasma Opening Switch technology. The present paper reviews mainly the basic experimental research of the POS a nd Z-pinch accomplished in the framework of Syrinx project. This work has a unique international level of participation, from conceptual designs to particular investigations. (author). 9 figs., 17 refs

  2. Surplus Facilities and Resource Conservation and Recovery Act Closure program plan, fiscal year 1992

    International Nuclear Information System (INIS)

    Hughes, M.C.; Wahlen, R.K.; Winship, R.A.

    1991-10-01

    The Surplus Facilities and Resource Conservation and Recovery Act Closure program is responsible to US Department of Energy Field Office, Richland for the safe, cost-effective surveillance, maintenance, and decommissioning of surplus facilities at the Hanford Site. The Surplus Facilities and Resource Conservation and Recovery Act Closure program is also responsible to US Department of Energy Field Office, Richland for the program management of specific Resource Conservation and Recovery Act closures at the Hanford Site. This program plan addresses only the surplus facilities. The criteria used to evaluate each factor relative to decommissioning are based on the guidelines presented by the US Department of Energy Field Office, Richland, Environmental Restoration Division. The guidelines are consistent with the Westinghouse Hanford Company commitment to decommission Hanford Site retired facilities in the safest and most cost-effective way achievable. This document outlines the plan for managing these facilities until disposal

  3. 49 CFR 37.61 - Public transportation programs and activities in existing facilities.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 1 2010-10-01 2010-10-01 false Public transportation programs and activities in... TRANSPORTATION SERVICES FOR INDIVIDUALS WITH DISABILITIES (ADA) Transportation Facilities § 37.61 Public transportation programs and activities in existing facilities. (a) A public entity shall operate a designated...

  4. Status of site investigation for L/ILW facilities in the Philippines - 59262

    International Nuclear Information System (INIS)

    Palattao, Maria V.; Nohay, Carl; Reyes, Rolando; Singayan, Alfonso; Mallants, Dirk

    2012-01-01

    Document available in abstract form only. Full text of publication follows: Radioactive waste in the Philippines is generated from the various applications of radioactive materials in medicine, industries and research. The Philippine Nuclear Research Institute (PNRI) currently manages these wastes through its centralized treatment and storage facilities on site. Radioactive wastes that are received at the Institute are of different types ranging from contaminated solid and liquid materials to spent sealed sources, including radium. Treated and conditioned wastes are temporarily stored in simple roofed above ground concrete bunkers. The Philippine government through the Inter-agency Subcommittee on Radioactive Waste Management is committed to the development of a national repository for the country's radioactive waste. This policy has been recognized in spite of the relatively small volume of radioactive waste compared with countries that have a nuclear power program. To date, a potential site has been identified for detailed investigation with the assistance of the International Atomic Energy Agency (IAEA). The site is located in the northern part of the Philippine archipelago and has about 34 hectares for potential development. A drilling program that aimed to investigate the geologic, hydrogeologic and hydrologic properties of the site has been implemented

  5. Investigating Integer Restrictions in Linear Programming

    Science.gov (United States)

    Edwards, Thomas G.; Chelst, Kenneth R.; Principato, Angela M.; Wilhelm, Thad L.

    2015-01-01

    Linear programming (LP) is an application of graphing linear systems that appears in many Algebra 2 textbooks. Although not explicitly mentioned in the Common Core State Standards for Mathematics, linear programming blends seamlessly into modeling with mathematics, the fourth Standard for Mathematical Practice (CCSSI 2010, p. 7). In solving a…

  6. Decommissioning and Decontamination Program: Battelle Plutonium Facility, Environmental assessment

    International Nuclear Information System (INIS)

    1979-09-01

    This assessment describes the decontamination of Battelle-Columbus Plutonium Facility and removal from the site of all material contamination which was associated with or produced by the Plutonium Facility. Useable uncontaminated material will be disposed of by procedures normally employed in scrap declaration and transfer. Contaminated waste will be transported to approved radioactive waste storage sites. 5 refs., 1 fig

  7. Geological investigations for the South African nuclear waste repository facility

    International Nuclear Information System (INIS)

    Hambleton-Jones, B.B.; Levin, M.; Andersen, N.J.B.; Brynard, H.J.; Toens, P.D.

    1984-02-01

    The selection of the Vaalputs site on the arid Bushmanland Plateau in the northwestern Cape of the Republic of South Africa for the disposal of low-level radioactive waste was based on a national screening phase program involving socio-economic and geological criteria. Regional geohydrological studies over an area of 27,000 km 2 and a detailed study over 1,300 km 2 indicated that in general the groundwater is saline and that Vaalputs and environs was the most favourable area. The groundwater table lies between 30 and 45 m below the surface, with 14 C ages between 2,500 and 9,000 years old in the immediate vicinity. The geology of Vaalputs consists of Proterozoic granites, gneisses, metasediments, and noritoids of the 1,050 Ma Namaqualand Metamorphic Complex. Upper cretaceous kimberlitic and basaltic intrusions occur locally. Overlying these basement rocks surficial upper Tertiary to Recent argillaceous sediments occur in the Vaalputs basin. The sediments consist of aeolian sand, calcrete, fluvial sandy to gritty clay, white kaolinised clay and very weathered basement rocks. It is in these rocks that the low-level waste trenches will be located. Extensive airborne geophysical surveys, such as aeromagnetics, INPUT, and infrared thermal line scanning, were undertaken to assist in the evaluation of the regional and local subsurface geology. Ground geophysical surveys included refraction seismics, electromagnetics, magnetics, borehole radiometrics and resistivity. Geohydrological modelling of the unsaturated and saturated zones is in progress

  8. Power Burst Facility severe-fuel-damage test program

    International Nuclear Information System (INIS)

    McCardell, R.K.; MacDonald, P.E.

    1982-01-01

    As a result of the Three Mile Island Unit 2 (TMI-2) accident, the United States Nuclear Regulatory Commission (USNRC) has initiated a severe fuel damage research program to investigate fuel rod and core response, and fission product and hydrogen release and transport during degraded core cooling accidents. This paper presents a discussion of the expected benefits of the PBF severe fuel damage tests to the nuclear industry, a description of the first five planned experiments, the results of pretest analysis performed to predict the fuel bundle heatup for the first two experiments, and a discussion of Phase II severe fuel damage experiments. Modifications to the fission product detection system envisioned for the later experiments are also described

  9. ORNL Surplus Facilities Management Program maintenance and surveillance plan for fiscal year 1984

    International Nuclear Information System (INIS)

    Coobs, J.H.; Myrick, T.E.

    1986-10-01

    The Surplus Facilities Management Program (SFMP) at Oak Ridge National Laboratory (ORNL) is part of the Department of Energy's (DOE) National SFMP, administered by the Richland Operations Office. The purpose and objectives of the national program are set forth in the current SFMP Program Plan and include (1) the maintenance and surveillance of facilities awaiting decommissioning, (2) planning for the orderly decommissioning of these facilities, and (3) implementation of a program to accomplish the facility disposition in a safe, cost-effective, and timely manner. As outlined in the national program plan, participating SFMP contractors are required to prepare a formal plan that documents the maintenance and surveillance (M and S) programs established for each site. This report has been prepared to provide this documentation for those facilties included in the ORNL SFMP

  10. Fast Flux Test Facility Asbestos Location Tracking Program

    International Nuclear Information System (INIS)

    REYNOLDS, J.A.

    1999-01-01

    Procedure Number HNF-PRO-408, revision 0, paragraph 1.0, ''Purpose,'' and paragraph 2.0, ''Requirements for Facility Management of Asbestos,'' relate building inspection and requirements for documentation of existing asbestos-containing building material (ACBM) per each building assessment. This documentation shall be available to all personnel (including contractor personnel) entering the facility at their request. Corrective action was required by 400 Area Integrated Annual Appraisal/Audit for Fiscal Year 1992 (IAA-92-0007) to provide this notification documentation. No formal method had been developed to communicate the location and nature of ACBM to maintenance personnel in the Fast Flux Test Facility (FFTF) 400 Area. The scope of this Data Package Document is to locate and evaluate any ACBM found at FFTF which constitutes a baseline. This includes all buildings within the protected area. These findings are compiled from earlier reports, numerous work packages and engineering evaluations of employee findings

  11. Computer program for source distribution process in radiation facility

    International Nuclear Information System (INIS)

    Al-Kassiri, H.; Abdul Ghani, B.

    2007-08-01

    Computer simulation for dose distribution using Visual Basic has been done according to the arrangement and activities of Co-60 sources. This program provides dose distribution in treated products depending on the product density and desired dose. The program is useful for optimization of sources distribution during loading process. there is good agreement between calculated data for the program and experimental data.(Author)

  12. An Investigation of Teaching and Learning Programs in Pharmacy Education.

    Science.gov (United States)

    Strang, Aimee F; Baia, Patricia

    2016-05-25

    Objective. To investigate published, peer-reviewed literature on pharmacy teaching and learning development programs and to synthesize existing data, examine reported efficacy and identify future areas for research. Methods. Medline and ERIC databases were searched for studies on teaching development programs published between 2001 and 2015. Results. Nineteen publications were included, representing 21 programs. Twenty programs were resident teaching programs, one program described faculty development. The majority of programs spanned one year and delivered instruction on teaching methodologies and assessment measures. All except one program included experiential components. Thirteen publications presented outcomes data; most measured satisfaction and self-perceived improvement. Conclusion. Published literature on teacher development in pharmacy is focused more on training residents than on developing faculty members. Although programs are considered important and highly valued by program directors and participants, little data substantiates that these programs improve teaching. Future research could focus on measurement of program outcomes and documentation of teaching development for existing faculty members.

  13. TMI-2 core-examination program: INEL facilities readiness study

    International Nuclear Information System (INIS)

    McLaughlin, T.B.

    1983-02-01

    This report reviews the capability and readiness of remote handling facilities at the Idaho National Engineering Laboratory (INEL) to receive, and store the TMI-2 core, and to examine and analyze TMI-2 core samples. To accomplish these objectives, the facilities must be able to receive commercial casks, unload canisters from the casks, store the canisters, open the canisters, handle the fuel debris and assemblies, and perform various examinations. The report identifies documentation, including core information, necessary to INEL before receiving the entire TMI-2 core. Also identified are prerequisites to INEL's receipt of the first canister: costs, schedules, and a preliminary project plan for the tasks

  14. 9 CFR 307.1 - Facilities for Program employees.

    Science.gov (United States)

    2010-01-01

    ... facilities exist in a nearby convenient location. Laundry service for inspectors' outer work clothing shall....1 Section 307.1 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF..., including necessary furnishings, light, heat, and janitor service, shall be provided by official...

  15. Disposal facility for spent nuclear fuel. Environmental impact assessment program

    International Nuclear Information System (INIS)

    1998-01-01

    The report presents the Environmental Impact Assessment (EIA) of the high level radioactive waste disposal in Finland. In EIA different alternatives concerning site selection, construction, operation and sealing of the disposal facility as well as waste transportation and encapsulation of the waste are considered

  16. Status of the Tau-Charm Facility and highlights of its physics program

    International Nuclear Information System (INIS)

    Schindler, R.H.

    1990-02-01

    In this paper I will first discuss the history and current status of the Tau-Charm Facility. I will then focus on the unique aspects of the heavy meson and tau physics program of such a facility, which motivates its construction and operation in the mid-1090's

  17. Older Adult Participation in Health Promotion Programs: Perspectives of Facility Administrators

    Science.gov (United States)

    Wright, Tim; Hyner, Gerald C.

    2011-01-01

    Administrators of older adult-centered facilities must identify barriers to the planning and implementation of health promotion programs. In this qualitative research those barriers were identified through in-depth interviews with administrators of older adult-centered facilities. As identified by administrators, the predominant barriers to the…

  18. Professional Development through Organizational Assessment: Using APPA's Facilities Management Evaluation Program

    Science.gov (United States)

    Medlin, E. Lander; Judd, R. Holly

    2013-01-01

    APPA's Facilities Management Evaluation Program (FMEP) provides an integrated system to optimize organizational performance. The criteria for evaluation not only provide a tool for organizational continuous improvement, they serve as a compelling leadership development tool essential for today's facilities management professional. The senior…

  19. 76 FR 59256 - Medicare Program; Inpatient Rehabilitation Facility Prospective Payment System for Federal Fiscal...

    Science.gov (United States)

    2011-09-26

    ...; Inpatient Rehabilitation Facility Prospective Payment System for Federal Fiscal Year 2012; Changes in Size... [CMS-1349-CN] RIN 0938-AQ28 Medicare Program; Inpatient Rehabilitation Facility Prospective Payment System for Federal Fiscal Year 2012; Changes in Size and Square Footage of Inpatient Rehabilitation Units...

  20. 76 FR 32085 - Medicare Program; Inpatient Psychiatric Facilities Prospective Payment System-Update for Rate...

    Science.gov (United States)

    2011-06-03

    ..., ``Inpatient Psychiatric Facilities Prospective Payment System--Update for Rate Year Beginning July 1, 2011 (RY... [CMS-1346-CN] RIN 0938-AQ23 Medicare Program; Inpatient Psychiatric Facilities Prospective Payment System--Update for Rate Year Beginning July 1, 2011 (RY 2012); Correction AGENCY: Centers for Medicare...

  1. The Abbott School Construction Program: NJ Department of Education Proposed Facilities Regulations. Analysis of Preschool Issues

    Science.gov (United States)

    Ponessa, Joan; Boylan, Ellen

    2004-01-01

    This report on preschool facilities analyzes regulations proposed by the New Jersey Department of Education (NJDOE) to implement the Educational Facilities Construction and Financing Act. (EFCFA). EFCFA, which authorizes and governs New Jersey's public school construction program, was enacted in July 2000 to implement the State Supreme Court's…

  2. 200 area liquid effluent facility quality assurance program plan. Revision 1

    International Nuclear Information System (INIS)

    Sullivan, N.J.

    1995-01-01

    Direct revision of Supporting Document WHC-SD-LEF-QAPP-001, Rev. 0. 200 Area Liquid Effluent Facilities Quality Assurance Program Plan. Incorporates changes to references in tables. Revises test to incorporate WHC-SD-LEF-CSCM-001, Computer Software Configuration Management Plan for 200 East/West Liquid Effluent Facilities

  3. Clinical Investigation Program: Annual Progress Report

    Science.gov (United States)

    1992-09-30

    Diamminedichloroplatinum (II), Methotrexate and Bleomycin in the Treatment of Advanced Epidermoid Carcinoma of the Penis , Phase II...II), Methotrexate and Bleomycin in the Treatment of Advanced Epidermoid Carcinoma of the Penis , Phase II (5) Start Date: (6) Est Compl Date: (7...Associate Investigators (11) Key Words: constitutional delay delayed puberty (12) Accumulative MEDCASE:* (13) Est Accum OKA Cost:* *Refer to Unit Summary

  4. 25 CFR Appendix A to Subpart G - List of Activities Eligible for Funding Under BIA Transportation Facility Maintenance Program

    Science.gov (United States)

    2010-04-01

    ... Transportation Facility Maintenance Program A Appendix A to Subpart G Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR LAND AND WATER INDIAN RESERVATION ROADS PROGRAM BIA Road Maintenance Pt. 170... Transportation Facility Maintenance Program The following activities are eligible for BIA Transportation Facility...

  5. 75 FR 1755 - Public Telecommunications Facilities Program: Notice of Availability of Funds

    Science.gov (United States)

    2010-01-13

    ... DEPARTMENT OF COMMERCE National Telecommunications and Information Administration [Docket No. 0911201414-0010-02] Public Telecommunications Facilities Program: Notice of Availability of Funds AGENCY: National Telecommunications and Information Administration, U.S. Department of Commerce. ACTION: Notice of...

  6. Performance indicator program for U.S. Department of Energy reactors and facilities

    International Nuclear Information System (INIS)

    Sastry, R.; Fielding, J.R.; Snyder, B.J.; Usher, J.; Boccio, J.

    1990-01-01

    The U.S. Department of Energy (DOE) is developing a Performance Indicator (PI) Program for all facilities. The objective is to periodically collect, statistically analyze and present performance-related information in a concise and consistent format for DOE and safety of facility operations. A set of 14 DOE-Hq. defined PI's has been established after review of programs used by other organizations. Since July 1989, these PI's have been used in a trial program for eight diverse DOE facilities. Electronic reporting is directly to the DOE Safety Performance Measurement System computer. This paper reports on results demonstrated for the feasibility and usefulness of a DOE-wide PI Program and steps being taken to include all DOE facilities

  7. The outline of investigation on integrity of JMTR concrete structures, cooling system and utility facilities

    International Nuclear Information System (INIS)

    Ebisawa, Hiroyuki; Hanakawa, Hiroki; Asano, Norikazu; Kusunoki, Hidehiko; Yanai, Tomohiro; Sato, Shinichi; Miyauchi, Masaru; Ohto, Tsutomu; Kimura, Tadashi; Kawamata, Takanori; Nemoto, Nobuaki; Watahiki, Shunsuke; Hanawa, Yoshio; Tsuboi, Kazuaki; Ogasawara, Yasushi; Nemoto, Hiroyoshi; Echigoya, Shinichi; Ohtsuka, Kaoru; Onoue, Ryuji; Koike, Sumio; Gorai, Shigeru; Nishiyama, Yutaka; Kurosawa, Akihiko; Hanawa, Nobuhiro; Tobita, Kenji; Tabata, Shuzo; Fukasaku, Akitomi; Isozaki, Takanori; Akashi, Kazutomo; Takahashi, Kunihiro; Tsuji, Tomoyuki

    2009-07-01

    The condition of facilities and machinery used continuously were investigated before the renewal work of JMTR on FY 2007. The subjects of investigation were reactor building, primary cooling system tanks, secondary cooling system piping and tower, emergency generator and so on. As the result, it was confirmed that some facilities and machinery were necessary to repair and others were used continuously for long term by maintaining on the long-term maintenance plan. JMTR is planed to renew by the result of this investigation. (author)

  8. Guidance for Facilities on Risk Management Programs (RMP)

    Science.gov (United States)

    Includes supplemental guidance specific to ammonia refrigeration, wastewater treatment, propane storage, warehouses, chemical distributors, offsite consequence analysis, retail agriculture, applicability of program levels, prevention, emergency response.

  9. Analysis of removal of residual decay heat from interim storage facilities by means of the CFD program FLUENT

    International Nuclear Information System (INIS)

    Stratmann, W.; Hages, P.

    2004-01-01

    Within the scope of nuclear licensing procedures of on-site interim storage facilities for dual purpose casks it is necessary, among other things, to provide proof of sufficient removal of the residual decay heat emitted by the casks. The results of the analyses performed for this purpose define e.g. the boundary conditions for further thermal analyses regarding the permissible cask component temperatures or the maximum permissible temperatures of the fuel cladding tubes of the fuel elements stored in the casks. Up to now, for the centralized interim storage facilities in Germany such analyses were performed on the basis of experimental investigations using scaled-down storage geometries. In the engineering phase of the Lingen on-site interim storage facility, proof was furnished for the first time using the CFD (computational fluid dynamics) program FLUENT. The program FLUENT is an internationally recognized and comprehensively verified program for the calculation of flow and heat transport processes. Starting from a brief discussion of modeling and the different boundary conditions of the computation, this contribution presents various results regarding the temperatures of air, cask surfaces and storage facility components, the mass flows through the storage facility and the heat transfer at the cask surface. The interface point to the cask-specific analyses is defined to be the cask surface

  10. Clinical Investigation Program, RCS MED-300 (RI).

    Science.gov (United States)

    1984-10-01

    protocol is a clinical validation study uti - lizing the BIOTRONIK DIPLOS 04 Dual Chamber Pulse Generator. This study is being conducted under an...recurrence-rates, survival-rates, and pattern of recurrence for patients receiving therapy uti - lizing surgery and postoperative radiation vs combined...placed in the treatment qroup or control aroup by the pharmacist . Progress: Terminate. Both the principal and associate investigators have ETS d. 7

  11. Clinical Investigation Program Annual Progress Report

    Science.gov (United States)

    1988-10-20

    Presented: Interna- tional Symposium on Orthopedics, Mexico , September 1987. Publications: In preparation. 147 FAMC A.P.R. (RCS MED 300) Detail Summary...Infection: A Prospective Study. Presented: 2nd Annual Symposium of the Rocky Moun- tain Flow Cytometry Users Group, Albuquerque, New Mexico , 10-11...Podgore, COL, MC (9) Dept/ISvc: Pediatrics (10) Associate Investigators (11) Key Words: Myron J. Levin, M.D. varicella vaccine U Co. HSC (12

  12. Quality Assurance Program Plan (QAPP) Waste Encapsulation and Storage Facility (WESF)

    International Nuclear Information System (INIS)

    ROBINSON, P.A.

    2000-01-01

    This Quality Assurance Plan describes how the Waste Encapsulation and Storage Facility (WESF) implements the quality assurance (QA) requirements of the Quality Assurance Program Description (QAPD) (HNF-Mp-599) for Project Hanford activities and products. This QAPP also describes the organizational structure necessary to successfully implement the program. The QAPP provides a road map of applicable Project Hanford Management System Procedures, and facility specific procedures, that may be utilized by WESF to implement the requirements of the QAPD

  13. Present status of ESNIT (energy selective neutron irradiation test facility) program

    International Nuclear Information System (INIS)

    Noda, K.; Ohno, H.; Sugimoto, M.; Kato, Y.; Matsuo, H.; Watanabe, K.; Kikuchi, T.; Sawai, T.; Usui, T.; Oyama, Y.; Kondo, T.

    1994-01-01

    The present status of technical studies of a high energy neutron irradiation facility, ESNIT (energy selective neutron irradiation test facility), is summarized. Technological survey and feasibility studies of ESNIT have continued since 1988. The results of technical studies of the accelerator, the target and the experimental systems in ESNIT program were reviewed by an International Advisory Committee in February 1993. Recommendations for future R and D on ESNIT program are also summarized in this paper. ((orig.))

  14. Status and future program of reactor physics experiments in JAERI Critical facilities, FCA and TCA

    International Nuclear Information System (INIS)

    Okajima, Shigeaki; Osugi, Toshitaka; Nakajima, Ken; Suzaki, Takenori; Miyoshi, Yoshinori

    1999-01-01

    The critical facilities in JAERI, FCA (Fast Critical Assembly) and TCA (Tank-type Critical Assembly), have been used to provide integral data for evaluation of nuclear data as well as for development of various types of reactor since they went critical in 1960's. In this paper a review is presented on the experimental programs in both facilities. And the experimental programs in next 5 years are also shown. (author)

  15. 22 CFR 711.150 - Program accessibility: Existing facilities.

    Science.gov (United States)

    2010-04-01

    ... result in a fundamental alteration in the nature of a program or activity or in undue financial and....150 Section 711.150 Foreign Relations OVERSEAS PRIVATE INVESTMENT CORPORATION ADMINISTRATIVE PROVISIONS ENFORCEMENT OF NONDISCRIMINATION ON THE BASIS OF HANDICAP IN PROGRAMS OR ACTIVITIES CONDUCTED BY...

  16. 75 FR 13259 - Public Telecommunications Facilities Program: New Closing Date

    Science.gov (United States)

    2010-03-19

    ... infrastructure of an analog station, the cost of activating additional programming services on digital radio are much less than the cost of constructing a new station. Further, stations can add additional programming... alternative music on its HD-3 channel. WJCT-FM, Jacksonville, FL, provides primarily news and information on...

  17. Clinton P. Anderson Meson Physics Facility and its operational safety program

    International Nuclear Information System (INIS)

    Putnam, T.M.

    1975-01-01

    The Clinton P. Anderson Meson Physics Facility (LAMPF) at the Los Alamos Scientific Laboratory consists of/ (1) a medium-energy, high-intensity linear proton accelerator; (2) experimental areas designed to support a multidisciplined program of research and practical applications; and (3) support facilities for accelerator operations and the experimental program. The high-intensity primary and secondary beams at LAMPF and the varied research program create many interesting and challenging problems for the Health Physics staff. A brief overview of LAMPF is presented, and the Operational Safety Program is discussed, with emphasis on the radiological safety and health physics aspects

  18. Education and training program for graduate school student with synchrotron radiation facility

    International Nuclear Information System (INIS)

    Harada, Isao; Ikeda, Naoshi; Yokoya, Takayoshi

    2008-01-01

    We report the education and training program for graduate students of Graduate School of Natural Science and Technology Okayama University made at synchrotron facilities, SPring-8 and HiSOR. This program is a joint course of graduate school lecture and synchrotron facility training with company researchers, that was authorized by the Ministry of Education, Culture, Sports, Science and Technology. The purpose of this program is the development of human resources who can understand the potential ability of synchrotron experiment. We report our plan and actual activity of the training program. (author)

  19. Status of CHESS facility and research programs: 2010

    Energy Technology Data Exchange (ETDEWEB)

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

    2011-09-01

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

  20. Status of CHESS facility and research programs: 2010

    International Nuclear Information System (INIS)

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

    2011-01-01

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

  1. An independent investigation into the deployment of the federal communications commissions' rural health care pilot program.

    Science.gov (United States)

    Whitten, Pamela; Holtz, Bree; Laplante, Carolyn; Alverson, Dale; Krupinski, Elizabeth

    2010-12-01

    the goal of this study was to provide an independent and objective evaluation of the implementation of the Federal Communications Commission's Rural Health Care Pilot Program. thirty-nine of the programs that were provided funding through this program were interviewed and asked about their project deployment, network planning, and the involvement of their state in implementation. RESULTS showed that programs recruited project team members from a variety of fields to fulfill different roles. Network partners were often chosen because they were stakeholders in the outcome of the project and because they had a past working relationship with the grant-receiving programs. In terms of deployment, many programs had made progress in filling out necessary paperwork and were tracking milestones, but had experienced changes since first receiving funding, such as losing participants. Additionally, many encountered challenges that inhibited deployment, such as coping with rule fluctuations. Many of the programs received support from their respective state governments in project development, often through matching funds, but few states were involved in the actual management of projects. as rural healthcare facilities often lack the information technology infrastructure compared with many urban facilities, it is important to understand the implementation process for programs such as the Rural Health Care Pilot Program and to examine what contributes to progress, stagnation, or disintegration. Although the programs reported some success, almost all had encountered challenges that inhibited implementation. A follow-up study is planned to further investigate deployment and determine the implications of Federal Communications Commission funding.

  2. Honeywell optical investigations on FLASH program

    Science.gov (United States)

    O'Rourke, Ken; Peterson, Eric; Yount, Larry

    1995-05-01

    The increasing performance and reduction of life cycle cost requirements placed on commercial and military transport aircraft are resulting in more complex, highly integrated aircraft control and management systems. The use of fiber optic data transmission media can make significant contributions in achieving these performance and cost goals. The Honeywell portion of Task 2A on the Fly-by-Light Advanced System Hardware (FLASH) program is evaluating a Primary Flight Control System (PFCS) using pilot and copilot inputs from Active Hand Controllers (AHC) which are optically linked to the primary flight Control Computers (PFCC). Customer involvement is an important element of the Task 2A activity. Establishing customer requirements and perspectives on productization of systems developed under FLASH are key to future product success. The Honeywell elements of the PFCS demonstrator provide a command path that is optically interfaced from crew inputs to commands of distributed, smart actuation subsystems commands. Optical communication architectures are implemented using several protocols including the new AS-1773A 20 Mbps data bus standard. The interconnecting fiber optic cable plant is provided by our Task 1A teammate McDonnell Douglas Aerospace (West). Fiber optic cable plant fabrication uses processed, tools and materials reflecting necessary advances in manufacturing required to make fly-by-light avionics systems marketable.

  3. Final work plan : investigation of potential contamination at the former CCC/USDA grain storage facility in Hanover, Kansas.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M.; Environmental Science Division

    2008-11-19

    The Commodity Credit Corporation (CCC), an agency of the U.S. Department of Agriculture (USDA), operated a grain storage facility at the northeastern edge of the city of Hanover, Kansas, from 1950 until the early 1970s. During this time, commercial grain fumigants containing carbon tetrachloride were in common use by the grain storage industry to preserve grain in their facilities. In February 1998, trace to low levels of carbon tetrachloride (below the maximum contaminant level [MCL] of 5.0 {micro}g/L) were detected in two private wells near the former grain storage facility at Hanover, as part of a statewide USDA private well sampling program that was implemented by the Kansas Department of Health and Environment (KDHE) near former CCC/USDA facilities. In April 2007, the CCC/USDA collected near-surface soil samples at 1.8-2 ft BGL (below ground level) at 61 locations across the former CCC/USDA facility. All soil samples were analyzed by the rigorous gas chromatograph-mass spectrometer analytical method (purge-and-trap method). No contamination was found in soil samples above the reporting limit of 10 {micro}g/kg. In July 2007, the CCC/USDA sampled indoor air at nine residences on or adjacent to its former facility to address the residents concerns regarding vapor intrusion. Low levels of carbon tetrachloride were detected at four of the nine homes. Because carbon tetrachloride found in private wells and indoor air at the site might be linked to historical use of fumigants containing carbon tetrachloride at its former grain storage facility, the CCC/USDA is proposing to conduct an investigation to determine the source and extent of the carbon tetrachloride contamination associated with the former facility. This investigation will be conducted in accordance with the intergovernmental agreement between the KDHE and the Farm Service Agency (FSA) of the USDA. The investigation at Hanover will be performed, on behalf of the CCC/USDA, by the Environmental Science

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

    Science.gov (United States)

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

    2015-12-01

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

  5. I and C security program for nuclear facilities: implementation guide - TAFICS/IG/2

    International Nuclear Information System (INIS)

    2016-04-01

    This is the second in a series of documents being developed by TAFICS for protecting computer-based I and C systems of Indian nuclear facilities from cyber attacks. The document provides guidance to nuclear facility management to establish, implement and maintain a robust I and C security program - consisting of security plan and a set of security controls. In order to provide a firm basis for the security program, the document also identifies the fundamental security principles and foundational security requirements related to computer-based I and C systems of nuclear facilities. It is recommended that all applicable Indian nuclear facilities should implement the security program - with required adaptation - so as to provide the necessary assurance that the I and C systems are adequately protected against cyber attacks. (author)

  6. The GANIL plus program for a RNB facility at GANIL

    International Nuclear Information System (INIS)

    Anne, R.; Bertrand, P.; Bourgarel, M.P.; Bieth, C.; Obert, J.; Putaux, J.C.; Liang, C.F.; Paris, P.; Orr, N.; Steckmayer, J.C.

    1993-01-01

    At first version of isotopic separator on-line test bench has been built in order to test the feasibility of the production of radioactive species from 96 MeV/u of 20 Ne impinging a thick target of MgO. This test bench was equipped with a very compact ECR ion source (Nanogan) entirely made from permanent magnets and operating at 10 Ghz. 18 Ne 2,4+ ; 19 Ne 1,2,3,4+ and 23,24 Ne 1+ have been produced and ionized. A new more performing separator (SIRa) allowing the use of different ion sources will be completed by the end of 1993. This separator is one stage of the project of a RNB facility called GANIL PLUS. This facility can be decomposed into two parts: The THI project and the SPIRaL project which includes the production, the separation and the acceleration of radioactive ions. These projects are presented here. (author) 3 refs., 3 figs., 1 tab

  7. Experimental Program for the CLIC test facility 3 test beam line

    CERN Document Server

    Adli, E; Dobert, S; Olvegaard, M; Schulte, D; Syratchev, I; Lillestol, Reidar

    2010-01-01

    The CLIC Test Facility 3 Test Beam Line is the first prototype for the CLIC drive beam decelerator. Stable transport of the drive beam under deceleration is a mandatory component in the CLIC two-beam scheme. In the Test Beam Line more than 50% of the total energy will be extracted from a 150 MeV, 28 A electron drive beam, by the use of 16 power extraction and transfer structures. A number of experiments are foreseen to investigate the drive beam characteristics under deceleration in the Test Beam Line, including beam stability, beam blow up and the efficiency of the power extraction. General benchmarking of decelerator simulation and theory studies will also be performed. Specially designed instrumentation including precision BPMs, loss monitors and a time-resolved spectrometer dump will be used for the experiments. This paper describes the experimental program foreseen for the Test Beam Line, including the relevance of the results for the CLIC decelerator studies.

  8. Final master work plan : environmental investigations at former CCC/USDA facilities in Kansas, 2002 revision.

    Energy Technology Data Exchange (ETDEWEB)

    Burton, J. C.; Environmental Research

    2003-01-23

    The Commodity Credit Corporation (CCC) of the U.S. Department of Agriculture (USDA) has entered into an interagency agreement with the U.S. Department of Energy (DOE) under which Argonne National Laboratory provides technical assistance for hazardous waste site characterization and remediation for the CCC/USDA. Carbon tetrachloride is the contaminant of primary concern at sites in Kansas where former CCC/USDA grain storage facilities were located. Argonne applies its QuickSite(reg sign) Expedited Site Characterization (ESC) approach to these former facilities. The QuickSite environmental site characterization methodology is Argonne's proprietary implementation of the ESC process (ASTM 1998). Argonne has used this approach at several former CCC/USDA facilities in Kansas, including Agenda, Agra, Everest, and Frankfort. The Argonne ESC approach revolves around a multidisciplinary, team-oriented approach to problem solving. The basic features and steps of the QuickSite methodology are as follows: (1) A team of scientists with diverse expertise and strong field experience is required to make the process work. The Argonne team is composed of geologists, geochemists, geophysicists, hydrogeologists, chemists, biologists, engineers, computer scientists, health and safety personnel, and regulatory staff, as well as technical support staff. Most of the staff scientists are at the Ph.D. level; each has on average, more than 15 years of experience. The technical team works together throughout the process. In other words, the team that plans the program also implements the program in the field and writes the reports. More experienced scientists do not remain in the office while individuals with lesser degrees or experience carry out the field work. (2) The technical team reviews, evaluates, and interprets existing data for the site and the contaminants there to determine which data sets are technically valid and can be used in initially designing the field program. A basic

  9. Investigation of s stressed-strained state and optimization of the T-15 facility electromagnetic system design

    International Nuclear Information System (INIS)

    Vaulina, I.G.; Gusev, S.V.; Monoszon, N.A.; Sivkova, G.N.; Spirchenko, Yu.V.; Chvartatskij, R.V.; Churakov, G.F.

    1982-01-01

    The results of investigation of a stressed-strained state (SSS) of superconducting coils of toroidal field (TFSC) of the T-15 facility are presented. The TFSC SSS dependence on the forces acting in the coil plane is reduced to solving the plane problem of the elasticity theory. The problem is solved by the finite element method according to a specially developed program. The TFSC SSS dependence on the action of tilting forces is studied by the structural mechanics method. A refined rod theory taking into account shear strain of the rod cross-section in the direction perpendicular to its axis is used. A comparative analysis of different versions of the TFSC design is carried out. A TFSC design optimized over the SSS is chosen. It is used in constructing the electromagnetic system of the T-15 facility

  10. Horonobe Underground Research Laboratory project. Investigation program for the 2008 fiscal year

    International Nuclear Information System (INIS)

    Nakayama, Masashi; Sanada, Hiroyuki; Yamaguchi, Takehiro; Sugita, Yutaka

    2008-09-01

    As part of the research and development program on geological disposal of high-level radioactive waste (HLW), the Horonobe Underground Research Center, a division of the Japan Atomic Energy Agency (JAEA), is implementing the Horonobe Underground Research Laboratory Project (Horonobe URL Project) with the aim at investigating sedimentary rock formations. According to the research plan described in the Midterm Plan of JAEA, geological investigations are to be carried out during the drilling of a shaft down to intermediate depth, while research and development in the areas of engineering technology and safety assessment are to be promoted by collaboration with other research organizations. The results of the R and D activities will be systematized as a 'knowledge base' that supports a wide range of arguments related to the safety of geological disposal. The Horonobe URL Project is planned to extend over a period of 20 years. The investigations will be conducted in three phases, namely 'Phase 1: Surface-based investigations', 'Phase 2: Construction phase' (investigations during construction of the underground facilities) and 'Phase 3: Operation phase' (research in the underground facilities). This report summarizes the investigation program for the 2008 fiscal year (2008/2009), the 4th year of the Phase 2 investigations. In the 2008 fiscal year, investigations in geoscientific research', including 'development of techniques for investigating the geological environment', 'development of techniques for long-term monitoring of the geological environment', 'development of engineering techniques for use in the deep underground environment' and studies on the long-term stability of the geological environment', are continuously carried out. Investigations in 'research and development on geological disposal technology', including 'improving the reliability of disposal technologies' and 'enhancement of safety assessment methodologies', are also continuously carried out

  11. Status of the US inertial fusion program and the National Ignition Facility

    International Nuclear Information System (INIS)

    Crandall, D.H.

    1997-01-01

    Research programs supported by the United States Office of Inertial Fusion and the NIF are summarized. The US inertial fusion program has developed an approach to high energy density physics and fusion ignition in the laboratory relying on the current physics basis of capsule drive by lasers and on the National Ignition Facility which is under construction. (AIP) copyright 1997 American Institute of Physics

  12. Intense neutron source facility for the fusion energy program

    International Nuclear Information System (INIS)

    Armstrong, D.D.; Emigh, C.R.; Meier, K.L.; Meyer, E.A.; Schneider, J.D.

    1975-01-01

    The Intense Neutron Source Facility, INS, has been proposed to provide a neutronic environment similar to that anticipated in a fully operational fusion-power reactor. The neutron generator will produce an intense flux of 14-MeV neutrons greater than 10 14 neutrons per cm 2 /sec from the collision of two intersecting beams, one of 1.1 A of 270 keV tritium ions and the other of a supersonic jet of deuterium gas. Using either the pure 14-MeV primary neutron spectrum or by tailoring the spectrum with appropriate moderators, crucial radiation-damage effects which are likely to occur in fusion reactors can be thoroughly explored and better understood

  13. Materials evaluation programs at the Defense Waste Processing Facility

    International Nuclear Information System (INIS)

    Gee, J.T.; Iverson, D.C.; Bickford, D.F.

    1992-01-01

    The Savannah River Site (SRS) has been operating a nuclear fuel cycle since the 1950s to produce nuclear materials in support of the national defense effort. About 83 million gallons of high-level waste produced since operations began has been consolidated by evaporation into 33 million gallons at the waste tank farm. The Department of Energy authorized the construction of the Defense Waste Processing Facility (DWPF), the function of which is to immobilize the waste as a durable borosilicate glass contained in stainless steel canisters prior to the placement of the canisters in a federal repository. The DWPF is now mechanically complete and is undergoing commissioning and run-in activities. A brief description of the DWPF process is provided

  14. Construction safety program for the National Ignition Facility

    International Nuclear Information System (INIS)

    Cerruti, S.J.

    1997-01-01

    The Construction Safety Program (CSP) for NIF sets forth the responsibilities, guidelines, rules, policies and regulations for all workers involved in the construction, special equipment installation, acceptance testing, and initial activation and operation of NIF at LLNL during the construction period of NIF

  15. Construction safety program for the National Ignition Facility, Appendix B

    Energy Technology Data Exchange (ETDEWEB)

    Cerruti, S.J.

    1997-06-26

    This Appendix contains material from the LLNL Health and Safety Manual as listed below. For sections not included in this list, please refer to the Manual itself. The areas covered are: asbestos, lead, fire prevention, lockout, and tag program confined space traffic safety.

  16. Construction safety program for the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Cerruti, S.J.

    1997-06-26

    The Construction Safety Program (CSP) for NIF sets forth the responsibilities, guidelines, rules, policies and regulations for all workers involved in the construction, special equipment installation, acceptance testing, and initial activation and operation of NIF at LLNL during the construction period of NIF.

  17. Construction safety program for the National Ignition Facility, Appendix B

    International Nuclear Information System (INIS)

    Cerruti, S.J.

    1997-01-01

    This Appendix contains material from the LLNL Health and Safety Manual as listed below. For sections not included in this list, please refer to the Manual itself. The areas covered are: asbestos, lead, fire prevention, lockout, and tag program confined space traffic safety

  18. From home deliveries to health care facilities: establishing a traditional birth attendant referral program in Kenya.

    Science.gov (United States)

    Tomedi, Angelo; Stroud, Sophia R; Maya, Tania Ruiz; Plaman, Christopher R; Mwanthi, Mutuku A

    2015-07-16

    To assess the effectiveness of a traditional birth attendant (TBA) referral program on increasing the number of deliveries overseen by skilled birth attendants (SBA) in rural Kenyan health facilities before and after the implementation of a free maternity care policy. In a rural region of Kenya, TBAs were recruited to educate pregnant women about the importance of delivering in healthcare facilities and were offered a stipend for every pregnant woman whom they brought to the healthcare facility. We evaluated the percentage of prenatal care (PNC) patients who delivered at the intervention site compared with the percentage of PNC patients who delivered at rural control facilities, before and after the referral program was implemented, and before and after the Kenya government implemented a policy of free maternity care. The window period of the study was from July of 2011 through September 2013, with a TBA referral intervention conducted from March to September 2013. The absolute increases from the pre-intervention period to the TBA referral intervention period in SBA deliveries were 5.7 and 24.0% in the control and intervention groups, respectively (p facility significantly increased compared to control health facilities when TBAs educated women about the need to deliver with a SBA and when TBAs received a stipend for bringing women to local health facilities to deliver. Furthermore, this TBA referral program proved to be far more effective in the target region of Kenya than a policy change to provide free obstetric care.

  19. ERDA test facilities, East Mesa Test Site. Geothermal resource investigations, Imperial Valley, California

    Energy Technology Data Exchange (ETDEWEB)

    1976-01-01

    Detailed specifications which must be complied with in the construction of the ERDA Test Facilities at the East Mesa Site for geothermal resource investigations in Imperial Valley, California are presented for use by prospective bidders for the construction contract. The principle construction work includes a 700 gpm cooling tower with its associated supports and equipment, pipelines from wells, electrical equipment, and all earthwork. (LCL)

  20. Design and first integral test of MUSE facility in ALPHA program

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hyun-sun; Yamano, Norihiro; Maruyama, Yu; Moriyama, Kiyofumi; Kudo, Tamotsu; Yang, Yanhua; Sugimoto, Jun [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-03-01

    Vapor explosion (Steam explosion or energetic Fuel-Coolant Interaction) is a phenomenon in which a hot liquid rapidly releases its internal energy into a surrounding colder and more volatile liquid when these liquids come into a sudden contact. This rapid energy release leads to rapid vapor production within a timescale short compared to vapor expansion causes local pressurization similar to an explosion and eventually threatens the surroundings by dynamic pressures and the subsequent expansion. It has been recognized that the energetics of vapor explosions strongly depend on the initial mixing geometry established by the contact of hot and cold liquids. Therefore, a new program has been initiated to investigate the energetics of vapor explosions in various contact geometries; i.e., pouring, stratified, coolant and melt injection modes in a facility which is able to measure the energy conversion ratio and eventually to provide data to evaluate the mechanistic analytical models. In the report, this new facility, called MUSE (MUlti-configuration in Steam Explosions), and the results of the first integral test are described in detail. (author)

  1. The lithium blanket program at the LOTUS facility

    International Nuclear Information System (INIS)

    File, J.; Haldy, P.A.; Quanci, J.

    1987-01-01

    An experimental program of neutron transport studies of the lithium Blanket Module (LBM) carried out with the LOTUS point-neutron source at the Ecole Polytechnique Federale de Lausanne (EPTL), Switzerland has been concluded. The major objectives of this program are to perform a series of neutron transport and tritium breeding experiments to qualify the LBM for future experiments on toroidal fusion devices such as TFTR to perform neutron multiplier experiments on the LBM employing various materials in a removable slab geometry; and, to compare the experimental results of radiation dosimetry and tritium breeding with the calculations of two and three dimensional neutron transport codes. An overview of the results from the radiation dosimetry and tritium assay are presented and compared to the two and three dimensional neutron transport codes

  2. Quality Assurance Program description, Defense Waste Processing Facility (DWPF)

    International Nuclear Information System (INIS)

    Maslar, S.R.

    1992-01-01

    This document describes the Westinghouse Savannah River Company's (WSRC) Quality Assurance Program for Defense Waste Processing at the Savannah River Site (SRS). WSRC is the operating contractor for the US Department of Energy (DOE) at the SRS. The following objectives are achieved through developing and implementing the Quality Assurance Program: (1) Ensure that the attainment of quality (in accomplishing defense high-level waste processing objectives at the SRS) is at a level commensurate with the government's responsibility for protecting public health and safety, the environment, the public investment, and for efficiently and effectively using national resources. (2) Ensure that high-level waste from qualification and production activities conform to requirements defined by OCRWM. These activities include production processes, equipment, and services; and products that are planned, designed, procured, fabricated, installed, tested, operated, maintained, modified, or produced

  3. Construction safety program for the National Ignition Facility

    International Nuclear Information System (INIS)

    Cerruti, S.J.

    1997-01-01

    The Construction Safety Program (CSP) for NIF sets forth the responsibilities, guidelines, rules, policies and regulations for all workers involved in the construction, special equipment installation, acceptance testing, and initial activation and operation of NIF at LLNL during the construction period of NIF. During this period, all workers are required to implement measures to create a universal awareness which promotes safe practice at the work site, and which will achieve NIF's management objectives in preventing accidents and illnesses. Construction safety for NIF is predicated on everyone performing their jobs in a manner which prevents job-related disabling injuries and illnesses. The CSP outlines the minimum environment, safety, and health (ES ampersand H) standards, LLNL policies and the Construction Industry Institute (CII) Zero Injury Techniques requirements that all workers at the NIF construction site shall adhere to during the construction period of NIF. It identifies the safety requirements which the NIF organizational Elements, construction contractors and construction subcontractors must include in their safety plans for the construction period of NIF, and presents safety protocols and guidelines which workers shall follow to assure a safe and healthful work environment. The CSP also identifies the ES ampersand H responsibilities of LLNL employees, non-LLNL employees, construction contractors, construction subcontractors, and various levels of management within the NIF Program at LLNL. In addition, the CSP contains the responsibilities and functions of ES ampersand H support organizations and administrative groups, and describes their interactions with the NIF Program

  4. Construction safety program for the National Ignition Facility

    Energy Technology Data Exchange (ETDEWEB)

    Cerruti, S.J.

    1997-01-01

    The Construction Safety Program (CSP) for NIF sets forth the responsibilities, guidelines, rules, policies and regulations for all workers involved in the construction, special equipment installation, acceptance testing, and initial activation and operation of NIF at LLNL during the construction period of NIF. During this period, all workers are required to implement measures to create a universal awareness which promotes safe practice at the work site, and which will achieve NIF`s management objectives in preventing accidents and illnesses. Construction safety for NIF is predicated on everyone performing their jobs in a manner which prevents job-related disabling injuries and illnesses. The CSP outlines the minimum environment, safety, and health (ES&H) standards, LLNL policies and the Construction Industry Institute (CII) Zero Injury Techniques requirements that all workers at the NIF construction site shall adhere to during the construction period of NIF. It identifies the safety requirements which the NIF organizational Elements, construction contractors and construction subcontractors must include in their safety plans for the construction period of NIF, and presents safety protocols and guidelines which workers shall follow to assure a safe and healthful work environment. The CSP also identifies the ES&H responsibilities of LLNL employees, non-LLNL employees, construction contractors, construction subcontractors, and various levels of management within the NIF Program at LLNL. In addition, the CSP contains the responsibilities and functions of ES&H support organizations and administrative groups, and describes their interactions with the NIF Program.

  5. Investigation on candidates of principal facilities for exposure dose to public for the facilities using nuclear material

    International Nuclear Information System (INIS)

    Shimazaki, Yosuke; Sawahata, Hiroaki; Takada, Shoji; Fujimoto, Nozomu

    2015-01-01

    HTTR holds the nuclear fuel material use facilities in its reactor facilities, for the purpose of study on the fracture behavior of fuel and release behavior of fission products, development of high-performance fuel, and measurement of neutron flux. Due to the revision of the 'Act on the regulation of nuclear source material, nuclear fuel material and reactor', the facilities having the 'Important safety-related facilities' among the facilities applicable to the Enforcement Ordinance Article 41 (Article 41 facilities) has come to need to conform to the 'Regulations concerning standards for the location, structure, and equipment of used facilities and others'. In this case, actions such as modification by all possible means are required. The nuclear fuel substance use facilities of HTTR correspond to Article 41 facilities. So, whether it is a candidate for the 'Important safety-related facilities' has been examined. As a result, it is confirmed that the facilities are not correspond to the 'Important safety-related facilities', and it has been concluded that modification measures for the purpose of conforming to this approval standard rule are not necessary as of the present. (A.O.)

  6. Facility Decontamination and Decommissioning Program Surveillance and Maintenance Plan, Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Poderis, Reed J. [NSTec; King, Rebecca A. [NSTec

    2013-09-30

    This Surveillance and Maintenance (S&M) Plan describes the activities performed between deactivation and final decommissioning of the following facilities located on the Nevada National Security Site, as documented in the Federal Facility Agreement and Consent Order under the Industrial Sites program as decontamination and decommissioning sites: ? Engine Maintenance, Assembly, and Disassembly (EMAD) Facility: o EMAD Building (Building 25-3900) o Locomotive Storage Shed (Building 25-3901) ? Test Cell C (TCC) Facility: o Equipment Building (Building 25-3220) o Motor Drive Building (Building 25-3230) o Pump Shop (Building 25-3231) o Cryogenic Lab (Building 25-3232) o Ancillary Structures (e.g., dewars, water tower, piping, tanks) These facilities have been declared excess and are in various stages of deactivation (low-risk, long-term stewardship disposition state). This S&M Plan establishes and implements a solid, cost-effective, and balanced S&M program consistent with federal, state, and regulatory requirements. A graded approach is used to plan and conduct S&M activities. The goal is to maintain the facilities in a safe condition in a cost-effective manner until their final end state is achieved. This plan accomplishes the following: ? Establishes S&M objectives and framework ? Identifies programmatic guidance for S&M activities to be conducted by National Security Technologies, LLC, for the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) ? Provides present facility condition information and identifies hazards ? Identifies facility-specific S&M activities to be performed and their frequency ? Identifies regulatory drivers, NNSA/NFO policies and procedures, and best management practices that necessitate implementation of S&M activities ? Provides criteria and frequencies for revisions and updates ? Establishes the process for identifying and dispositioning a condition that has not been previously identified or

  7. PWR blowdown heat transfer separate-effects program: thermal-hydraulic test facility experimental data report for test 104

    International Nuclear Information System (INIS)

    Leon, D.M.; White, M.D.; Moore, P.A.; Hedrick, R.A.

    1978-01-01

    Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 104, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in the PWR system. Test 104 was conducted to obtain CHF in bundle 1 under blowdown conditions. The primary purpose of this report is to make the reduced instrument responses during test 104 available

  8. Environmental, economic, and energy impacts of material recovery facilities. A MITE Program evaluation

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    This report documents an evaluation of the environmental, economic, and energy impacts of material recovery facilities (MRFs) conducted under the Municipal Solid Waste Innovative Technology Evaluation (MITE) Program. The MITE Program is sponsored by the US Environmental Protection Agency to foster the demonstration and development of innovative technologies for the management of municipal solid waste (MSW). This project was also funded by the National Renewable Energy Laboratory (NREL). Material recovery facilities are increasingly being used as one option for managing a significant portion of municipal solid waste (MSW). The owners and operators of these facilities employ a combination of manual and mechanical techniques to separate and sort the recyclable fraction of MSW and to transport the separated materials to recycling facilities.

  9. Ocean Thermal Energy Converstion (OTEC) test facilities study program. Final report. Volume II. Part B

    Energy Technology Data Exchange (ETDEWEB)

    None

    1977-01-17

    Results are presented of an 8-month study to develop alternative non-site-specific OTEC facilities/platform requirements for an integrated OTEC test program which may include land and floating test facilities. Volume II--Appendixes is bound in three parts (A, B, and C) which together comprise a compendium of the most significant detailed data developed during the study. Part B provides an annotated test list and describes component tests and system tests.

  10. Test program element II blanket and shield thermal-hydraulic and thermomechanical testing, experimental facility survey

    International Nuclear Information System (INIS)

    Ware, A.G.; Longhurst, G.R.

    1981-12-01

    This report presents results of a survey conducted by EG and G Idaho to determine facilities available to conduct thermal-hydraulic and thermomechanical testing for the Department of Energy Office of Fusion Energy First Wall/Blanket/Shield Engineering Test Program. In response to EG and G queries, twelve organizations (in addition to EG and G and General Atomic) expressed interest in providing experimental facilities. A variety of methods of supplying heat is available

  11. Test program element II blanket and shield thermal-hydraulic and thermomechanical testing, experimental facility survey

    Energy Technology Data Exchange (ETDEWEB)

    Ware, A.G.; Longhurst, G.R.

    1981-12-01

    This report presents results of a survey conducted by EG and G Idaho to determine facilities available to conduct thermal-hydraulic and thermomechanical testing for the Department of Energy Office of Fusion Energy First Wall/Blanket/Shield Engineering Test Program. In response to EG and G queries, twelve organizations (in addition to EG and G and General Atomic) expressed interest in providing experimental facilities. A variety of methods of supplying heat is available.

  12. Atmospheric Radiation Measurement Program facilities newsletter, July 2001.; TOPICAL

    International Nuclear Information System (INIS)

    Holdridge, D. J.

    2001-01-01

    Global Warming and Methane-Global warming, an increase in Earth's near-surface temperature, is believed to result from the buildup of what scientists refer to as ''greenhouse gases.'' These gases include water vapor, carbon dioxide, methane, nitrous oxide, ozone, perfluorocarbons, hydrofluoro-carbons, and sulfur hexafluoride. Greenhouse gases can absorb outgoing infrared (heat) radiation and re-emit it back to Earth, warming the surface. Thus, these gases act like the glass of a greenhouse enclosure, trapping infrared radiation inside and warming the space. One of the more important greenhouse gases is the naturally occurring hydrocarbon methane. Methane, a primary component of natural gas, is the second most important contributor to the greenhouse effect (after carbon dioxide). Natural sources of methane include wetlands, fossil sources, termites, oceans, fresh-waters, and non-wetland soils. Methane is also produced by human-related (or anthropogenic) activities such as fossil fuel production, coal mining, rice cultivation, biomass burning, water treatment facilities, waste management operations and landfills, and domesticated livestock operations (Figure 1). These anthropogenic activities account for approximately 70% of the methane emissions to the atmosphere. Methane is removed naturally from the atmosphere in three ways. These methods, commonly referred to as sinks, are oxidation by chemical reaction with tropospheric hydroxyl ion, oxidation within the stratosphere, and microbial uptake by soils. In spite of their important role in removing excess methane from the atmosphere, the sinks cannot keep up with global methane production. Methane concentrations in the atmosphere have increased by 145% since 1800. Increases in atmospheric methane roughly parallel world population growth, pointing to anthropogenic sources as the cause (Figure 2). Increases in the methane concentration reduce Earth's natural cooling efficiency by trapping more of the outgoing

  13. SSC string test facility for superconducting magnets: Testing capabilities and program for collider magnets

    International Nuclear Information System (INIS)

    Kraushaar, P.; Burgett, W.; Dombeck, T.; McInturff, A.; Robinson, W.; Saladin, V.

    1993-05-01

    The Accelerator Systems String Test (ASST) R ampersand D Testing Facility has been established at the SSC Laboratory to test Collider and High Energy Booster (HEB) superconducting magnet strings. The facility is operational and has had two testing periods utilizing a half cell of collider prototypical magnets with the associated spool pieces and support systems. This paper presents a description of the testing capabilities of the facility with respect to components and supporting subsystems (cryogenic, power, quench protection, controls and instrumentation), the planned testing program for the collider magnets

  14. Spent Fuel Handling and Packaging Program: a survey of hot cell facilities

    International Nuclear Information System (INIS)

    Menon, M.N.

    1978-07-01

    Hot cell facilities in the United States were surveyed to determine their capabilities for conducting integral fuel assembly and individual fuel rod examinations that are required in support of the Spent Fuel Handling and Packaging Program. The ability to receive, handle, disassemble and reconstitute full-length light water reactor spent fuel assemblies, and the ability to conduct nondestructive and destructive examinations on full-length fuel rods were of particular interest. Three DOE-supported facilities and three commercial facilities were included in the survey. This report provides a summary of the findings

  15. Safety Assessment for LILW Near-Surface Disposal Facility Using the IAEA Reference Model and MASCOT Program

    International Nuclear Information System (INIS)

    Kim, Hyun Joo; Park, Joo Wan; Kim, Chang Lak

    2002-01-01

    A reference scenario of vault safety case prepared by the IAEA for the near-surface disposal facility of low-and intermediate-level radioactive wastes is assessed with the MASCOT program. The appropriate conceptual models for the MASCOT implementation is developed. An assessment of groundwater pathway through a drinking well as a geosphere-biosphere interface is performed first, then biosphere pathway is analysed to estimate the radiological consequences of the disposed radionuclides based on compartment modeling approach. The validity of conceptual modeling for the reference scenario is investigated where possible comparing to the results generated by the other assessment. The result of this study shows that the typical conceptual model for groundwater pathway represented by the compartment model can be satisfactorily used for safety assessment of the entire disposal system in a consistent way. It is also shown that safety assessment of a disposal facility considering complex and various pathways would be possible by the MASCOT program

  16. Multi-Function Waste Tank Facility Quality Assurance Program Plan, Project W-236A. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Hall, L.R.

    1995-05-30

    This document describes the Quality Assurance (QA) program for the Multi-Function Waste Tank Facility (MWTF) Project. The purpose of this QA program is to control project activities in such a manner as to achieve the mission of the MWTF Project in a safe and reliable manner. The QA program for the MWTF Project is founded on DOE Order 5700.6C, Quality Assurance, and implemented through the use of ASME NQA-1, Quality Assurance Program Requirements for Nuclear Facilities (ASME 1989 with addenda la-1989, lb-1991 and lc-1992). This document describes the program and planned actions which the Westinghouse Hanford Company (WHC) will implement to demonstrate and ensure that the project meets the requirements of DOE Order 5700.6C through the interpretive guidance of ASME NQA-1.

  17. Multi-Function Waste Tank Facility Quality Assurance Program Plan, Project W-236A. Revision 2

    International Nuclear Information System (INIS)

    Hall, L.R.

    1995-01-01

    This document describes the Quality Assurance (QA) program for the Multi-Function Waste Tank Facility (MWTF) Project. The purpose of this QA program is to control project activities in such a manner as to achieve the mission of the MWTF Project in a safe and reliable manner. The QA program for the MWTF Project is founded on DOE Order 5700.6C, Quality Assurance, and implemented through the use of ASME NQA-1, Quality Assurance Program Requirements for Nuclear Facilities (ASME 1989 with addenda la-1989, lb-1991 and lc-1992). This document describes the program and planned actions which the Westinghouse Hanford Company (WHC) will implement to demonstrate and ensure that the project meets the requirements of DOE Order 5700.6C through the interpretive guidance of ASME NQA-1

  18. Self-imposed self-assessment program at a DOE Nuclear Facility

    International Nuclear Information System (INIS)

    Geoffrion, R.R.; Loud, J.J.; Walter, E.C.

    1996-01-01

    The Nuclear Materials and Technology (NMT) Division at Los Alamos National Laboratory (LANL) has implemented a performance-based self-assessment program at the TA-55 plutonium facility. The program was conceptualized and developed by LANL's internal assessment group, AA-2. The management walkaround program fosters continuous improvement in NMT products and performance of its activities. The program, based on experience from the Institute of Nuclear Power Operations, is endorsed at the site by the U.S. Department of Energy (DOE) Environment, Safety, and Health (ES ampersand H) personnel and by the Defense Nuclear Facility Safety Board. The self-assessment program focuses on how work is actually performed rather than on paperwork or process compliance. Managers critically and continually assess ES ampersand H, conduct of operations, and other functional area requirements

  19. Investigating attitudes to hydrogen refuelling facilities and the social cost to local residents

    International Nuclear Information System (INIS)

    O'Garra, Tanya; Mourato, Susana; Pearson, Peter

    2008-01-01

    Vehicles fuelled by hydrogen (H 2 ) have attracted increasing attention because of their potentially enhanced environmental profiles. Their penetration into the vehicle stock will be influenced by the spread of refuelling facilities. This study investigates local attitudes towards the proposed installation of H 2 storage facilities at existing refuelling stations throughout London. Using multinomial logit analysis, we identify the determinants of attitudes. Results suggest that residents living very close to a proposed H 2 facility are less likely to be opposed than residents living 200-500 m away. Opposition appears to be determined by a lack of trust in safety regulations, non-environmental attitudes, and concerns about the existing local refuelling station. The social cost to local residents of a local H 2 storage facility was estimated using a method developed by Atkinson et al. [2004. 'Amenity' or 'eyesore'? Negative willingness to pay for options to replace electricity transmission towers. Applied Economics Letters 11(4), 203-208], which elicits the amount of time respondents are willing to commit to oppose a new facility development. Using the leisure rate of time, the social cost is estimated at just under Pounds 14 per local opposed resident. Add to this the WTP to support opposition efforts by a local group, and the value comes to just under Pounds 25 per opposed resident

  20. Experimental program for the Fast Breeder Blanket Facility, FBBF

    International Nuclear Information System (INIS)

    Ott, K.O.; Clikeman, F.M.; Johnson, R.H.; Borg, R.C.

    1976-01-01

    The work performed in the reporting period was primarily concerned with the development of the experimental program (Task A) and with the pre-analysis of future loadings and the impact upon the permanent loading of the two converter regions, which contain 4.8 percent enriched UO 2 rods. It appears necessary that a neutron poison (B 4 C) be placed in the converter (transformer) regions in order to hold, also for future loadings, the k/sub eff/ of a hypothetically flooded FBBF well below 1. Since it is planned to use the same welded converter regions for all experiments, the required B 4 C loading needs to be determined prior to the first blanket loading. Further the equipment needs have been identified (Task D), the 252 Cf-source has been requested on a loan basis (Task E). First discussions with ANL on blanket experiments have been initiated

  1. INVESTIGATION OF QUANTIFICATION OF FLOOD CONTROL AND WATER UTILIZATION EFFECT OF RAINFALL INFILTRATION FACILITY BY USING WATER BALANCE ANALYSIS MODEL

    OpenAIRE

    文, 勇起; BUN, Yuki

    2013-01-01

    In recent years, many flood damage and drought attributed to urbanization has occurred. At present infiltration facility is suggested for the solution of these problems. Based on this background, the purpose of this study is investigation of quantification of flood control and water utilization effect of rainfall infiltration facility by using water balance analysis model. Key Words : flood control, water utilization , rainfall infiltration facility

  2. LLE 1998 annual report, October 1997 -September 1998. Inertial fusion program and National Laser Users' Facility program

    International Nuclear Information System (INIS)

    1999-01-01

    This report summarizes research at the Laboratory for Laser Energetics (LLE), the operation of the National Laser Users' Facility (NLUF), and programs involving the education of high school, undergraduate, and graduate students for FY98. Research summaries cover: progress in laser fusion; diagnostic development; laser and optical technology; and advanced technology for laser targets

  3. LLE 1998 annual report, October 1997--September 1998. Inertial fusion program and National Laser Users` Facility program

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-01-01

    This report summarizes research at the Laboratory for Laser Energetics (LLE), the operation of the National Laser Users` Facility (NLUF), and programs involving the education of high school, undergraduate, and graduate students for FY98. Research summaries cover: progress in laser fusion; diagnostic development; laser and optical technology; and advanced technology for laser targets.

  4. Interactive house investigation and radon diagnostics computer program

    International Nuclear Information System (INIS)

    Gillette, L.M.

    1990-01-01

    This paper reports on the interactive computer program called Dungeons and Radon which was developed as part of the Environmental Protection Agency's (EPA's) Radon Contractor Proficiency (RCP) Program's Radon Technology for Mitigators (RTM) course which is currently being offered in the Regional Radon Training Centers (RRTCs). The program was designed by Terry Brennan to be used in training radon mitigation contractors. The Macintosh based program consists of a series of animated, sound and voice enhanced house scenes. The participants choose where and what to investigate and where to perform diagnostic tests in order to gather enough information to design a successful mitigation system

  5. Atmospheric radiation measurement program facilities newsletter, September 2001.; TOPICAL

    International Nuclear Information System (INIS)

    Holdridge, D. J.

    2001-01-01

    Our Changing Climate-Is our climate really changing? How do we measure climate change? How can we predict what Earth's climate will be like for generations to come? One focus of the Atmospheric Radiation Measurement (ARM) Program is to improve scientific climate models enough to achieve reliable regional prediction of future climate. According to the Environmental Protection Agency (EPA), the global mean surface temperature has increased by 0.5-1.0 F since the late 19th century. The 20th century's 10 warmest years all occurred in the last 15 years of the century, with 1998 being the warmest year of record. The global mean surface temperature is measured by a network of temperature-sensing instruments distributed around the world, including ships, ocean buoys, and weather stations on land. The data from this network are retrieved and analyzed by various organizations, including the National Aeronautics and Space Administration, the National Oceanic and Atmospheric Administration, and the World Meteorological Organization. Worldwide temperature records date back to 1860. To reconstruct Earth's temperature history before 1860, scientists use limited temperature records, along with proxy indicators such as tree rings, pollen records, and analysis of air frozen in ancient ice. The solar energy received from the sun drives Earth's weather and climate. Some of this energy is reflected and filtered by the atmosphere, but most is absorbed by Earth's surface. The absorbed solar radiation warms the surface and is re-radiated as heat energy into the atmosphere. Some atmospheric gases, called greenhouse gases, trap some of the re-emitted heat, keeping the surface temperature regulated and suitable for sustaining life. Although the greenhouse effect is natural, some evidence indicates that human activities are producing increased levels of some greenhouse gases such as carbon dioxide, methane, and nitrous oxide. Scientists believe that the combustion of fossil fuels is

  6. 200 Areas Remedial Investigation/Feasibility Study Implementation Plan - Environmental Restoration Program

    International Nuclear Information System (INIS)

    Knepp, A. J.

    1999-01-01

    The 200 Areas Remedial Investigation/Feasibility Study Implementation Plan - Environmental Restoration Program (Implementation Plan) addresses approximately 700 soil waste sites (and associated structures such as pipelines) resulting from the discharge of liquids and solids from processing facilities to the ground (e.g., ponds, ditches, cribs,burial grounds) in the 200 Areas and assigned to the Environmental Restoration Program. The Implementation Plan outlines the framework for implementing assessment activities in the 200 Areas to ensure consistency in documentation, level of characterization, and decision making. The Implementation Plan also consolidates background information and other typical work plan materials, to serve as a single referenceable source for this type of information

  7. Establishing cyber security programs for I and C systems at nuclear facilities

    International Nuclear Information System (INIS)

    Waedt, Karl

    2012-01-01

    In recent years, across the international nuclear community, cyber security issues have quickly gained significant attention from safety authorities and plant designers alike. This increased attention was accelerated by news of the Stuxnet virus, which impaired control systems at Iranian nuclear facilities in 2010, but is also fueled by regular news about cyber security breaches of data systems at large business corporations. This paper discusses key aspects of establishing a cyber security program for Instrumentation and Control (I and C) systems at a nuclear facility, and identifies inherent aspects of nuclear power plant (NPP) design, that differentiate the needs of such a cyber security program from those of typical corporate data systems. (orig.)

  8. Development programs on decommissioning technology for reactors and fuel cycle facilities in Japan

    International Nuclear Information System (INIS)

    Fujiki, K.

    1992-01-01

    The Science and Technology Agency (STA) of Japan is promoting technology development for decommissioning of nuclear facilities by entrusting various research programs to concerned research organisations: JAERI, PNC and RANDEC, including first full scale reactor decommissioning of JPDR. According to the results of these programs, significant improvement on dismantling techniques, decontamination, measurement etc. has been achieved. Further development of advanced decommissioning technology has been started in order to achieve reduction of duration of decommissioning work and occupational exposures in consideration of the decommissioning of reactors and fuel cycle facilities. (author) 5 refs.; 7 figs.; 1 tab

  9. Establishing cyber security programs for I and C systems at nuclear facilities

    Energy Technology Data Exchange (ETDEWEB)

    Waedt, Karl [AREVA NP GmbH (Germany)

    2012-11-01

    In recent years, across the international nuclear community, cyber security issues have quickly gained significant attention from safety authorities and plant designers alike. This increased attention was accelerated by news of the Stuxnet virus, which impaired control systems at Iranian nuclear facilities in 2010, but is also fueled by regular news about cyber security breaches of data systems at large business corporations. This paper discusses key aspects of establishing a cyber security program for Instrumentation and Control (I and C) systems at a nuclear facility, and identifies inherent aspects of nuclear power plant (NPP) design, that differentiate the needs of such a cyber security program from those of typical corporate data systems. (orig.)

  10. Atmospheric radiation measurement program facilities newsletter, April 2001.; TOPICAL

    International Nuclear Information System (INIS)

    Holdridge, D. J.

    2001-01-01

    ) Validation Campaign-Researchers from Lawrence Berkeley National Laboratory in California will be deploying instruments at the CART site in May. Portable micrometeorology towers will be used to measure fluxes of carbon dioxide, water, and heat between the surface and the atmosphere. The exchange of these constituents varies with regional climate, soil type, and surface vegetation. Greater knowledge will improve the accuracy of computer models (and hence predictions) of the exchanges. Measurements made with the portable instruments will be compared with measurements being collected by instruments at the central facility. AWS Campaign-The State University of New York at Albany will deploy an oxygen A-band and water vapor band spectrometer (AWS) at the CART site on May 20-June 30, 2001. Measurements made by the AWS will be used to determine absorption of radiation by water vapor within clouds, a quantity important to understanding the behavior of solar radiation as it passes through clouds

  11. Final work plan : investigation of potential contamination at the former USDA facility in Powhattan, Kansas.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M.; Environmental Science Division

    2007-02-02

    This Work Plan outlines the scope of work to be conducted to investigate the subsurface contaminant conditions at the property formerly leased by the Commodity Credit Corporation (CCC) in Powhattan, Kansas (Figure 1.1). Data obtained during this event will be used to (1) evaluate potential contaminant source areas on the property; (2) determine the vertical and horizontal extent of potential contamination; and (3) provide recommendations for future action, with the ultimate goal of assigning this site No Further Action status. The planned investigation includes groundwater monitoring requested by the Kansas Department of Health and Environment (KDHE), in accordance with Section V of the Intergovernmental Agreement between the KDHE and the Farm Service Agency of the U.S. Department of Agriculture (USDA). The work is being performed on behalf of the CCC/USDA by the Environmental Science Division of Argonne National Laboratory. A nonprofit, multidisciplinary research center operated by the University of Chicago for the U.S. Department of Energy, Argonne provides technical assistance to the CCC/USDA with environmental site characterization and remediation at former CCC/USDA grain storage facilities. Argonne issued a Master Work Plan (Argonne 2002) that has been approved by the KDHE. The Master Work Plan describes the general scope of all investigations at former CCC/USDA facilities in Kansas and provides guidance for these investigations. It should be consulted for the complete details of plans for work associated with the former CCC/USDA facility at Powhattan.

  12. The LEU target development and conversion program for the MAPLE reactors and new processing facility

    International Nuclear Information System (INIS)

    Malkoske, G.R.

    2003-01-01

    The availability of isotope grade, Highly Enriched Uranium (HEU), from the United States for use in the manufacture of targets for molybdenum-99 production in AECL's NRU research reactor has been a key factor to enable MDS Nordion to develop a reliable, secure supply of medical isotopes for the international nuclear medicine community. The molybdenum extraction process from HEU targets is a proven and established method that has reliably produced medical isotopes for several decades. The HEU process provides predictable, consistent yields for our high-volume, molybdenum-99 production. Other medical isotopes such as I-131 and Xe-133, which play an important role in nuclear medicine applications, are also produced from irradiated HEU targets as a by-product of the molybdenum-99 process. To ensure a continued reliable and timely supply of medical isotopes, MDS Nordion is completing the commissioning of two MAPLE reactors and an associated isotope processing facility (the New Processing Facility). The new MAPLE facilities, which will be dedicated exclusively to medical isotope production, will provide an essential contribution to a secure, robust global healthcare system. Design and construction of these facilities has been based on a life cycle management philosophy for the isotope production process. This includes target irradiation, isotope extraction and waste management. The MAPLE reactors will operate with Low Enriched Uranium (LEU) fuel, a significant contribution to the objectives of the RERTR program. The design of the isotope production process in the MAPLE facilities is based on an established process - extraction of isotopes from HEU target material. This is a proven technology that has been demonstrated over more than three decades of operation. However, in support of the RERTR program and in compliance with U.S. legislation, MDS Nordion has undertaken a LEU Target Development and Conversion Program for the MAPLE facilities. This paper will provide an

  13. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    1991-09-01

    The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

  14. Yearly program of safety research for nuclear facilities and others

    International Nuclear Information System (INIS)

    1987-01-01

    The development of FBRs in Japan has steadily progressed, and subsequently to the experimental reactor 'Joyo' and the prototype reactor 'Monju', by promoting the construction of a demonstration reactor, the stage of verifying and acquiring skill of the electricity generation plant technology of practical scale, improving the performance and establishing the economical efficiency is about to begin. The development of FBRs in Japan has been advanced independently as a national project, and the method of preventing accidents in the actual reactors has been thoroughly taken. 'On the way of thinking in the safety evaluation of FBRs' was decided by the Nuclear Safety Commission. When the safety research from 1987 is systematized, as the constituents of safety logic, the way of thinking of the defense in depth, the way of thinking of the classification according to importance, the way of thinking of multilayer barriers against radioactive substances, and the way of thinking on severe accidents were investigated. The research concerning the decision of safety design and evaluation policy, and the safety research regarding accident prevention and relaxation, accident evaluation and severe accidents are reported. (Kako, I.)

  15. User Delay Cost Model and Facilities Maintenance Cost Model for a Terminal Control Area : Volume 3. User's Manual and Program Documentation for the Facilities Maintenance Cost Model

    Science.gov (United States)

    1978-05-01

    The Facilities Maintenance Cost Model (FMCM) is an analytic model designed to calculate expected annual labor costs of maintenance within a given FAA maintenance sector. The model is programmed in FORTRAN IV and has been demonstrated on the CDC Krono...

  16. Facility Design and Health Management Program at the Sinnhuber Aquatic Research Laboratory.

    Science.gov (United States)

    Barton, Carrie L; Johnson, Eric W; Tanguay, Robert L

    2016-07-01

    The number of researchers and institutions moving to the utilization of zebrafish for biomedical research continues to increase because of the recognized advantages of this model. Numerous factors should be considered before building a new or retooling an existing facility. Design decisions will directly impact the management and maintenance costs. We and others have advocated for more rigorous approaches to zebrafish health management to support and protect an increasingly diverse portfolio of important research. The Sinnhuber Aquatic Research Laboratory (SARL) is located ∼3 miles from the main Oregon State University campus in Corvallis, Oregon. This facility supports several research programs that depend heavily on the use of adult, larval, and embryonic zebrafish. The new zebrafish facility of the SARL began operation in 2007 with a commitment to build and manage an efficient facility that diligently protects human and fish health. An important goal was to ensure that the facility was free of Pseudoloma neurophilia (Microsporidia), which is very common in zebrafish research facilities. We recognize that there are certain limitations in space, resources, and financial support that are institution dependent, but in this article, we describe the steps taken to build and manage an efficient specific pathogen-free facility.

  17. 21 CFR 1000.55 - Recommendation for quality assurance programs in diagnostic radiology facilities.

    Science.gov (United States)

    2010-04-01

    ... facilities where more than one department operates x-ray equipment, to the chief medical officer of the..., improved image quality, and/or financial savings will compensate for the resources required for the program... generally be delegated a basic quality assurance role by the practitioner in charge. Responsibility for...

  18. Spent fuel receipt and lag storage facility for the spent fuel handling and packaging program

    International Nuclear Information System (INIS)

    Black, J.E.; King, F.D.

    1979-01-01

    Savannah River Laboratory (SRL) is participating in the Spent Fuel Handling and Packaging Program for retrievable, near-surface storage of spent light water reactor (LWR) fuel. One of SRL's responsibilities is to provide a technical description of the wet fuel receipt and lag storage part of the Spent Fuel Handling and Packaging (SFHP) facility. This document is the required technical description

  19. 78 FR 26879 - Medicare Program; Inpatient Rehabilitation Facility Prospective Payment System for Federal Fiscal...

    Science.gov (United States)

    2013-05-08

    ... Prospective Payment System for Federal Fiscal Year 2014; Proposed Rule #0;#0;Federal Register / Vol. 78, No... Program; Inpatient Rehabilitation Facility Prospective Payment System for Federal Fiscal Year 2014 AGENCY... IRF prospective payment system's (PPS) case-mix groups and a description of the methodology and data...

  20. Minnesota's Nursing Facility Performance-Based Incentive Payment Program: An Innovative Model for Promoting Care Quality

    Science.gov (United States)

    Cooke, Valerie; Arling, Greg; Lewis, Teresa; Abrahamson, Kathleen A.; Mueller, Christine; Edstrom, Lisa

    2010-01-01

    Purpose: Minnesota's Nursing Facility Performance-Based Incentive Payment Program (PIPP) supports provider-initiated projects aimed at improving care quality and efficiency. PIPP moves beyond conventional pay for performance. It seeks to promote implementation of evidence-based practices, encourage innovation and risk taking, foster collaboration…

  1. A Guide for Planning Facilities for Occupational Preparation Programs in Metallurgy Technology. Interim Report. Research 28.

    Science.gov (United States)

    German, Carl, Jr.

    The major purpose of this guide is to elicit the information necessary for writing educational specifications for facilities to house technical education programs in metallurgy. It is organized in these parts: (1) Part I discusses the major purpose, underlying assumptions, recent instructional trends, and guiding principles utilized in the…

  2. Type B investigation report of curium-244 exposure at the ORNL TRU Facility, January 15, 1986

    International Nuclear Information System (INIS)

    Love, G.L.; Butler, H.M.; Duncan, D.T.; Oakes, T.W.

    1986-04-01

    This Type B Investigative Report provides an evaluation of relevant events and activities that led to, were a part of, or resulted from the release of curium-244 in the Building 7920 facility at ORNL in January 1986. Impacts have been evaluated with respect to employee exposures and the costs and loss of productivity resulting from increased bioassay analyses and activities of investigative committees. Management systems evaluated include (1) training of employees performing lab analyses, (2) adherence to procedures, and (3) response to unusual circumstances

  3. Investigation on Transmission and Substation Facilities of Sichuan Power Grid in Wenchuan Earthquake

    Institute of Scientific and Technical Information of China (English)

    Yu Yongqing; Li Guangfan; Li Peng; Zhu Quanjun; Yuan Dalu; Wang Chengyu; Li Jinzhong; Huang Huang; Li Lixin; Zhang Xinghai; Liu Jingmin

    2009-01-01

    @@ On May 12,2008,an earthquake of Ms 8.0 hit the area around Wenchuan County,Sichuan Province,China.It has been one of the most destructive earthquakes since the founding of P.R.China in 1949.The quake caused not only tremendous loss of life and wealth,but also severe damage to transmission and substation facilities.After the disaster,an expert group from China Electric Power Research Institute (CEPRI)was sent for on-site investigation.This paper is a summary of the investigation,in which suggestions for electric equipment to resist earthquake disasters are also proponed.

  4. Working program for deep borehole investigations. HDB-6,7,8, borehole

    International Nuclear Information System (INIS)

    Hama, Katsuhiro; Takahashi, Kazuharu; Ishii, Eiichi; Takeuchi, Ryuji; Sasaki, Manabu; Kunimaru, Takanori; Eki, Nobuhiro; Matsui, Hiroya

    2003-08-01

    In the Horonobe Underground Research Laboratory project, a wide range of geoscientific research and development activities are planned to be performed in three phases, Surface-based Investigations (Phase I), Construction (Phase II) and Operations (Phase III), over period of 20 years. Surface-based investigations have been conducted since 2000. Main goals of the Horonobe project are; To establish comprehensive techniques for investigating the geological environment, and To develop a range of engineering techniques for deep underground applications. The specific goals of the surface-based investigations are, To construct geological models of the geological environment based on the surface-based investigations and develop an understanding of the deep geological environment (undisturbed, initial conditions) before excavation of the shaft and experimental drifts To formulate detailed design and plans for the construction of the shaft and experimental drifts, and To plan scientific investigations during the construction phase. Field investigations during the surface-based investigations phase are planned for completion by the end of 2005, with excavation of the main shaft, Phase 2 construction, planned to start in 2005. The diameter of the main shafts has provisionally been set at 6.5 meters and the proposed depth is 500 meters. Details of the geometry and depth of specific underground facilities, including the main shaft, the ventilation shaft and the drifts, will be defined using data on the geological environment obtained during the surface-based investigation phase. As part of the surface-based investigations, geological, geophysical, hydrogeological, hydrochemical and rock mechanical investigations were carried out. Deep borehole investigations started in 2000 in order to characterize the sedimentary rocks. Taking into account the status of the investigations as of April 2003 and the remaining time (i.e., three year) for the surface-based investigations, an

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

    International Nuclear Information System (INIS)

    Bissani, M; O'Kelly, D S

    2006-01-01

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

  6. Segmented fuel irradiation program: investigation on advanced materials

    International Nuclear Information System (INIS)

    Uchida, H.; Goto, K.; Sabate, R.; Abeta, S.; Baba, T.; Matias, E. de; Alonso, J.

    1999-01-01

    The Segmented Fuel Irradiation Program, started in 1991, is a collaboration between the Japanese organisations Nuclear Power Engineering Corporation (NUPEC), the Kansai Electric Power Co., Inc. (KEPCO) representing other Japanese utilities, and Mitsubishi Heavy Industries, Ltd. (MHI); and the Spanish Organisations Empresa Nacional de Electricidad, S.A. (ENDESA) representing A.N. Vandellos 2, and Empresa Nacional Uranio, S.A. (ENUSA); with the collaboration of Westinghouse. The objective of the Program is to make substantial contribution to the development of advanced cladding and fuel materials for better performance at high burn-up and under operational power transients. For this Program, segmented fuel rods were selected as the most appropriate vehicle to accomplish the aforementioned objective. Thus, a large number of fuel and cladding combinations are provided while minimising the total amount of new material, at the same time, facilitating an eventual irradiation extension in a test reactor. The Program consists of three major phases: phase I: design, licensing, fabrication and characterisation of the assemblies carrying the segmented rods (1991 - 1994); phase II: base irradiation of the assemblies at Vandellos 2 NPP, and on-site examination at the end of four cycles (1994-1999). Phase III: ramp testing at the Studsvik facilities and hot cell PIE (1996-2001). The main fuel design features whose effects on fuel behaviour are being analysed are: alloy composition (MDA and ZIRLO vs. Zircaloy-4); tubing texture; pellet grain size. The Program is progressing satisfactorily as planned. The base irradiation is completed in the first quarter of 1999, and so far, tests and inspections already carried out are providing useful information on the behaviour of the new materials. Also, the Program is delivering a well characterized fuel material, irradiated in a commercial reactor, which can be further used in other fuel behaviour experiments. The paper presents the main

  7. Report of preliminary investigations on the next-generation large-scale synchrotron radiation facility projects

    International Nuclear Information System (INIS)

    1990-01-01

    The Special Committee for Future Project of the Japanese Society for Synchrotron Radiation Research investigated the construction-projects of the large-scaled synchrotron radiation facilities which are presently in progress in Japan. As a result, the following both projects are considered the very valuable research-project which will carry the development of Japan's next-generation synchrotron radiation science: 1. the 8 GeV synchrotron radiation facilities (SPring-8) projected to be constructed by Japan Atomic Energy Research Institute and the Institute of Physical and Chemical Research under the sponsorship of Science Technology Agency at Harima Science Park City, Hyogo Pref., Japan. 2. The project to utilize the Tristan Main Ring (MR) of the National Laboratory for High Energy Physics as the radiation source. Both projects are unique in research theme and technological approach, and complemental each other. Therefore it has been concluded that both projects should be aided and ratified by the Society. (M.T.)

  8. Investigating proton emitters at the limits of stability with radioactive beams from the Oak Ridge facility

    Energy Technology Data Exchange (ETDEWEB)

    Toth, K.S. [Oak Ridge National Lab., TN (United States); Batchelder, J.C.; Zganjar, E.F. [Louisiana State Univ., Baton Rouge, LA (United States); Bingham, C.R.; Wauters, J. [Tennessee Univ., Knoxville, TN (United States); Davinson, T.; MacKenzie, J.A.; Woods, P.J. [Edinburgh Univ. (United Kingdom)

    1996-10-01

    By using beams from the Holifield Radioactive Ion Beam Facility at ORNL, it should be possible to identify many new ground-state proton emitters in the mass region from Sn to Pb. In these investigations nuclei produced in fusion-evaporation reactions will be separated from incident ions and dispersed in mass/charge with a recoil mass separator and then implanted into a double-sided Si strip detector for study of proton (and {alpha}-particle) radioactivity. This paper summarizes data presently extant on proton emitters and then focuses on tests and initial experiments that will be carried out with stable beams and with radioactive ions as they are developed at the Oak Ridge facility.

  9. Investigation of development and management of treatment planning systems for BNCT at foreign facilities

    International Nuclear Information System (INIS)

    2001-03-01

    A new computational dosimetry system for BNCT: JCDS is developed by JAERI in order to carry out BNCT with epithermal neutron beam at present. The development and management situation of computational dosimetry system, which are developed and are used in BNCT facilities in foreign countries, were investigated in order to accurately grasp functions necessary for preparation of the treatment planning and its future subjects. In present state, 'SERA', which are developed by Idaho National Engineering and Environmental Laboratory (INEEL), is used in many BNCT facilities. Followings are necessary for development and management of the treatment planning system. (1) Reliability confirmation of system performance by verification as comparison examination of calculated value with actual experimental measured value. (2) Confirmation systems such as periodic maintenance for retention of the system quality. (3) The improvement system, which always considered relative merits and demerits with other computational dosimetry system. (4) The development of integrated system with patient setting. (author)

  10. Field Investigation Plan for 1301-N and 1325-N Facilities Sampling to Support Remedial Design

    International Nuclear Information System (INIS)

    Weiss, S. G.

    1998-01-01

    This field investigation plan (FIP) provides for the sampling and analysis activities supporting the remedial design planning for the planned removal action for the 1301-N and 1325-N Liquid Waste Disposal Facilities (LWDFs), which are treatment, storage,and disposal (TSD) units (cribs/trenches). The planned removal action involves excavation, transportation, and disposal of contaminated material at the Environmental Restoration Disposal Facility (ERDF).An engineering study (BHI 1997) was performed to develop and evaluate various options that are predominantly influenced by the volume of high- and low-activity contaminated soil requiring removal. The study recommended that additional sampling be performed to supplement historical data for use in the remedial design

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

    International Nuclear Information System (INIS)

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

    2011-08-01

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

  12. Horonobe underground research program. Research report of 2002 FY investigation

    International Nuclear Information System (INIS)

    2003-06-01

    Main results of investigation about Horonobe deep underground research center in 2002 FY were reported. It consists of six chapters: introduction, main results, selection of research center area, underground science research, R and D of geological disposal, and the environmental survey and research center on the ground. The research center area at about 3 km north of Horonobe (B1) was selected in the four areas: A, B1, B2 and C on the basis of data, researches in the sky, aboveground and underground and other conditions. The model of geological environment was constructed by physical, geological, surface water supply researches. Development of geological environment monitoring techniques, investigation of long stabilization of geological environment and design of underground facilities are reported. The basic design of preparation of research center was investigated. (S.Y.)

  13. PWR blowdown heat transfer separate-effects program: Thermal-Hydraulic Test Facility experimental data report for test 100

    International Nuclear Information System (INIS)

    White, M.D.; Hedrick, R.A.

    1977-01-01

    Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 100, which is part of the ORNL Pressurized-Water-Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in a PWR system. Test 100 was conducted to investigate the response of heater rod bundle 1 and instrumented spool pieces with flow homogenizing screens to a double-ended rupture with equal break areas at the test section inlet and outlet. The primary purpose of this report is to make the reduced instrument responses during test 100 available. The responses are presented in graphical form in engineering units and have been analyzed only to the extent necessary to assure reasonableness and consistency

  14. Construction program for a large superconducting MHD magnet system at the coal-fired flow facility

    International Nuclear Information System (INIS)

    Wang, S.T.; Genens, L.; Gonczy, J.; Ludwig, H.; Lieberg, M.; Kraft, E.; Gacek, D.; Huang, Y.C.; Chen, C.J.

    1980-01-01

    The Argonne National Laboratory has designed and is constructing a 6 T large aperture superconducting MHD magnet for use in the Coal-Fired Flow Facility (CFFF) at the University of Tennessee Space Institute (UTSI) at Tullahoma, Tennessee. The magnet system consists of the superconducting magnet, a magnet power supply, an integrated instrumentation for operation, control and protection, and a complete cryogenic facility including a CTI Model 2800 helium refrigerator/liquefier with two compressors, helium gas handling system and a 7500 liter liquid helium dewar. The complete system will be tested at Argonne, IL in 1981. The magnet design is reviewed, and the coil fabrication programs are described in detail

  15. Development and implementation of the waste diversion program at MDS Nordion's Cobalt Operations Facility

    International Nuclear Information System (INIS)

    Wasiak, T.

    2004-01-01

    Historically, the MDS Nordion (MDSN) Cobalt Operations Facility sent solid waste for disposal to Atomic Energy of Canada Ltd.'s Chalk River Laboratories (AECL-CRL). A large portion of this waste was not contaminated. Because this non-contaminated waste originated in the 'active area' of the MDSN facility, it was routinely disposed of as low-level active waste. In 2002, MDSN undertook an initiative to develop and implement a more sophisticated and more economical waste management program. The Waste Diversion Program (WDP) ensures continued environmental and public protection, and reduces the demand on Canada's limited capacity for storage of radioactive material and the associated operating costs. The goal of the WDP is to reduce the volume of waste currently being shipped to AECL-CRL's Waste Management Operation as low-level active waste. The presentation discusses key elements of both the development and the implementation of WDP. It focuses on the following areas: the regulatory environment surrounding the waste disposal issues in Canada and abroad. Methods used by MDSN for determination of radionuclides, which could be present in the facility. Choice of equipment and calculation of individual alarm levels for each identified radionuclide. Key elements of the practical implementation of the program. CNSC Regulatory approval process. The bottom line - dollars and cents. The primary objective of the WDP is to ensure that only waste, which meets regulatory requirements, is diverted from the solid active waste stream. This has been successfully accomplished in MDSN's Cobalt Operations Facility. The objective of the presentation is to share the knowledge and experience obtained in the development process, and thus provide a guideline for other nuclear facilities interested in establishing similar proactive and cost effective programs. (author)

  16. Final work plan : supplemental upward vapor intrusion investigation at the former CCC/USDA grain storage facility in Hanover, Kansas.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M.; Environmental Science Division

    2008-12-15

    The Commodity Credit Corporation (CCC), an agency of the U.S. Department of Agriculture (USDA), operated a grain storage facility at the northeastern edge of the city of Hanover, Kansas, from 1950 until the early 1970s. During this time, commercial grain fumigants containing carbon tetrachloride were in common use by the grain storage industry to preserve grain in their facilities. In February 1998, trace to low levels of carbon tetrachloride (below the maximum contaminant level [MCL] of 5.0 {micro}g/L) were detected in two private wells near the former grain storage facility at Hanover, as part of a statewide USDA private well sampling program that was implemented by the Kansas Department of Health and Environment (KDHE) near former CCC/USDA facilities. In 2007, the CCC/USDA conducted near-surface soil sampling at 61 locations and also sampled indoor air at nine residences on or adjacent to its former Hanover facility to address the residents concerns regarding vapor intrusion. Low levels of carbon tetrachloride were detected at four of the nine homes. The results were submitted to the KDHE in October 2007 (Argonne 2007). On the basis of the results, the KDHE requested sub-slab sampling and/or indoor air sampling (KDHE 2007). This Work Plan describes, in detail, the proposed additional scope of work requested by the KDHE and has been developed as a supplement to the comprehensive site investigation work plan that is pending (Argonne 2008). Indoor air samples collected previously from four homes at Hanover were shown to contain the carbon tetrachloride at low concentrations (Table 2.1). It cannot be concluded from these previous data that the source of the detected carbon tetrachloride is vapor intrusion attributable to former grain storage operations of the CCC/USDA at Hanover. The technical objective of the vapor intrusion investigation described here is to assess the risk to human health due to the potential for upward migration of carbon tetrachloride and

  17. Cultural Resource Investigations for the Remote Handled Low Level Waste Facility at the Idaho National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Brenda R. Pace; Hollie Gilbert; Julie Braun Williams; Clayton Marler; Dino Lowrey; Cameron Brizzee

    2010-06-01

    The U. S. Department of Energy, Idaho Operations Office is considering options for construction of a facility for disposal of Idaho National Laboratory (INL) generated remote-handled low-level waste. Initial screening has resulted in the identification of two recommended alternative locations for this new facility: one near the Advanced Test Reactor (ATR) Complex and one near the Idaho Comprehensive Environmental Response, Compensation, and Liability Act Disposal Facility (ICDF). In April and May of 2010, the INL Cultural Resource Management Office conducted archival searches, intensive archaeological field surveys, and initial coordination with the Shoshone-Bannock Tribes to identify cultural resources that may be adversely affected by new construction within either one of these candidate locations. This investigation showed that construction within the location near the ATR Complex may impact one historic homestead and several historic canals and ditches that are potentially eligible for nomination to the National Register of Historic Places. No resources judged to be of National Register significance were identified in the candidate location near the ICDF. Generalized tribal concerns regarding protection of natural resources were also documented in both locations. This report outlines recommendations for protective measures to help ensure that the impacts of construction on the identified resources are not adverse.

  18. In situ TEM-tandem/implanter interface facility in Wuhan University for investigation of radiation effects

    International Nuclear Information System (INIS)

    Guo Liping; Li Ming; Liu Chuansheng; Song Bo; Ye Mingsheng; Fan Xiangjun; Fu Dejun

    2007-01-01

    Transmission electron microscope (TEM) interfaced to one or more ion implanters and/or accelerators, i.e. in situ TEM, provides effective tools to observe microstructural changes of studied samples during the ion irradiation. Evolution of both radiation damages and irradiation-induced nano-sized microstructures can be investigated with this technique, much more convenient than conventional ex situ techniques. In situ TEM technique has been widely applied in various fields, especially in the study of radiation damages of structural materials of fission and fusion nuclear reactors, and in evaluation and qualification of radioactive waste forms. Nowadays there are more than a dozen such facilities located in Japan, France, and the United States. Recently, we have constructed the first TEM-Tandem/Implanter interface facility of China in Wuhan University. A modified Hitachi H800 TEM was interfaced to a 200 kV ion implanter and a 2 x 1.7 MV tandem accelerator. Effective steps were taken to isolate the TEM from mechanical vibration from the ion beam line, and no obvious wobbling of the TEM image was observed during the ion implantation. The amorphization process of Si crystal irradiated by 115 keV N + ion beam was observed in the primary experiments, demonstrating that this interface facility is capable of in situ study of radiation effects. An online low energy gaseous ion source which may provide 1-20 keV H + and He + is under construction. (authors)

  19. Investigation of high flux test module for the international fusion materials irradiation facilities (IFMIF)

    International Nuclear Information System (INIS)

    Miyashita, Makoto; Sugimoto, Masayoshi; Yutani, Toshiaki

    2007-03-01

    This report describes investigation on structure of a high neutron flux test module (HFTM) for the International Fusion Materials Irradiation Facilities (IFMIF). The HFTM is aimed for neutron irradiation of a specimen in a high neutron flux domain of the test cell for irradiation ground of IFMIF. We investigated the overall structure of the HFTM that was able to include specimens in a rig and thermocouple arrangement, an interface of control signal and support structure. Moreover, pressure and the amount of the bend in the module vessel (a rectangular section pressure vessel) were calculated. The module vessel did a rectangular section from limitation of a high neutron flux domain. Also, we investigated damage of thermocouples under neutron irradiation, which was a temperature sensor of irradiation materials temperature control demanded high precision. Based on these results, drawings on the HTFM structure. (author)

  20. Sandia National Laboratories support of the Iraq Nuclear Facility Dismantlement and Disposal Program.

    Energy Technology Data Exchange (ETDEWEB)

    Cochran, John Russell; Danneels, Jeffrey John

    2009-03-01

    Because of past military operations, lack of upkeep and looting there are now enormous radioactive waste problems in Iraq. These waste problems include destroyed nuclear facilities, uncharacterized radioactive wastes, liquid radioactive waste in underground tanks, wastes related to the production of yellow cake, sealed radioactive sources, activated metals and contaminated metals that must be constantly guarded. Iraq currently lacks the trained personnel, regulatory and physical infrastructure to safely and securely manage these facilities and wastes. In 2005 the International Atomic Energy Agency (IAEA) agreed to organize an international cooperative program to assist Iraq with these issues. Soon after, the Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) was initiated by the U.S. Department of State (DOS) to support the IAEA and assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials. The Iraq NDs Program is providing support for the IAEA plus training, consultation and limited equipment to the GOI. The GOI owns the problems and will be responsible for implementation of the Iraq NDs Program. Sandia National Laboratories (Sandia) is a part of the DOS's team implementing the Iraq NDs Program. This report documents Sandia's support of the Iraq NDs Program, which has developed into three principal work streams: (1) training and technical consultation; (2) introducing Iraqis to modern decommissioning and waste management practices; and (3) supporting the IAEA, as they assist the GOI. Examples of each of these work streams include: (1) presentation of a three-day training workshop on 'Practical Concepts for Safe Disposal of Low-Level Radioactive Waste in Arid Settings;' (2) leading GOI representatives on a tour of two operating low level radioactive waste disposal facilities in the U.S.; and (3) supporting the IAEA's Technical Meeting with the GOI from April 21

  1. Horonobe Underground Research Laboratory project investigation program for the 2007 fiscal year (Translated document)

    International Nuclear Information System (INIS)

    Matsui, Hiroya; Nakayama, Masashi; Sanada, Hiroyuki; Yamaguchi, Takehiro

    2008-09-01

    As past of the research and development program on the geological disposal of high-level radioactive waste (HLW), the Horonobe Underground Research Center, a division of the Japan Atomic Energy Agency (JAEA), is implementing the Horonobe Underground Research Laboratory Project (Horonobe URL Project) with the aim at investigating sedimentary rock formations. According to the research plan described in the Midterm Plan of JAEA, geological investigations are to be carried out during the drilling of a shaft down to intermediate depth, while research and development in the areas of engineering technology and safety assessment are to be promoted by collaboration with other research organizations. The results of the R and D activities will be systematized as a 'knowledge base' that supports a wide range of arguments related to the safety of geological disposal. The Horonobe URL Project is planned to extend over a period of 20 years. The investigations will be conducted in three phases, namely 'Phase 1: Surface-based investigations', 'Phase 2: Construction phase' (investigations during construction of the underground facilities) and 'Phase 3: Operation phase' (research in the underground facilities). This report summarizes the investigation program for the 2007 fiscal year (2007/2008), the third year of the Phase 2 investigations. In the 2007 fiscal year, investigations in geoscientific research', including 'development of techniques for investigating the geological environment', 'development of techniques for use in the deep underground environment' and 'studies on the long-term stability of the geological environment', is continuously carried out. Investigations in 'research and development on geological disposal technology', including improving the reliability of disposal technologies' and 'enhancement of safety assessment methodologies' are also continuously carried out. Construction of the underground facilities is ongoing at the Ventilation Shaft and the East Shaft

  2. Simulations of the Response of the Cluster Detector/Scintillator Wall for the 4π facility at SIS/ESR using the GEANT Detector program

    International Nuclear Information System (INIS)

    Herrmann, N.; Maguire, C.F.; Cerruti, C.; Coffin, J.P.; Fintz, P.; Guillaume, G.; Jundt, F.; Rami, F.; Tezkratt, R.; Wagner, P.

    1990-01-01

    The expected response of the cluster detector/scintillator wall of the SIS/ESR 4π facility has been investigated with the use of the GEANT detector program and the FREESCO event generator code. Results are presented and discussed. It is shown in particular that the efficiency of the track reconstruction method should be acceptable

  3. Management of radioactive material safety programs at medical facilities. Final report

    International Nuclear Information System (INIS)

    Camper, L.W.; Schlueter, J.; Woods, S.

    1997-05-01

    A Task Force, comprising eight US Nuclear Regulatory Commission and two Agreement State program staff members, developed the guidance contained in this report. This report describes a systematic approach for effectively managing radiation safety programs at medical facilities. This is accomplished by defining and emphasizing the roles of an institution's executive management, radiation safety committee, and radiation safety officer. Various aspects of program management are discussed and guidance is offered on selecting the radiation safety officer, determining adequate resources for the program, using such contractual services as consultants and service companies, conducting audits, and establishing the roles of authorized users and supervised individuals; NRC's reporting and notification requirements are discussed, and a general description is given of how NRC's licensing, inspection and enforcement programs work

  4. Management of radioactive material safety programs at medical facilities. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Camper, L.W.; Schlueter, J.; Woods, S. [and others

    1997-05-01

    A Task Force, comprising eight US Nuclear Regulatory Commission and two Agreement State program staff members, developed the guidance contained in this report. This report describes a systematic approach for effectively managing radiation safety programs at medical facilities. This is accomplished by defining and emphasizing the roles of an institution`s executive management, radiation safety committee, and radiation safety officer. Various aspects of program management are discussed and guidance is offered on selecting the radiation safety officer, determining adequate resources for the program, using such contractual services as consultants and service companies, conducting audits, and establishing the roles of authorized users and supervised individuals; NRC`s reporting and notification requirements are discussed, and a general description is given of how NRC`s licensing, inspection and enforcement programs work.

  5. BROOKHAVEN NATIONAL LABORATORY INSTRUMENTATION DIVISION, R AND D PROGRAMS, FACILITIES, STAFF

    International Nuclear Information System (INIS)

    INSTRUMENTATION DIVISION STAFF

    1999-01-01

    To develop state-of-the-art instrumentation required for experimental research programs at BNL, and to maintain the expertise and facilities in specialized high technology areas essential for this work. Development of facilities is motivated by present BNL research programs and anticipated future directions of BNL research. The Division's research efforts also have a significant impact on programs throughout the world that rely on state-of-the-art radiation detectors and readout electronics. Our staff scientists are encouraged to: Become involved in challenging problems in collaborations with other scientists; Offer unique expertise in solving problems; and Develop new devices and instruments when not commercially available. Scientists from other BNL Departments are encouraged to bring problems and ideas directly to the Division staff members with the appropriate expertise. Division staff is encouraged to become involved with research problems in other Departments to advance the application of new ideas in instrumentation. The Division Head integrates these efforts when they evolve into larger projects, within available staff and budget resources, and defines the priorities and direction with concurrence of appropriate Laboratory program leaders. The Division Head also ensures that these efforts are accompanied by strict adherence to all ES and H regulatory mandates and policies of the Laboratory. The responsibility for safety and environmental protection is integrated with supervision of particular facilities and conduct of operations

  6. BROOKHAVEN NATIONAL LABORATORY INSTRUMENTATION DIVISION, R AND D PROGRAMS, FACILITIES, STAFF.

    Energy Technology Data Exchange (ETDEWEB)

    INSTRUMENTATION DIVISION STAFF

    1999-06-01

    To develop state-of-the-art instrumentation required for experimental research programs at BNL, and to maintain the expertise and facilities in specialized high technology areas essential for this work. Development of facilities is motivated by present BNL research programs and anticipated future directions of BNL research. The Division's research efforts also have a significant impact on programs throughout the world that rely on state-of-the-art radiation detectors and readout electronics. Our staff scientists are encouraged to: Become involved in challenging problems in collaborations with other scientists; Offer unique expertise in solving problems; and Develop new devices and instruments when not commercially available. Scientists from other BNL Departments are encouraged to bring problems and ideas directly to the Division staff members with the appropriate expertise. Division staff is encouraged to become involved with research problems in other Departments to advance the application of new ideas in instrumentation. The Division Head integrates these efforts when they evolve into larger projects, within available staff and budget resources, and defines the priorities and direction with concurrence of appropriate Laboratory program leaders. The Division Head also ensures that these efforts are accompanied by strict adherence to all ES and H regulatory mandates and policies of the Laboratory. The responsibility for safety and environmental protection is integrated with supervision of particular facilities and conduct of operations.

  7. RCRA facility investigation report for the 200-PO-1 operable unit. Revision 1

    International Nuclear Information System (INIS)

    1997-05-01

    This Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) report is prepared in support of the RFI/corrective measures study process for the 200-PO-1 Groundwater Operable Unit in the 200 East Area of the Hanford Site. This report summarizes existing information on this operable unit presented in the 200 East and PUREX Aggregate Area Management Study Reports, contaminant specific studies, available modeling data, and groundwater monitoring data summary reports. Existing contaminant data are screened against current regulatory limits to determine contaminants of potential concern (COPC). Each identified COPC is evaluated using well-specific and plume trend analyses

  8. Safety analysis report upgrade program at the Plutonium Facility, Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Pan, P.Y.

    1993-01-01

    Plutonium research and development activities have resided at the Los Alamos National Laboratory (LANL) since 1943. The function of the Plutonium Facility (PF-4) has been to perform basic special nuclear materials research and development and to support national defense and energy programs. The original Final Safety Analysis Report (FSAR) for PF-4 was approved by DOE in 1978. This FSAR analyzed design-basis and bounding accidents. In 1986, DOE/AL published DOE/AL Order 5481.1B, ''Safety Analysis and Review System'', as a requirement for preparation and review of safety analyses. To meet the new DOE requirements, the Facilities Management Group of the Nuclear Material Technology Division submitted a draft FSAR to DOE for approval in April 1991. This draft FSAR analyzed the new configurations and used a limited-scope probabilistic risk analysis for accident analysis. During the DOE review of the draft FSAR, DOE Order 5480.23 ''Nuclear Safety Analysis Reports'', was promulgated and was later officially released in April 1992. The new order significantly expands the scope, preparation, and maintenance efforts beyond those required in DOE/AL Order 5481.1B by requiring: description of institutional and human-factor safety programs; clear definitions of all facility-specific safety commitments; more comprehensive and detailed hazard assessment; use of new safety analysis methods; and annual updates of FSARs. This paper describes the safety analysis report (SAR) upgrade program at the Plutonium Facility in LANL. The SAR upgrade program is established to meet the requirements in DOE Order 5480.23. Described in this paper are the SAR background, authorization basis for operations, hazard classification, and technical program elements

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

    International Nuclear Information System (INIS)

    Persiani, P.J.

    1975-02-01

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

  10. Facility accident considerations in the US Department of Energy Waste Management Program

    International Nuclear Information System (INIS)

    Mueller, C.

    1994-01-01

    A principal consideration in developing waste management strategies is the relative importance of Potential radiological and hazardous releases to the environment during postulated facility accidents with respect to protection of human health and the environment. The Office of Environmental Management (EM) within the US Department of Energy (DOE) is currently formulating an integrated national program to manage the treatment, storage, and disposal of existing and future wastes at DOE sites. As part of this process, a Programmatic Environmental impact Statement (PEIS) is being prepared to evaluate different waste management alternatives. This paper reviews analyses that have been Performed to characterize, screen, and develop source terms for accidents that may occur in facilities used to store and treat the waste streams considered in these alternatives. Preliminary results of these analyses are discussed with respect to the comparative potential for significant releases due to accidents affecting various treatment processes and facility configurations. Key assumptions and sensitivities are described

  11. Investigating the effects of counseling programs on runaway youth

    Directory of Open Access Journals (Sweden)

    Mohammad Reza Iravani

    2014-04-01

    Full Text Available This paper presents an empirical investigation to study the effects of counseling programs on reducing the runaway youth in Iran. The study selects a sample of 30 students and divides them into two groups of control and experiment. The first group is kept under eight sessions of social skills training and a questionnaire consists of various questions including confidence items is distributed among both groups after the training ends. The implementation of Kolmogorov-Smirnov has revealed that both pre and post-test data are normally distributed. In addition, the result of ANOVA test has revealed that training program could significantly improve runaway youth’s confidence.

  12. Benefits of a Dedicated Breastfeeding Facility and Support Program for Exclusive Breastfeeding among Workers in Indonesia.

    Science.gov (United States)

    Basrowi, Ray W; Sulistomo, Astrid B; Adi, Nuri Purwito; Vandenplas, Yvan

    2015-06-01

    A mother's working environment is believed to be a major determinant of exclusive breastfeeding (EBF) practice. We aimed to define the influence of a facility dedicated to breastfeeding and a breastfeeding support program at the workplace on breastfeeding practice. A cross-sectional study was performed in five workplaces. The inclusion criteria were female workers whose last child was between 6 and 36 months old. Observational data were obtained and a questionnaire was filled out. The World Health Organization definition for EBF was used. Data from 186 subjects (74 office workers and 112 factory workers) were collected. Just over half (52%) of the mothers were between 20 and 46 years old, 75.3% had graduated from high school and university, 12.9% had more than two children and 36.0% owned a house. The prevalence of EBF during the last 6 months was 32.3%. A proper dedicated breastfeeding facility was available for 21.5% of the mothers, but only 7.5% had been in contact with a breastfeeding support program. The presence of a dedicated breastfeeding facility increased EBF practice almost threefold, by an odds ratio (OR) of 2.74 and a 95% confidence interval (CI) of 1.34-5.64 (pdedicated breastfeeding facility at the workplace as these simple measures significantly increase EBF.

  13. Occupational dose reduction at Department of Energy contractor facilities: Study of ALARA programs

    International Nuclear Information System (INIS)

    Dionne, B.J.; Meinhold, C.B.; Khan, T.A.; Baum, J.W.

    1992-03-01

    This report provides the US Department of Energy (DOE) and its contractors with information that will be useful for reducing occupational radiation doses at DOE's nuclear facilities. In 1989 and 1990, health physicists from the Brookhaven National Laboratory's (BNL) ALARA Center visited twelve DOE contractor facilities with annual collective dose equivalents greater than 100 person-rem (100 person-cSv). The health physicists interviewed radiological safety staff, engineers, and training personnel who were responsible for dose control. The status of ALARA practices at the major contractor facilities was compared with the requirements and recommendation in DOE Order 5480.11 ''Radiation Protection for Occupational Workers'' and PNL-6577 ''Health Physics Manual of Good Practices for Reducing Radiation Exposure to Levels that are as Low as Reasonably Achievable.'' The information and data collected are described and examples of successful practices are presented. The findings on the status of the DOE Contractor ALARA Programs are summarized and evaluated. In addition, the supplement to this report contains examples of good-practice documents associated with implementing the major elements of a formally documented ALARA program for a major DOE contractor facility

  14. Identification of potential recovery facilities for designing a reverse supply chain network using physical programming

    Science.gov (United States)

    Pochampally, Kishore K.; Gupta, Surendra M.; Kamarthi, Sagar V.

    2004-02-01

    Although there are many quantitative models in the literature to design a reverse supply chain, every model assumes that all the recovery facilities that are engaged in the supply chain have enough potential to efficiently re-process the incoming used products. Motivated by the risk of re-processing used products in facilities of insufficient potentiality, this paper proposes a method to identify potential facilities in a set of candidate recovery facilities operating in a region where a reverse supply chain is to be established. In this paper, the problem is solved using a newly developed method called physical programming. The most significant advantage of using physical programming is that it allows a decision maker to express his preferences for values of criteria (for comparing the alternatives), not in the traditional form of weights but in terms of ranges of different degrees of desirability, such as ideal range, desirable range, highly desirable range, undesirable range, and unacceptable range. A numerical example is considered to illustrate the proposed method.

  15. An overview of the PIREX Proton Irradiation facility and its research program

    Energy Technology Data Exchange (ETDEWEB)

    Victoria, M.; Gavillet, D. [Association EURATOM, Villigen (Switzerland)

    1995-10-01

    The main design characteristics of PIREX (Proton Irradiation Experiment) are described. The facility is installed in the 590 MeV proton beam of the PSI accelerator system. Its main task is the irradiation and testing of fusion reactor candidate materials. Protons of this energy produce simultaneously in the target material displacement damage and impurities, amongst them helium. They can therefore simulate possible synergistic effects between helium and damage that would result from irradiations with the fusion neutrons. The research program being developed includes studies on both materials of technological interest, such as martensitic stainless steels and Mo - based alloys and basic radiation damage research on pure metals. The facility is also being used for actinide transmutation studies, in the so called ATHENA experiment. The main directions of the research program are described and examples of present results are given.

  16. Experimental programs and facilities for ASTRID development related to the Severe Accident Issue

    International Nuclear Information System (INIS)

    Journeau, C.; Suteau, C.; Trotignon, L.; Willermoz, G.; Ducros, G.; Courouau, J.L.; Ruggieri, J.M.; Serre, F.

    2013-01-01

    A comprehensive experimental program has been launched in order to gain new data in support of the severe accident studies related to the ASTRID demonstrator. The main new issues with respect to the historic experimental database are mainly related to new design options: heterogeneous core with thick pins; new materials; new severe accident mitigation systems such as - corium discharge channels; - core-catcher with sacrificial materials; - some issues remaining open as Fuel Coolant Interaction. Experiments are needed both in-pile and out of pile: - Depending on the objectives, the out of pile experiments can be conducted - with simulant; - with prototypic corium; - or with irradiated fuel. A new large scale corium facility, FOURNAISE, must be built to fulfill this program. Already, experimental R&D started in existing facilities, such as VITI or CORRONA

  17. LWR fuel rod testing facilities in high flux reactor (HFT) Petten for investigation of power cycling and ramping behaviour

    Energy Technology Data Exchange (ETDEWEB)

    Markgraf, J; Perry, D; Oudaert, J [Commission of the European Communities, Joint Reserach Centre, Petten Establishment, Petten (Netherlands)

    1983-06-01

    LWR fuel rod irradiation experiments are being performed in HFR's Pool Side Facility (PSF) by means of pressurized boiling water capsules (BWFC). For more than 6 years the major application of these devices has been in performing irradiation programs to investigate the power ramp behaviour of PWR and BWR rods which have been pre-irradiated in power reactors. Irradiation devices with various types of monitoring instrumentation are available, e.g. for fuel rod length, fuel stack length, fuel rod internal pressure and fuel rod central temperature measurements. The application scope covers PWR and BWR fuel rods, with burn-up levels up to 45 MWd/kg(U), max. linear heat generation rates up to 700 W/cm and simulation of constant power change rates between 0.05 and 1000 W/cm.min. The paper describes the different designs of LWR fuel rod testing facilities and associated non-destructive testing devices in use at the HFR Petten. It also addresses the new test capabilities that will become available after exchange of the HFR vessel in 1983. Furthermore it shows some typical results. (author)

  18. Technology requirements to be addressed by the NASA Lewis Research Center Cryogenic Fluid Management Facility program

    Science.gov (United States)

    Aydelott, J. C.; Rudland, R. S.

    1985-01-01

    The NASA Lewis Research Center is responsible for the planning and execution of a scientific program which will provide advance in space cryogenic fluid management technology. A number of future space missions were identified that require or could benefit from this technology. These fluid management technology needs were prioritized and a shuttle attached reuseable test bed, the cryogenic fluid management facility (CFMF), is being designed to provide the experimental data necessary for the technology development effort.

  19. Status and update of the National Ignition Facility radiation effects testing program

    International Nuclear Information System (INIS)

    Davis, J F; Serduke, F J; Wuest, C R.

    1998-01-01

    We are progressing in our efforts to make the National Ignition Facility (NIF) available to the nation as a radiation effects simulator to support the Services needs for nuclear hardness and survivability testing and validation. Details of our program were summarized in a paper presented at the 1998 HEART Conference [1]. This paper describes recent activities and updates plans for NIF radiation effects testing. research. Radiation Effects Testing

  20. Nuclear criticality safety assessment of the Consolidated Edison Uranium-Solidification Program Facility

    International Nuclear Information System (INIS)

    Thomas, J.T.

    1984-01-01

    A nuclear criticality assessment of the Consolidated Edison Uranium-Solidification Program facility confirms that all operations involved in the process may be conducted with an acceptable margin of subcriticality. Normal operation presents no concern since subcriticality is maintained by design. Several recommendations are presented to prevent, or mitigate the consequences of, any abnormal events that might occur in the various portions of the process. These measures would also serve to reduce to a minimum the administrative controls required to prevent criticality

  1. Test facility for investigation of heating of 30 GHz accelerating structure imitator for the CLIC project

    International Nuclear Information System (INIS)

    Elzhov, A.V.; Ginzburg, N.S.; Kaminsky, A.K.; Kuzikov, S.V.; Perelstein, E.A.; Peskov, N.Yu.; Petelin, M.I.; Sedykh, S.N.; Sergeev, A.P.; Sergeev, A.S.; Syratchev, I.; Zaitsev, N.I.

    2004-01-01

    Since 2001 an experimental test facility for investigation of lifetime of a copper material, with respect to multiple RF pulse actions, was set up on the basis of the JINR (Dubna) FEM oscillator, in collaboration with IAP RAS (Nizhny Novgorod). A high-Q copper cavity, which simulates the parameters of the accelerating structure of the collider CLIC at an operating frequency of 30 GHz, is used in the investigation. The experimental setup consists of a wavebeam injector--FEM oscillator (power of ∼25 MW, pulse duration up to 200 ns, spectral bandwidth not higher than 0.1%), a quasi-optic two-mirror transmission line, a wave-type converter, and a testing cavity. The frequency and transmission features of the components of the quasi-optic line were analyzed

  2. Test facility for investigation of heating of 30 GHz accelerating structure imitator for the CLIC project

    CERN Document Server

    Elzhov, A V; Kaminsky, A K; Kuzikov, S V; Perelshtejn, E A; Peskov, N Yu; Petelin, M I; Sedykh, S N; Sergeev, A P; Sergeev, A S; Syratchev, I V; Zaitsev, N I

    2004-01-01

    Since 2001 an experimental test facility for investigation of lifetime of a copper material, with respect to multiple RF pulse actions, was set up on the basis of the JINR (Dubna) FEM oscillator, in collaboration with IAP RAS (Nizhny Novgorod). A high-Q copper cavity, which simulates the parameters of the accelerating structure of the collider CLIC at an operating frequency of 30GHz, is used in the investigation. The experimental setup consists of a wavebeam injector - FEM oscillator (power of similar to 25MW, pulse duration up to 200ns, spectral bandwidth not higher than 0.1%), a quasi-optic two-mirror transmission line, a wave-type converter, and a testing cavity. The frequency and transmission features of the components of the quasi-optic line were analyzed.

  3. A program for dynamic noise investigations of reactor systems

    International Nuclear Information System (INIS)

    Antonov, N.A.; Yaneva, N.B.

    1980-01-01

    A stochastic process analysis in nuclear reactors is used for the state diagnosis and dynamic characteristic investigation of the reactor system. A program DENSITY adapted and tested on an IBM 360 ES type computer is developed. The program is adjusted for fast processing of long series exploiting a relatively small memory. The testing procedure is discussed and the method of the periodic sequences corresponding to characteristic reactivity perturbations of the reactor systems is considered. The program is written for calculating the auto-power spectral density and the cross-power spectral density, as well as the coherence function of stationary statistical time series using the advantages of the fast Fourier transformation. In particular, it is shown that the multi-frequency binary sequences are very useful with respect to the signal-to-noise ratio and the frequency distribution in view of the frequency reactor test

  4. Results of the groundwater quality assessment program at the 216-A-29 ditch RCRA facility

    International Nuclear Information System (INIS)

    Votava, J.M.

    1995-01-01

    This report presents the findings of the groundwater quality assessment program for the 216-A-29 Ditch. The information presented in this report Ditch have affected the quality of the groundwater in the unconfined aquifer beneath the facility. The results indicate that the 216-A-29 Ditch is the source of elevated specific conductance in well 299-E25-35 and that the source is nonhazardous. This report describes the current monitoring status of the 216-A-29 Ditch, groundwater chemical data interpretation, and recommends the reinstatement of an indicator-evaluation monitoring program in accordance with 40 CFR 265.93(d)(6)

  5. Reliability and safety program plan outline for the operational phase of a waste isolation facility

    International Nuclear Information System (INIS)

    Ammer, H.G.; Wood, D.E.

    1977-01-01

    A Reliability and Safety Program plan outline has been prepared for the operational phase of a Waste Isolation Facility. The program includes major functions of risk assessment, technical support activities, quality assurance, operational safety, configuration monitoring, reliability analysis and support and coordination meetings. Detailed activity or task descriptions are included for each function. Activities are time-phased and presented in the PERT format for scheduling and interactions. Task descriptions include manloading, travel, and computer time estimates to provide data for future costing. The program outlined here will be used to provide guidance from a reliability and safety standpoint to design, procurement, construction, and operation of repositories for nuclear waste. These repositories are to be constructed under the National Waste Terminal Storage program under the direction of the Office of Waste Isolation, Union Carbide Corp. Nuclear Division

  6. Engineering program in order to increase the irradiated fuel storage capacity in pool facilities of Juragua

    International Nuclear Information System (INIS)

    Rodriguez R, J.

    1996-01-01

    In 1993, a technical program in the spent fuel storage area of Nuclear Plant Juragua was launched. Such a program tries to carry out an engineering assessment of the possibility of increasing the spent fuel storage capacity in pool storage facilities by using high density racks (re-racking) instead of the original (non-compact) ones. The purpose of the above-mentioned program is to evaluate possible solutions that can be applied to the construction works prior to plant operation. The first stage of the program for the 1994-95 period is an ongoing Engineering-Economic Feasibility Study (EEFS), which endeavors to examine the capabilities of the reloading pool in Unit-1 Reactor building and long-term storage pool in auxiliary building in high density storage conditions. Technical details of the EEFS and reached results and difficulties are described. (author). 5 refs., 2 figs

  7. The Idaho Power Burst Facility/Boron Neutron Capture Therapy (PBF/BNCT) Program overview

    International Nuclear Information System (INIS)

    Dorn, R.V. III; Griebenow, M.L.; Ackermann, A.L.; Miller, L.G.; Miller, D.L.; Wheeler, F.J.; Bradshaw, K.M.; Wessol, D.E.; Harker, Y.D.; Nigg, D.W.; Randolph, P.D.; Bauer, W.F.; Gavin, P.R.; Richards, T.L.

    1992-01-01

    The Power Burst Facility/Boron Neutron Capture Therapy (PBF/BNCT) Program has been funded since 1988 to evaluate brain tumor treatment using Na 2 B 12 H 11 SH (borocaptate sodium or BSH) and epithermal neutrons. The PBF/BNCT Program pursues this goal as a comprehensive, multidisciplinary, multiorganizational endeavor applying modern program management techniques. The initial focus was to: (1) establish a representative large animal model and (2) develop the generic analytical and measurement capabilities require to control treatment repeatability and determine critical treatment parameters independent of tumor type and body location. This paper will identify the PBF/BNCT Program elements and summarize the status of some of the developed capabilities

  8. Aquatic Species Program review: proceedings of principal investigators meeting

    Energy Technology Data Exchange (ETDEWEB)

    1985-06-01

    The purpose of the Aquatic Species Program is to improve the productivity, conversion to fuels, and cost efficiency of aquatic plant culture technologies. The emphasis of the program is on developing a mass culture technology for cultivating oil-yielding microalgae in the American southwest. A technical and economic analysis indicated that such a concept would be feasible if (1) lipid yields from microalgae are improved, (2) there is sufficient saline water for large-scale development, and (3) microalgal lipids can be economically converted to conventional fuels. It was determined that fuels from microalgal lipids presented better options than converting the microalgal biomass to either alcohols or methane. All lipids can potentially be catalytically converted to gasoline, or the fatty acids can be converted to substitute diesel fuels. The Southwest has the necessary low, flat, underutilized lands, and carbon dioxide is available from either natural deposits or flue gas from industrial plants. The amount of saline water available will probably determine how much fuel can be produced from aquatic species, and this question should be answered during 1985. The largest constraint of this technology is the economical production of an oil-rich microalgal feedstock. The agenda for the review was divided into four sections: species selection and characterization, applied physiological studies, outdoor mass cultivation, and systems design and analysis. Papers from these presentations are included in these proceedings. Program advances were reported in the areas of species collection and selection, modulated light physiology, mass culture yields, harvesting of microalgae, mass culture facility design and analysis, and assessments on fuel options from microalgae. Separate abstracts have been prepared for each paper for inclusion in the Energy Data Base.

  9. Investigation on integrity of JMTR concrete structures, cooling system and utility facilities

    International Nuclear Information System (INIS)

    Ebisawa, Hiroyuki; Tobita, Kenji; Fukasaku, Akitomi; Kaminaga, Masanori

    2010-02-01

    The condition of facilities and components to be used for re-operation of the Japan Materials Testing Reactor (JMTR) from FY2011, was investigated before the refurbishment work. An investigation of aged components (aged-investigation) was carried out for concrete structures of the JMTR reactor building, exhaust stack, trench, canal, filter banks and for aged components of tanks in the primary cooling system, heat exchangers, pipes in the secondary cooling system, cooling tower, emergency generators and so on, in order to identify their integrity. The aged-investigation was carried out from the beginning of FY2007. As a result, cracks of concrete structures such as the exhaust stack, a foundation of the UCL (Utility Cooling Line) elevated water tank were repaired and pipe linings of secondary cooling system were replaced. Motors of primary cooling pumps, pumps in the secondary cooling system and in other systems were decided to replace from viewpoints of future maintenance and improvement of reliability. Other components and the reactor building were decided to use continuously for a long-term by appropriate maintenance activities based on the long-term maintenance plan. In this paper, the aged-investigation for the JMTR reactor building, heat exchangers and emergency generators is presented. (author)

  10. PWR Blowdown Heat Transfer Separate-Effects Program. Thermal-Hydraulic Test Facility experimental data report for test 166S

    International Nuclear Information System (INIS)

    Clemons, V.D.; White, M.D.; Hedrick, R.A.

    1978-01-01

    Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 166S, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in a PWR system. Test 166S was conducted to obtain thermal-hydraulic and CHF information in THTF bundle 1 with an intact hot leg. The primary purpose of this report is to make the reduced instrument responses during tests 166S available. These are presented in graphical form in engineering units and have been analyzed only to the extent necessary to ensure reasonableness and consistency

  11. Air quality investigations of the Sandia National Laboratories Sol se Mete Aerial Cable Facility

    International Nuclear Information System (INIS)

    Gutman, W.M.; Silver, R.J.

    1994-12-01

    The air quality implications of the test and evaluation activities at the Sandia National Laboratories Sol se Mete Aerial Cable Facility are examined. All facets of the activity that affect air quality are considered. Air contaminants produced directly include exhaust products of rocket motors used to accelerate test articles, dust and gas from chemical explosives, and exhaust gases from electricity generators in the test arenas. Air contaminants produced indirectly include fugitive dust and exhaust contaminants from vehicles used to transport personnel and material to the test area, and effluents produced by equipment used to heat the project buildings. Both the ongoing program and the proposed changes in the program are considered. Using a reliable estimate of th maximum annual testing level, the quantities of contaminants released by project activities ar computed either from known characteristics of test items or from EPA-approved emission factors Atmospheric concentrations of air contaminants are predicted using EPA dispersion models. The predicted quantities and concentrations are evaluated in relation to Federal, New Mexico, an Bernalillo County air quality regulations and the human health and safety standards of the American Conference of Governmental Industrial Hygienists

  12. The RIB facility EXOTIC and its experimental program at INFN-LNL

    Science.gov (United States)

    Parascandolo, Concetta

    2018-05-01

    In this contribution, I will present a review about the EXOTIC facility and the research field accessible by using its Radioactive Ion Beams. The EXOTIC facility, installed at the INFN-Laboratori Nazionali di Legnaro, is devoted to the in-flight production of light Radioactive Ion Beams in the energy range between 3-5 MeV/nucleon. The scientific activity performed at EXOTIC concerns different aspects of nuclear physics and nuclear astrophysics, such as, the investigation of reaction mechanisms and nuclear structure, resonant scattering experiments and measurements of nuclear reaction cross sections of astrophysical interest.

  13. Investigation of flashing-induced instabilities at Circus test facility with the code ATHLET

    Energy Technology Data Exchange (ETDEWEB)

    Schafer, F.; Manera, A. [Forschungzentrum Rossendorf e.V., Institute of Safety Research, P.O. Box 510119, D-01314 Dresden (Germany)]. E-mail: F.Schaefer@fz-rossendorf.de; A.Manera@fz-rossendorf.de

    2006-07-01

    The test facility CIRCUS (CIRculation Under Start-up) was built to study the start-up phase of a natural-circulation BWR. During the start-up,so-called flashing-induced instabilities can arise. These instabilities are induced by flashing (i.e., steam production in adiabatic conditions) of the coolant in the long riser section, which is placed above the core to enhance the flow rate. The flashing that occurs in the riser causes an imbalance between driving force and pressure losses in the natural-circulation loop, giving rise to flow oscillations. Within the European-Union 5th Framework Programme, a project, NACUSP (Natural circulation and stability performance of BWRs), has been started in December 2000, having as one of its main aims the understanding of the physics of the phenomena involved during the start-up phase of natural-circulation-cooled BWRs, providing a large experimental database and validating state-of-the-art thermo-hydraulic codes in the low-pressure, low-power operational region of these reactors. One part of this project deals with the modelling of selected CIRCUS tests using the thermo-hydraulic code ATHLET (Analysis of THermal-hydraulics of LEaks and Transients). This paper gives an overview about experiments and simulations. The code ATHLET is used to investigate the dynamic behaviour of the CIRCUS test facility and the results of the calculations are compared with the experimental data. (author)

  14. Tetraphenylpyrimidine-Based AIEgens: Facile Preparation, Theoretical Investigation and Practical Application

    Directory of Open Access Journals (Sweden)

    Junkai Liu

    2017-10-01

    Full Text Available Aggregation-induced emission (AIE has become a hot research area and tremendous amounts of AIE-active luminogens (AIEgens have been generated. To further promote the development of AIE, new AIEgens are highly desirable. Herein, new AIEgens based on tetraphenylpyrimidine (TPPM are rationally designed according to the AIE mechanism of restriction of intramolecular motion, and facilely prepared under mild reaction conditions. The photophysical property of the generated TPPM, TPPM-4M and TPPM-4P are systematically investigated and the results show that they feature the aggregation-enhanced emission (AEE characteristics. Theoretical study shows the high-frequency bending vibrations in the central pyrimidine ring of TPPM derivatives dominate the nonradiative decay channels. Thanks to the AEE feature, their aggregates can be used to detect explosives with super-amplification quenching effects, and the sensing ability is higher than typical AIE-active tetraphenylethene. It is anticipated that TPPM derivatives could serve as a new type of widely used AIEgen based on their facile preparation and good thermo-, photo- and chemostabilities.

  15. 78 FR 79253 - CCC Export Credit Guarantee (GSM-102) Program and Facility Guarantee Program (FGP)

    Science.gov (United States)

    2013-12-27

    ... been worked out in advance of the exporter's application for the payment guarantee. Foreign Financial... country of domicile must provide financial statements in accordance with prevailing accounting standards... smaller U.S. exporters. Changes are also intended to improve CCC's financial management of the program...

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

    Energy Technology Data Exchange (ETDEWEB)

    Bissani, M; O' Kelly, D S

    2006-05-08

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

  17. TMI-2 Vessel Investigation Project (VIP) Metallurgical Program

    International Nuclear Information System (INIS)

    Diercks, D.R.; Neimark, L.A.

    1990-06-01

    The TMI-2 Vessel Investigation Project (VIP) Metallurgical Program is a part of the international TMI-2 Vessel Investigation Project being conducting jointly by the US Nuclear Regulatory Commission and the Organization for Economic Co-operation and Development (OECD). The overall project consists of three phases, namely (1) recovery of material samples from the lower head of the TMI-2 reactor, (2) examination and analysis of the lower head samples and the preparation and testing of archive material subjected to a similar thermal history, and (3) procurement, examination, and analysis of companion core material located adjacent to or near the lower head material. The specific objectives of the ANL Metallurgical Program, which comprises a major portion of Phase 2, are to prepare metallographic and mechanical test specimen blanks from the TMI-2 lower head material, prepare similar test specimen blanks from suitable archive material subjected to the appropriate thermal processing, determine the mechanical properties of the lower vessel head and archive materials under the conditions of the core-melt accident, and assess the lower head integrity and margin-to-failure during the accident. The ANL work consists of three tasks: (1) archive materials program, (2) fabrication of metallurgical and mechanical test specimens from the TMI-2 pressure vessel samples, and (3) mechanical property characterization of TMI-2 lower pressure vessel head and archive material

  18. Water quality facility investigation report : final summary of project and evaluation of monitoring plan implementation.

    Science.gov (United States)

    2005-07-05

    The Oregon Department of Transportation (ODOT) has installed several stormwater : treatment facilities throughout the State to improve the quality of runoff discharged from : highways. These facilities include a variety of both above ground and below...

  19. Experimental investigations of the accelerator-driven transmutation technologies at the subcritical facility ''Yalina''

    International Nuclear Information System (INIS)

    Chigrinov, S.E.; Kiyavitskaya, H.I.; Serafimovich, I.G.; Rakhno, I.L.; Rutkovskaia, Ch.K.; Fokov, Y.; Khilmanovich, A.M.; Marstinkevich, B.A.; Bournos, V.V.; Korneev, S.V.; Mazanik, S.E.; Kulikovskaya, A.V.; Korbut, T.P.; Voropaj, N.K.; Zhouk, I.V.; Kievec, M.K.

    2002-01-01

    The investigations on accelerator-driven transmutation technologies (ADTT) focus on the reduction of the amount of long-lived wastes and the physics of a subcritical system driven with an external neutron source. This paper presents the experimental facility 'Yalina' which was designed and created at the Radiation Physics and Chemistry Problems Institute of the National Academy of Sciences of Belarus in the framework of the ISTC project no. B-070 to study the peculiarities of ADTT in thermal spectrum. A detailed description of the assembly, neutron generator and a preliminary analysis of some calculated and experimental data (multiplication factor, neutron flux density distribution in the assembly, transmutation rates of some long-lived fission products and minor actinides) are presented. (authors)

  20. Investigation of the possibility of using hydrogranulation in reprocessing radioactive wastes of radiochemical production facilities

    Energy Technology Data Exchange (ETDEWEB)

    Revyakin, V.; Borisov, L.M. [All Russian Scientific and Research Institute of Non-Organic Materials, Moscow (Russian Federation)

    1996-05-01

    Radio-chemical production facilities are constantly accumulating liquid radioactive wastes (still residues as the result of evaporation of extraction and adsorption solutions etc.) which are a complex multicomponent mixtures. The wastes are frequently stored for extended periods of time while awaiting disposition and in some cases, and this is much worse, they are released into the environment. In this report, I would like to draw your attention to some results we have obtained from investigations aimed at simplifying handing of such wastes by the precipitation of hard to dissolve metal hydroxides, the flocculation of the above into granules with the help of surface-active agents (in this case a polyacrylamide - PAA), quickly precipitated and easily filtered. The precipitate may be quickly dried and calcinated, if necessary, and transformed into a dense oxide sinter. In other words it may be transformed into a material convenient for storage or burial.

  1. Savannah River Site RCRA Facility Investigation plan: Road A Chemical Basin

    International Nuclear Information System (INIS)

    1989-06-01

    The nature of wastes disposed of at the Road A Chemical Basin (RACB) is such that some degree of soil contamination is probable. Lead has also been detected in site monitoring wells at concentrations above SRS background levels. A RCRA Facility Investigation (RFI) is proposed for the RACB and will include a ground penetrating radar (GPR) survey, collection and chemical and radiological analyses of soil cores, installation of groundwater monitoring wells, collection and chemical and radiological analyses of groundwater samples, and collection of chemical and radiological analyses of surface water and sediment samples. Upon completion of the proposed RFI field work and chemical and radiological analyses, and RFI report should be prepared to present conclusions on the nature and extent of contamination at the site, and to make recommendations for site remediation. If contamination is detected at concentrations above SRS background levels, a receptor analysis should be done to evaluate potential impacts of site contamination on nearby populations

  2. Need of geotechnical investigations for civil design of Nuclear Fuel Cycle Facilities

    International Nuclear Information System (INIS)

    Sharma, Sudin; Bhalerao, Sandip; Subramanyam, P.; Bhargava, Kapilesh; Agarwal, Kailash; Rao, D.A.S.; Roy, Amitava; Basu, S.

    2015-01-01

    An adequate assessment of the site geologic and geotechnical conditions is one of the most important aspects in safety evaluation of a Nuclear Fuel Cycle Facility (NFCF). Evaluation of safety of either a new or an existing NFCF requires, among other things, that its founding strata has been adequately examined, explored, and investigated so that it is as fully understood as possible. Foundation explorations should be directed towards obtaining only such information as may be important to an evaluation of Safety of the NFCF Civil structures of NFCF generally impose heavy loads on the foundation systems. Safe design of foundation aims at providing sound foundation systems for the structures so that they can fulfil their functional requirements towards the objective of nuclear safety. This paper aims at discussing various geotechnical tests and there importance in the safe evaluation and design of civil structures of NFCF in India. (author)

  3. CHANDA and ERINDA: Joint European programs for research on safety of nuclear facilities and waste reduction

    Energy Technology Data Exchange (ETDEWEB)

    Beyer, Roland; Hannaske, Roland; Koegler, Toni [Institut fuer Strahlenphysik, Helmholtz Zentrum DD-Rossendorf, 01328 Dresden (Germany); Institut fuer Kern- und Teilchenphysik, TU Dresden, 01069 Dresden (Germany); Grosse, Eckart [Institut fuer Kern- und Teilchenphysik, TU Dresden, 01069 Dresden (Germany); Junghans, Arnd R. [Institut fuer Strahlenphysik, Helmholtz Zentrum DD-Rossendorf, 01328 Dresden (Germany)

    2014-07-01

    In spite of the planned termination of the German nuclear power program neutron beam facilities in Germany can contribute considerably to research studies on the reduction of hazards due to nuclear waste. Transnational research programs support EU groups who want to carry out projects at the new tof set-up nELBE at HZDR, the calibrated n-flux at PTB and the FRANZ accelerator under construction at Frankfurt. Vice versa various facilities in the EU offer beams for transmutation and safety related studies with neutrons to German scientists under support by ERINDA (2011-2013) and CHANDA (2014-2017; solving challenges in nuclear data for the safety of European nuclear facilities). For work in that field scientific visits are also fostered to improve the exchange of experience between the partners (13 and in future about 35 from 18 countries). Plans for new projects as well as results obtained so far are discussed, and special emphasis is given to the present research performed at nELBE on neutron scattering and absorption.

  4. Canadian development program for off-gas management in nuclear facilities

    International Nuclear Information System (INIS)

    Sridhar, T.S.

    1983-01-01

    The Canadian program for the development and evaluation of processes and technology for the separation and containment of radioactive species in off-gases is directed towards the following specific aspects: 1) assessment of available treatment technology and evaluation of future clean-up requirements; 2) development and engineering evaluation, under realistic conditions, of promising new processes that would be inherently simpler and safer; and 3) specification of off-gas emission control systems for future nuclear facilities based on the most favourable technology. The program is being carried out by Atomic Energy of Canada Limited in collaboration with the electrical utility, Ontario Hydro, and selected Canadian universities. A brief description is presented of methods for removing tritium and carbon-14 from the moderator systems of CANDU power reactors, methods for removing iodine from the off-gases of a molybdenum-99 production facility at the Chalk River Nuclear Laboratories, and procedures for monitoring the off-gas effluent composition in the Thorium Fuel Reprocessing Experiment (TFRE) facility at the Whiteshell Nuclear Research Establishment

  5. 25 CFR 170.808 - Can BIA Road Maintenance Program funds be used to improve IRR transportation facilities?

    Science.gov (United States)

    2010-04-01

    ... 25 Indians 1 2010-04-01 2010-04-01 false Can BIA Road Maintenance Program funds be used to improve... THE INTERIOR LAND AND WATER INDIAN RESERVATION ROADS PROGRAM BIA Road Maintenance § 170.808 Can BIA Road Maintenance Program funds be used to improve IRR transportation facilities? No. BIA Road...

  6. Standard guide for establishing a quality assurance program for uranium conversion facilities

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2004-01-01

    1.1 This guide provides guidance and recommended practices for establishing a comprehensive quality assurance program for uranium conversion facilities. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate health and safety practices and determine the applicability of regulatory limitations prior to use. 1.3 The basic elements of a quality assurance program appear in the following order: FUNCTION SECTION Organization 5 Quality Assurance Program 6 Design Control 7 Instructions, Procedures & Drawings 8 Document Control 9 Procurement 10 Identification and Traceability 11 Processes 12 Inspection 13 Control of Measuring and Test Equipment 14 Handling, Storage and Shipping 15 Inspection, Test and Operating Status 16 Control of Nonconforming Items 17 Corrective Actions 18 Quality Assurance Records 19 Audits 20 TABLE 1 NQA-1 Basic Requirements Relat...

  7. Summary of multi-core hardware and programming model investigations

    Energy Technology Data Exchange (ETDEWEB)

    Kelly, Suzanne Marie; Pedretti, Kevin Thomas Tauke; Levenhagen, Michael J.

    2008-05-01

    This report summarizes our investigations into multi-core processors and programming models for parallel scientific applications. The motivation for this study was to better understand the landscape of multi-core hardware, future trends, and the implications on system software for capability supercomputers. The results of this study are being used as input into the design of a new open-source light-weight kernel operating system being targeted at future capability supercomputers made up of multi-core processors. A goal of this effort is to create an agile system that is able to adapt to and efficiently support whatever multi-core hardware and programming models gain acceptance by the community.

  8. A new test facility for the E-ELT infrared detector program

    Science.gov (United States)

    Lizon, Jean Louis; Amico, Paola; Brinkmann, Martin; Delabre, Bernard; Finger, Gert; Guidolin, Ivan Maria; Guzman, Ronald; Hinterschuster, Renate; Ives, Derek; Klein, Barbara; Quattri, Marco

    2016-08-01

    During the development of the VLT instrumentation program, ESO acquired considerable expertise in the area of infrared detectors, their testing and optimizing their performance. This can mainly be attributed to a very competent team and most importantly to the availability of a very well suited test facility, namely, IRATEC. This test facility was designed more than 15 years ago, specifically for 1K × 1K detectors such as the Aladdin device, with a maximum field of only 30 mm square. Unfortunately, this facility is no longer suited for the testing of the new larger format detectors that are going to be used to equip the future E-ELT instruments. It is projected that over the next 20 years, there will be of the order of 50-100 very large format detectors to be procured and tested for use with E-ELT first and second generation instruments and VLT third generation instruments. For this reason ESO has initiated the in-house design and construction of a dedicated new IR detector arrays test facility: the Facility for Infrared Array Testing (FIAT). It will be possible to mount up to four 60 mm square detectors in the facility, as well as mosaics of smaller detectors. It is being designed to have a very low thermal background such that detectors with 5.3 μm cut-off material can routinely be tested. The paper introduces the most important use cases for which FIAT is designed: they range from performing routine performance measurements on acquired devices, optimization setups for custom applications (like spot scan intra-pixel response, persistence and surface reflectivity measurements), test of new complex operation modes (e.g. high speed subwindowing mode for low order sensing, flexure control, etc.) and the development of new tests and calibration procedures to support the scientific requirements of the E-ELT and to allow troubleshooting the unexpected challenges that arise when a new detector system is brought online. The facility is also being designed to minimize

  9. Investigating an Intervention Program Linking Writing and Vocabulary Development for Homeless Children

    Directory of Open Access Journals (Sweden)

    Richard Sinatra

    2010-03-01

    Full Text Available The presented study investigated the effects of a four-week academic and activity – enriched summer program on vocabulary development and writing achievement of homeless children residing in traditional shelter facilities. When compared to controls the experimental students did not reveal gains in vocabulary and spelling as measured by two norm referenced tests. They did however demonstrate highly significant gains in writing ability based on the New York State standards criteria, reflecting five qualities of writing. On two project-developed instruments designed to measure improvement in book vocabulary and tennis skills, they showed significant increases based on analyses of their pre- and posttest scores. The program closed achievement gaps, fulfilled standards criteria, and may be the first of its kind in the homeless literature whereby students’ writing development was compared to matched controls as vocabulary development occurred based on literary readings.

  10. Analysis of operational records in the bituminization demonstration facility. Investigation of the cause of fire

    International Nuclear Information System (INIS)

    Shibata, A.; Sano, Y.; Yoneya, M.; Koyama, T.

    1997-12-01

    Operational records in the bituminization demonstration facility in 97-M46-1 campaign were analyzed in order to investigate the cause of fire. Operational records which are different from ordinary level in this campaign are drum weight, temperature at 7th zone and extruder torque. So we investigated past campaign data about these records. The results are as follows. 1) In some campaigns, drum weight was lighter, temperature at 7th zone higher, and torque higher. 2) When drum weight is lighter, temperature at 7th zone becomes relatively higher. 3) In the case that higher temperature was measured at 7th zone, drum weight was sometimes less than the past average. 4) When the extruder's torque increases, it sometimes influences drum weight and temperature at 7th zone. The maximum of salt and bitumen became hotter from 28B. As the heat source, both frictional resistance and exothermic chemical reaction can be considered. Frictional resistance came out with increase of the torque. So we checked some operational parameters to investigate what increases the torque. Feed rate of waste solution is related with the torque increase. The other parameters are not related with it. Now we can not specify any causes of the torque increase from 27B, the feed rate of waste solution is however possible to be one of the causes. (author)

  11. Report of investigation regarding accident in Tomsk reprocessing facilities in Russia

    International Nuclear Information System (INIS)

    1994-01-01

    At 1258 on April 6, 1993, the explosion accident of a welded tank occurred in the military reprocessing facilities in Tomsk, Siberia District, Russia. Japan carried out the investigation of the effect on the environmental radiation in Japan, dispatched the investigation mission to Russia, and explained the way of thinking on securing the safety of Japanese reprocessing plants to local communities. Science and Technology Agency organized the working group for investigating the accident, which exerted efforts to collect the information, analyze and examine it. This report is the summary of its results. The explosion occurred in the tank for adjusting the acid concentration of the solution to be supplied to the solvent extraction shop, and the building was destructed. No one died or was injured. The results of the radioactivity examination are reported. The process of the accident was inferred, and described. The factors that caused the accident were the mixing of organic impurities the use of the diluting liquid containing aromatic hydrocarbon, the contact of nitric acid with organic substances at high temperature, in sufficient agitation at the time of pouring nitric acid and so on. The safety countermeasures in Japanese reprocessing plants and the response by Japan based on the accident are described. (K.I.)

  12. Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center

    International Nuclear Information System (INIS)

    Bryant, J.W.; Nenni, J.A.

    2003-01-01

    This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, ''Radioactive Waste Management Manual.'' Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities

  13. Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center

    International Nuclear Information System (INIS)

    Jeffrey Bryant

    2008-01-01

    This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, 'Radioactive Waste Management Manual'. Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities

  14. Performance Assessment Program for the Savannah River Site Liquid Waste Facilities - 13610

    International Nuclear Information System (INIS)

    Rosenberger, Kent H.

    2013-01-01

    The Liquid Waste facilities at the U.S. Department of Energy's (DOE) Savannah River Site (SRS) are operated by Liquid Waste Operations contractor Savannah River Remediation LLC (SRR). A separate Performance Assessment (PA) is prepared to support disposal operations at the Saltstone Disposal Facility and closure evaluations for the two liquid waste tank farm facilities at SRS, F-Tank Farm and H-Tank Farm. A PA provides the technical basis and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements identified in operations and closure regulatory guidance. The Saltstone Disposal Facility is subject to a State of South Carolina industrial solid waste landfill permit and the tank farms are subject to a state industrial waste water permit. The three Liquid Waste facilities are also subject to a Federal Facility Agreement approved by the State, DOE and the Environmental Protection Agency (EPA). Due to the regulatory structure, a PA is a key technical document reviewed by the DOE, the State of South Carolina and the EPA. As the waste material disposed of in the Saltstone Disposal Facility and the residual material in the closed tank farms is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005, the U.S. Nuclear Regulatory Commission (NRC) is also a reviewing agency for the PAs. Pursuant to the Act, the NRC also has a continuing role to monitor disposal actions to assess compliance with stated performance objectives. The Liquid Waste PA program at SRS represents a continual process over the life of the disposal and closure operations. When the need for a PA or PA revision is identified, the first step is to develop a conceptual model to best represent the facility conditions. The conceptual model will include physical dimensions of the closed system, both the engineered and natural system, and modeling

  15. Performance Assessment Program for the Savannah River Site Liquid Waste Facilities - 13610

    Energy Technology Data Exchange (ETDEWEB)

    Rosenberger, Kent H. [Savannah River Remediation LLC, Building 705-1C, Aiken, SC 29808 (United States)

    2013-07-01

    The Liquid Waste facilities at the U.S. Department of Energy's (DOE) Savannah River Site (SRS) are operated by Liquid Waste Operations contractor Savannah River Remediation LLC (SRR). A separate Performance Assessment (PA) is prepared to support disposal operations at the Saltstone Disposal Facility and closure evaluations for the two liquid waste tank farm facilities at SRS, F-Tank Farm and H-Tank Farm. A PA provides the technical basis and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements identified in operations and closure regulatory guidance. The Saltstone Disposal Facility is subject to a State of South Carolina industrial solid waste landfill permit and the tank farms are subject to a state industrial waste water permit. The three Liquid Waste facilities are also subject to a Federal Facility Agreement approved by the State, DOE and the Environmental Protection Agency (EPA). Due to the regulatory structure, a PA is a key technical document reviewed by the DOE, the State of South Carolina and the EPA. As the waste material disposed of in the Saltstone Disposal Facility and the residual material in the closed tank farms is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005, the U.S. Nuclear Regulatory Commission (NRC) is also a reviewing agency for the PAs. Pursuant to the Act, the NRC also has a continuing role to monitor disposal actions to assess compliance with stated performance objectives. The Liquid Waste PA program at SRS represents a continual process over the life of the disposal and closure operations. When the need for a PA or PA revision is identified, the first step is to develop a conceptual model to best represent the facility conditions. The conceptual model will include physical dimensions of the closed system, both the engineered and natural system, and

  16. Computer program for storage of historical and routine safety data related to radiologically controlled facilities

    International Nuclear Information System (INIS)

    Marsh, D.A.; Hall, C.J.

    1984-01-01

    A method for tracking and quick retrieval of radiological status of radiation and industrial safety systems in an active or inactive facility has been developed. The system uses a mini computer, a graphics plotter, and mass storage devices. Software has been developed which allows input and storage of architectural details, radiological conditions such as exposure rates, current location of safety systems, and routine and historical information on exposure and contamination levels. A blue print size digitizer is used for input. The computer program retains facility floor plans in three dimensional arrays. The software accesses an eight pen color plotter for output. The plotter generates color plots of the floor plans and safety systems on 8 1/2 x 11 or 20 x 30 paper or on overhead transparencies for reports and presentations

  17. The influences of Taiwan's National Health Insurance on women's choice of prenatal care facility: Investigation of differences between rural and non-rural areas

    Directory of Open Access Journals (Sweden)

    Chen Chi-Liang

    2008-03-01

    Full Text Available Abstract Background Taiwan's National Health Insurance (NHI, implemented in 1995, substantially increased the number of health care facilities that can deliver free prenatal care. Because of the increase in such facilities, it is usually assumed that women would have more choices regarding prenatal care facilities and thus experience reduction in travel cost. Nevertheless, there has been no research exploring these issues in the literature. This study compares how Taiwan's NHI program may have influenced choice of prenatal care facility and perception regarding convenience in transportation for obtaining such care for women in rural and non-rural areas in Taiwan. Methods Based on data collected by a national survey conducted by Taiwan's National Health Research Institutes (NHRI in 2000, we tried to compare how women chose prenatal care facility before and after Taiwan's National Health Insurance program was implemented. Basing our analysis on how women answered questionnaire items regarding "the type of major health care facility used and convenience of transportation to and from prenatal care facility," we investigated whether there were disparities in how women in rural and non-rural areas chose prenatal care facilities and felt about the transportation, and whether the NHI had different influences for the two groups of women. Results After NHI, women in rural areas were more likely than before to choose large hospitals for prenatal care services. For women in rural areas, the relative probability of choosing large hospitals to choosing non-hospital settings in 1998–1999 was about 6.54 times of that in 1990–1992. In contrast, no such change was found in women in non-rural areas. For a woman in a non-rural area, she was significantly more likely to perceive the transportation to and from prenatal care facilities to be very convenient between 1998 and 1999 than in the period between 1990 and 1992. No such improvement was found for women in

  18. Safe shutdown of Defense Program facilities at the Mound Plant, Miamisburg, Ohio

    International Nuclear Information System (INIS)

    Anderson, H.F.; Bantz, P.D.; Luthy, D.F.

    1996-01-01

    The Mound Plant was one of several production sites in the US Department of Energy's Defense Programs (DP) Weapons Complex. As a result of the downsizing of the weapons program, certain operations at Mound are being transferred to other DOE sites and the DP buildings at Mound are being shutdown. The objectives of the program are to reduce the hazardous and financial liabilities to DOE and to foster the reuse of facilities for economic development. The overall program is described. The process began with the categorization of excess DP buildings into three groups depending on their anticipated future use. The draft DOE/EM-60 Acceptance Criteria were used to develop a detailed shutdown checklist as the foundation of the process. The overall program budget, schedule, ad options for disposition of materials and components is presented. Accomplishments in FY94 and FY95 are described. By the end of FY95, all excess energetic materials and components, all excess chemicals (from non-radiation areas) and significant amounts of radioactive materials have been removed from the site. By the end of FY95, 47 of the 72 buildings in the program have been taken through all ten of the draft EM-60 acceptance criteria. Lessons learned, based on experience at Mound to date, are summarized

  19. Whistleblowers ask Congress to investigate TVA's nuclear power program

    International Nuclear Information System (INIS)

    Lane, E.

    1993-01-01

    Congress should investigate the Tennessee Valley Authority's nuclear power plant construction and operations programs as soon as possible, a coalition of Tennessee environmentalists and whistleblowers told reporters at a press conference in Washington, DC. The Foundation for Global Sustainability and four employees of TVA nuclear plants called for congressional action because they contend the Nuclear Regulatory Commission and the Department of Labor have failed to act to protect whistleblowers who report nuclear safety problems. The foundation contends the economics of nuclear plant construction by TVA do not make sense and in the rush to finish the Watts Bar nuclear plant, which has been under construction for 20 years, TVA has ignored safety issues

  20. The Abbott School Construction Program: Report on the NJ Department of Education Proposed Regulations on Long-Range Facilities Plans

    Science.gov (United States)

    Ponessa, Joan

    2004-01-01

    This report on Long Range Facilities Plans (LRFPs) analyzes regulations proposed by the New Jersey Department of Education (NJDOE) to implement the Educational Facilities Construction and Financing Act. (EFCFA). EFCFA, which authorizes and governs New Jersey's public school construction program, was enacted in July 2000 to implement the State…

  1. Atomic physics with highly-charged heavy ions at the GSI future facility: The scientific program of the SPARC collaboration

    International Nuclear Information System (INIS)

    Stoehlker, Th.; Beier, T.; Beyer, H.F.; Bosch, F.; Braeuning-Demian, A.; Gumberidze, A.; Hagmann, S.; Kozhuharov, C.; Kuehl, Th.; Liesen, D.; Mann, R.; Mokler, P.H.; Quint, W.; Schuch, R.; Warczak, A.

    2005-01-01

    In the current report a short overview about the envisioned program of the atomic physics research collaboration SPARC (Stored Particle Atomic Research Collaboration, at the new international accelerator Facility for Antiproton and Ion Research (FAIR) at GSI is given. In addition, a condensed description of the planned experimental areas devoted to atomic physics research at the new facility is presented

  2. The effect of facility-based antiretroviral therapy programs on outpatient services in Kenya and Uganda.

    Science.gov (United States)

    Wollum, Alexandra; Dansereau, Emily; Fullman, Nancy; Achan, Jane; Bannon, Kelsey A; Burstein, Roy; Conner, Ruben O; DeCenso, Brendan; Gasasira, Anne; Haakenstad, Annie; Hanlon, Michael; Ikilezi, Gloria; Kisia, Caroline; Levine, Aubrey J; Masters, Samuel H; Njuguna, Pamela; Okiro, Emelda A; Odeny, Thomas A; Allen Roberts, D; Gakidou, Emmanuela; Duber, Herbert C

    2017-08-16

    Considerable debate exists concerning the effects of antiretroviral therapy (ART) service scale-up on non-HIV services and overall health system performance in sub-Saharan Africa. In this study, we examined whether ART services affected trends in non-ART outpatient department (OPD) visits in Kenya and Uganda. Using a nationally representative sample of health facilities in Kenya and Uganda, we estimated the effect of ART programs on OPD visits from 2007 to 2012. We modeled the annual percent change in non-ART OPD visits using hierarchical mixed-effects linear regressions, controlling for a range of facility characteristics. We used four different constructs of ART services to capture the different ways in which the presence, growth, overall, and relative size of ART programs may affect non-ART OPD services. Our final sample included 321 health facilities (140 in Kenya and 181 in Uganda). On average, OPD and ART visits increased steadily in Kenya and Uganda between 2007 and 2012. For facilities where ART services were not offered, the average annual increase in OPD visits was 4·2% in Kenya and 13·5% in Uganda. Among facilities that provided ART services, we found average annual OPD volume increases of 7·2% in Kenya and 5·6% in Uganda, with simultaneous annual increases of 13·7% and 12·5% in ART volumes. We did not find a statistically significant relationship between annual changes in OPD services and the presence, growth, overall, or relative size of ART services. However, in a subgroup analysis, we found that Ugandan hospitals that offered ART services had statistically significantly less growth in OPD visits than Ugandan hospitals that did not provide ART services. Our findings suggest that ART services in Kenya and Uganda did not have a statistically significant deleterious effects on OPD services between 2007 and 2012, although subgroup analyses indicate variation by facility type. Our findings are encouraging, particularly given recent recommendations

  3. Evaluation of the Nuclear Medicine facilities in Minas Gerais state: quality control program of equipment

    International Nuclear Information System (INIS)

    Kubo, Tadeu Takao Almodovar; Biancardi, Rodrigo; Rocha, Adriana Marcia Guimaraes; Ferreira, Denia Romao; Silva, Franciele Aquiles Anjos; Assuncao, Jonathan Buenos Aires; Alves, Ederson Henrique; Almeida, Ana Flavia Batista; Alves, Nathalia Fernandes; Xavier, Faber Henrique Zacarias; Gontijo, Rodrigo Modesto Gadelha; Mamede, Marcelo; Universidade Federal de Minas Gerais

    2017-01-01

    With the reformulation of the CNEN-NN-3.05 standard in December 2013, Brazil's Nuclear Medicine (NMS) services have to perform a greater number of quality controls for SPECT and PET equipment. However, little is known about the reality of the quality control programs of these services regarding the application of the new standard. Thus, in this context, the objective of the present study was to evaluate the quality control program of MNSs in the state of Minas Gerais. All NMSs in the state of Minas Gerais were invited to participate in the project. Of these, 34.48% (20 facilities) agreed to participate in the project, 50.00% (29 facilities) did not respond to the invitation and 15.52%(9 facilities) declined their participation. Thus, as of November 2015, 20 SPECT and 2 PET/CT equipment were evaluated for the performance of the quality control tests recommended by the new CNEN standard. The phantoms required for the evaluation came from the Laboratory of Dosimetry and Quality Control of UFMG. Even with the deadlines set by CNEN for the implementation of the quality control program in the NMSs, more than 50% of the evaluated services did not implement the quality controls, and the absence of specific phantoms is the main reason for the failure. Among the problems found in the installations, the most critical were: collimators with no conditions of use in the clinical routine, linearity problems of the evaluated image and values of image uniformity superior to the limits of acceptance. Problems in the uniformity and linearity of the image found directly impacted the performance of other tests, such as spatial resolution, SPECT performance, among others. In a general way, the NMSs in the state of Minas Gerais evaluated with the present study are in clinical feasible conditions. (author)

  4. Investigation and analysis of neutron emission characteristics in Denaplasma focus facility

    International Nuclear Information System (INIS)

    Goodarzi, Sh.; Amrollahi, R.; Babazadeh, A.; Nasiri, A.

    2003-01-01

    Since the first experiments with plasma focus facilities in 1960' s. These devices are known as intense sources of neutron when the working gas contains deuterium with a proper density. Most of the emitted neutrons are produced by D-D reactions, but the mechanism of these reactions in not still clear completely. In this paper, the results of experimental investigations of neutron emission characteristics in D ena p lasma focus facility (Filipov type, 90 kJ, 25 kV) over a range of discharge voltages and pressures are presented. Out working gases are D 2 and D 2+%1 Kr, two different conic and flat insert anodes were employed. We have simultaneously measured the total emission in our experiments for analyzing the neutron generation mechanism in this device. We have found the upper and lower pressure limits and the optimum pressure for neutron generation, and we have observed the double pluses structure of neutron signal for the first time in this device. Form the experimental results, it seems that both thermonuclear and no thermonuclear mechanisms are always present in neutron generation, but their contribution in the total yield is strongly dependent on experimental conditions (initial pressure, discharge voltage, gas admixture, etc.). It was found that the range of variation of total neutron yield and neutron emission anisotropy factor for experiments with D + %1 Kr is wider than experiments with D 2, and the best neutron emission results belongs to discharges in D 2 + %1 Kr with a conic insert anode. By employing D 2 + %1 Kr with a conic insert anode, and varying pressure between 0.3-2 torr at a discharge voltage of 16 kV, it can be deduced that in low pressures ( n ∝ I α ρ ∝E α / 2 was found about 3.62 for D 2 + %1 Kr and 3 for D 2

  5. TMI-2 Vessel Investigation Project (VIP) Metallurgical Program

    International Nuclear Information System (INIS)

    Diercks, D.R.; Neimark, L.A.

    1991-01-01

    The Three Mile Island Unite 2 (TMI-2) Vessel Investigation Project Metallurgical Program is a part of the international TMI-2 Vessel Investigation Project being conducted jointly by the U.S. Nuclear Regulatory Commission and the Organization for Economic Cooperation and Development. The objectives of the metallurgical program are to deduce the temperatures of, determine the mechanical properties of, and assess the integrity of the TMI-2 lower head during the loss-of-coolant accident. Fifteen samples have been removed from the lower head and are being examined. In addition, archive material from the lower head of the Midland nuclear reactor has been procured for conducting supplemental metallurgical evaluations and mechanical property determinations. Evaluations of the microstructure and mechanical properties of the as-received archive material have been completed, and a series of heat treatment experiments has been conducted to develop standard microstructures to be compared with those present in the TMI-2 samples. Results have been obtained from examinations of two of the fifteen TMI-2 lower head samples. These results indicate that one of these two samples, which contained cracks in the weld cladding extending ∼3 mm into the underlying base metal, apparently reached temperatures on the order of 1000 to 1100C during the accident. A preliminary examination of the core debris deposited on this sample has been performed. The other sample, from an area away from the region of core relocation, did not exceed 727C during the accident

  6. Investigating Public Facility Characteristics from a Spatial Interaction Perspective: A Case Study of Beijing Hospitals Using Taxi Data

    Directory of Open Access Journals (Sweden)

    Xiaoqing Kong

    2017-02-01

    Full Text Available Services provided by public facilities are essential to people’s lives and are closely associated with human mobility. Traditionally, public facility access characteristics, such as accessibility, equity issues and service areas, are investigated mainly based on static data (census data, travel surveys and particular records, such as medical records. Currently, the advent of big data offers an unprecedented opportunity to obtain large-scale human mobility data, which can be used to study the characteristics of public facilities from the spatial interaction perspective. Intuitively, spatial interaction characteristics and service areas of different types and sizes of public facilities are different, but how different remains an open question, so we, in turn, examine this question. Based on spatial interaction, we classify public facilities and explore the differences in facilities. In the research, based on spatial interaction extracted from taxi data, we introduce an unsupervised classification method to classify 78 hospitals in 6 districts of Beijing, and the results better reflect the type of hospital. The findings are of great significance for optimizing the spatial configuration of medical facilities or other types of public facilities, allocating public resources reasonably and relieving traffic pressure.

  7. Mathematical programming models for solving in equal-sized facilities layout problems. A genetic search method

    International Nuclear Information System (INIS)

    Tavakkoli-Moghaddam, R.

    1999-01-01

    This paper present unequal-sized facilities layout solutions generated by a genetic search program. named Layout Design using a Genetic Algorithm) 9. The generalized quadratic assignment problem requiring pre-determined distance and material flow matrices as the input data and the continuous plane model employing a dynamic distance measure and a material flow matrix are discussed. Computational results on test problems are reported as compared with layout solutions generated by the branch - and bound algorithm a hybrid method merging simulated annealing and local search techniques, and an optimization process of an enveloped block

  8. Beam trajectory simulation program at the National Institute of Nuclear Research Tandem Accelerator facility

    International Nuclear Information System (INIS)

    Murillo C, G.

    1996-01-01

    The main object of this thesis is to show in a clear and simple way to the people in general, the function of the Tandem Accelerator located on site the ININ facilities. For this presentation, a computer program was developed. The software written in C language in a structural form, simulates the ion production and its trajectory in a schematic and in an easy way to comprehend. According to the goals of this work, the simulation also shows details of some of the machine components like the source, the accelerator cavity, ,and the bombarding chamber. Electric and magnetic fields calculations are included for the 90 degrees bending magnet and quadrupoles. (Author)

  9. The LEU target development and conversion program for the MAPLE reactors and new processing facility

    International Nuclear Information System (INIS)

    Malkoske, G.R.

    2002-01-01

    Historically, the production of molybdenum-99 in the NRU research reactors at Chalk River, Canada has been extracted from reactor targets employing highly enriched uranium (HEU). A reliable supply of HEU metal from the United States used in the manufacture of targets for the NRU research reactor has been a key factor to enable MDS Nordion to develop a secure supply of medical isotopes for the international nuclear medicine community. The molybdenum extraction process from HEU targets provides predictable, consistent yields for our high-volume molybdenum production process. Each link of the isotope supply chain, from isotope production to ultimate use by the physician, has been established using this proven and established method of HEU target irradiation and processing to extract molybdenum-99. To ensure a continued reliable and timely supply of medical isotopes, MDS Nordion is completing the construction of two MAPLE reactors and a New Processing Facility. The design of the MAPLE facilities was based on an established process developed by Atomic Energy of Canada Ltd. (AECL) - extraction of isotopes from HEU target material. However, in concert with the global trend to utilize low enriched uranium (LEU) in research reactors, MDS Nordion has launched a three phase LEU Target Development and Conversion Program for the MAPLE facilities. Phase 1, the Initial Feasibility Study, which identified the technical issues to convert the MAPLE reactor targets from HEU to LEU for large scale commercial production was reported on at the RERTR- 2000 conference. The second phase of the LEU Target Development and Conversion Program was developed with extensive consultation and involvement of experts knowledgeable in target development, process system design, enriched uranium conversion chemistry and commercial scale reactor operations and molybdenum production. This paper will provide an overview of the Phase 2 Conversion Development Program, report on progress to date, and further

  10. Oak Ridge Reservation Federal Facility Agreement for the Environmental Restoration Program. Volume 4

    International Nuclear Information System (INIS)

    1993-10-01

    This quarterly progress report satisfies requirements for the Environmental Restoration (ER) Program that are specified in the Oak Ridge Reservation (ORR) Federal Facility Agreement (FFA) established between the U.S. Department of Energy (DOE), the U.S. Environmental protection Agency (EPA), and the Tennessee Department of Environment and Conservation (TDEC). The reporting period covered is July through September 1993 (fourth quarter of FY 1993). Sections 1.1 and 1.2 provide respectively the milestones scheduled for completion during the reporting period and a list of documents that have been proposed for transmittal during the following quarter but have not been approved as FY 1994 commitments

  11. Second session: operating European facilities and their programs; Session 2: Les installations Europeennes actuelles et leurs programmes

    Energy Technology Data Exchange (ETDEWEB)

    Iracane, D. [CEA Saclay, Dir. de l' Energie Nucleaire (DEN), 91 - Gif sur Yvette (France); Porracchia, A.; Fougeras, P.; Morey, J.M. [CEA Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d' Etudes des Reacteurs; Loubiere, S.; Durande-Ayme, P. [CEA Saclay, Nuclear Energy Div., Reactors and Nuclear Services Deptment, 91 - Gif-sur-Yvette (France); Guidez, J.; Goux, D. [CEA Valrho, Dir. de l' Energie Nucleaire, DEN, 30 - Marcoule (France); Dupraz, R.; Brand, B. [FRAMATOME, AREVA-FANP, 69 - Lyon (France); Blanc, J.Y. [CEA Saclay, 91 - Gif sur Yvette (France); Perthuis, S. de [FRAMATOME ANP, 92 - Paris-La-Defence (France); Le Rouzic, J.F. [Electricite de France (EDF), 92 - Clamart (France)

    2005-07-01

    Most European nuclear post-irradiation examination facilities are ageing and the optimization of the remaining infrastructures may lead to connect them through a network implying consistent staff competence between countries and efficient nuclear material transport means. The second article describes the 3 very-low power research reactors operating in France: Minerve, Masurca and Eole. The Osiris reactor is presented in the third article, the author focuses on the devices available in Osiris to perform irradiation in light water reactor conditions and in high temperature reactor conditions and on the associated programs. Phenix reactor located on the Marcoule site had been performing from 1974 to 1990 the necessary technological qualifications required by the fast reactor system. An important upgrading program, led from 1994 to 2003, has allowed the reactor to begin a second life. Its investigation program encompasses research work on the transmutation of actinides and fission products and on new nuclear fuels and materials required for the future fourth generation of reactors. In Europe about 20 hot laboratories offer services to perform examination and qualification required by their national civil nuclear programs. Most are state-owned and show a large range of activities: nuclear fuels, materials, reprocessing, radio-nuclides, and radio-active sources. The last article reviews the main test loops operating in France and in neighboring countries. About 30 installations are reported and classified according to their activity fields : critical heat flux, hydro-mechanics, device testing, accidental situations, helium and severe reactor accidents. (A.C.)

  12. An investigation of high-temperature irradiation test program of new ceramic materials

    International Nuclear Information System (INIS)

    Ishino, Shiori; Terai, Takayuki; Oku, Tatsuo

    1999-08-01

    The Japan Atomic Energy Research Institute entrusted the Atomic Energy Society of Japan with an investigation into the trend of irradiation processing/damage research on new ceramic materials. The present report describes the result of the investigation, which was aimed at effective execution of irradiation programs using the High Temperature Engineering Test Reactor (HTTR) by examining preferential research subjects and their concrete research methods. Objects of the investigation were currently on-going preliminary tests of functional materials (high-temperature oxide superconductor and high-temperature semiconductor) and structural materials (carbon/carbon and SiC/SiC composite materials), together with newly proposed subjects of, e.g., radiation effects on ceramics-coated materials and super-plastic ceramic materials as well as microscopic computer simulation of deformation and fracture of ceramics. These works have revealed 1) the background of each research subject, 2) its objective and significance from viewpoints of science and engineering, 3) research methodology in stages from preliminary tests to real HTTR irradiation, and 4) concrete HTTR-irradiation methods which include main specifications of test specimens, irradiation facilities and post-irradiation examination facilities and apparatuses. The present efforts have constructed the important fundamentals in the new ceramic materials field for further planning and execution of the innovative basic research on high-temperature engineering. (author)

  13. Seismic investigations of the HDR Safety Program. Summary report

    International Nuclear Information System (INIS)

    Malcher, L.; Schrammel, D.; Steinhilber, H.; Kot, C.A.

    1994-08-01

    The primary objective of the seismic investigations, performed at the HDR facility in Kahl/Main, FRG was to validate calculational methods for the seismic evaluation of nuclear-reactor systems, using experimental data from an actual nuclear plant. Using eccentric mass shaker excitation the HDR soil/structure system was tested to incipient failure, exhibiting highly nonlinear response and demonstrating that structures not seismically designed can sustain loads equivalent to a design basin earthquake (DBE). Load transmission from the structure to piping/equipment indicated significant response amplifications and shifts to higher frequencies, while the response of tanks/vessels depended mainly on their support conditions. The evaluation of various piping support configurations demonstrated that proper system design (for a given spectrum) rather than number of supports or system stiffness is important to limiting pipe greens. Piping at loads exceeding the DBE eightfold still had significant margins and failure is improbable inspite of multiple support failures. The mean value for pipe damping, even under extreme loads, was found to be about 4%. Comparison of linear and nonlinear computational results with piping response measurements showed that predictions have a wide scatter and do not necessarily yield conservative responses underpredicting, in particular, peak support forces. For the soil/structure system the quality of the predictions did not depend so much on the complexity of the modeling, but rather on whether the model captured the salient features and nonlinearities of the system

  14. Oak Ridge Reservation Federal Facility Agreement: Quarterly report for the Environmental Restoration Program. Volume 2, January--March 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    This report provides information about ER Program activities conducted on the Oak Ridge Reservation under the Federal Facility Agreement (FFA). Specifically, it includes information on milestones scheduled for completion during the reporting period as well as scheduled for completion during the next reporting period (quarter), accomplishments of the ER Program, concerns related to program work, and scheduled activities for the next quarter. It also provides a listing of the identity and assigned tasks of contractors performing ER Program work under the FFA.

  15. Performance investigation of a salt gradient solar pond coupled with desalination facility near the Dead Sea

    International Nuclear Information System (INIS)

    Saleh, A.; Qudeiri, J.A.; Al-Nimr, M.A.

    2011-01-01

    Solar ponds provide the most convenient and least expensive option for heat storage for daily and seasonal cycles. This is particularly important for a desalination facility, if steady and constant water production is required. If, in addition to high storage capacity, other favorable conditions exist, the salt gradient solar ponds (SGSPs) are expected to be able to carry the entire load of a large-scale flash desalination plants without dependence upon supplementary sources. This paper presents a performance investigation of a SGSP coupled with desalination plant under Jordanian climatic conditions. This is particularly convenient in the Dead Sea region characterized by high solar radiation intensities, high ambient temperature most of the year, and by the availability of high concentration brine. It was found that a 3000 m 2 solar pond installed near the Dead Sea is able to provide an annual average production rate of 4.3 L min -1 distilled water compared with 3.3 L min -1 that would be produced by El Paso solar pond, which has the same surface area. Based on this study, solar ponds appear to be a feasible and an appropriate technology for water desalination near the Dead Sea in Jordan. -- Research highlights: → A performance investigation of a solar pond coupled with desalination plant. → Dead Sea area is characterized by availability of high solar radiation and brine. → The Dead Sea solar pond can provide production rate of 4.3 L min -1 . → El Paso solar pond has production rate of 3.32 L min -1 . The improvement is about 30%. → The solar pond with desalination investigated showed to be a feasible technology.

  16. Environmental Restoration Program pollution prevention checklist guide for the facility characterization project phase

    International Nuclear Information System (INIS)

    1993-09-01

    A facility characterization (FC) is conducted to determine the nature and extent contamination at a potential hazardous facility waste site. The information gathered during an FC includes (1) data on the volume and chemical nature of the waste, (2) information on the extent of contamination and the migration potential of the contaminants, (3) preliminary information on evaluation of alternative concepts that can or cannot be considered, and (4)supportive technical and cost data. For the purposes of identification, the following operational phases will be used for definition for this phase of the decommissioning and decontamination process (1) facility characterization before clean up, (2) characterization during clean up, (3) characterization of waste materials, and (4) site characterization after clean up. A key consideration in this process is the prevention of any waste to be generated from these characterization activities. The purpose of this checklist guide is to assist users with incorporating pollution prevention/waste minimization (PP/WM) in all FC phase projects of the Environmental Restoration (ER) Program. This guide will help users document PP/WM activities for technology transfer and reporting requirements. Automated computer screens will be created from the checklist data to assist users with implementing and evaluating waste reduction

  17. A conversion development program to LEU targets for medical isotope production in the MAPLE Facilities

    International Nuclear Information System (INIS)

    Malkoske, G.R.

    2000-01-01

    Historically, the production of molybdenum-99 in the NRU research reactors at Chalk River, Canada has been extracted from reactor targets employing highly enriched uranium (HEU). The molybdenum extraction process from the HEU targets provided predictable, consistent yields for our high-volume molybdenum production process. A reliable supply of HEU for the NRU research reactor targets has enabled MDS Nordion to develop a secure chain of medical isotope supply for the international nuclear medicine community. Each link of the isotope supply chain, from isotope production to patient application, has been established on a proven method of HEU target irradiation and processing. To ensure a continued reliable and timely supply of medical isotopes, the design of the MAPLE facilities was based on our established process - extraction of isotopes from HEU target material. However, in concert with the global trend to utilize low enriched uranium (LEU) in research reactors, MDS Nordion has launched a program to convert the MAPLE facilities to LEU targets. An initial feasibility study was initiated to identify the technical issues to convert the MAPLE targets from HEU to LEU. This paper will present the results of the feasibility study. It will also describe future challenges and opportunities in converting the MAPLE facilities to LEU targets for large scale, commercial medical isotope production. (author)

  18. Medicare Program; Inpatient Rehabilitation Facility Prospective Payment System for Federal Fiscal Year 2018. Final rule.

    Science.gov (United States)

    2017-08-03

    This final rule updates the prospective payment rates for inpatient rehabilitation facilities (IRFs) for federal fiscal year (FY) 2018 as required by the statute. As required by section 1886(j)(5) of the Social Security Act (the Act), this rule includes the classification and weighting factors for the IRF prospective payment system's (IRF PPS) case-mix groups and a description of the methodologies and data used in computing the prospective payment rates for FY 2018. This final rule also revises the International Classification of Diseases, 10th Revision, Clinical Modification (ICD-10-CM) diagnosis codes that are used to determine presumptive compliance under the "60 percent rule," removes the 25 percent payment penalty for inpatient rehabilitation facility patient assessment instrument (IRF-PAI) late transmissions, removes the voluntary swallowing status item (Item 27) from the IRF-PAI, summarizes comments regarding the criteria used to classify facilities for payment under the IRF PPS, provides for a subregulatory process for certain annual updates to the presumptive methodology diagnosis code lists, adopts the use of height/weight items on the IRF-PAI to determine patient body mass index (BMI) greater than 50 for cases of single-joint replacement under the presumptive methodology, and revises and updates measures and reporting requirements under the IRF quality reporting program (QRP).

  19. Oregon state university's advanced plant experiment (APEX) AP1000 integral facility test program

    International Nuclear Information System (INIS)

    Reyes, J.N.; Groome, J.T.; Woods, B.G.; Young, E.; Abel, K.; Wu, Q.

    2005-01-01

    Oregon State University (OSU) has recently completed a three year study of the thermal hydraulic behavior of the Westinghouse AP1000 passive safety systems. Eleven Design Basis Accident (DBA) scenarios, sponsored by the U.S. Department of Energy (DOE) with technical support from Westinghouse Electric, were simulated in OSU's Advanced Plant Experiment (APEX)-1000. The OSU test program was conducted within the purview of the requirements of 10CFR50 Appendix B, NQA-1 and 10 CFR 21 and the test data was used to provide benchmarks for computer codes used in the final design approval of the AP1000. In addition to the DOE certification testing, OSU conducted eleven confirmatory tests for the U.S. Nuclear Regulatory Commission. This paper presents the test program objectives, a description of the APEX-1000 test facility and an overview of the test matrix that was conducted in support of plant certification. (authors)

  20. Development and implementation of a construction environmental protection program at a solid radioactive waste management facility

    Energy Technology Data Exchange (ETDEWEB)

    Wong, T.S. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada); Bishop, T. [Atomic Energy of Canada Limited, Saint John, New Brunswick (Canada); Hickman, C.N. [Point Lepreau Generating Station, Saint John, New Brunswick (Canada)

    2007-07-01

    Refurbishment of ageing nuclear stations has great economic and environmental benefits, including reduced greenhouse gas emissions. The Government of New Brunswick (NB) decided in 2005 to refurbish the Point Lepreau Generating Station with Atomic Energy of Canada Limited (AECL) as the general contractor. The project includes construction of additional radioactive waste management facilities. AECL developed, for the construction project, an environmental protection program to comply with commitments made during the environmental assessment process, and regulatory requirements. The program covers detailed environmental plans, training courses, and engagement of consultants to provide training and conduct monitoring of the construction activities. Construction related environmental effects have been successfully mitigated and the monitoring results indicate compliance with all environmental requirements. (author)

  1. Program user's manual: cryogen system for the analysis for the Mirror Fusion Test Facility

    International Nuclear Information System (INIS)

    1979-04-01

    The Mirror Fusion Test Facility being designed and constructed at the Lawrence Livermore Laboratory requires a liquid helium liquefaction, storage, distribution, and recovery system and a liquid nitrogen storage and distribution system. To provide a powerful analytical tool to aid in the design evolution of this system through hardware, a thermodynamic fluid flow model was developed. This model allows the Lawrence Livermore Laboratory to verify that the design meets desired goals and to play what if games during the design evolution. For example, what if the helium flow rate is changed in the magnet liquid helium flow loop; how does this affect the temperature, fluid quality, and pressure. This manual provides all the information required to run all or portions of this program as desired. In addition, the program is constructed in a modular fashion so changes or modifications can be made easily to keep up with the evolving design

  2. Shared use of school facilities with community organizations and afterschool physical activity program participation: a cost-benefit assessment.

    Science.gov (United States)

    Kanters, Michael A; Bocarro, Jason N; Filardo, Mary; Edwards, Michael B; McKenzie, Thomas L; Floyd, Myron F

    2014-05-01

    Partnerships between school districts and community-based organizations to share school facilities during afterschool hours can be an effective strategy for increasing physical activity. However, the perceived cost of shared use has been noted as an important reason for restricting community access to schools. This study examined shared use of middle school facilities, the amount and type of afterschool physical activity programs provided at middle schools together with the costs of operating the facilities. Afterschool programs were assessed for frequency, duration, and type of structured physical activity programs provided and the number of boys and girls in each program. School operating costs were used to calculate a cost per student and cost per building square foot measure. Data were collected at all 30 middle schools in a large school district over 12 months in 2010-2011. Policies that permitted more use of school facilities for community-sponsored programs increased participation in afterschool programs without a significant increase in operating expenses. These results suggest partnerships between schools and other community agencies to share facilities and create new opportunities for afterschool physical activity programs are a promising health promotion strategy. © 2014, American School Health Association.

  3. Programs for visualization, handling and quantification of PIXE maps at the AGLAE facility

    International Nuclear Information System (INIS)

    Pichon, L.; Calligaro, T.; Lemasson, Q.; Moignard, B.; Pacheco, C.

    2015-01-01

    The external beam setup of the AGLAE facility has been developed in order to combine PIXE with PIGE, EBS and recently IBIL for the analysis of cultural heritage artefacts. The upgraded external beam end-station integrates five large solid angle X-ray detectors either to reduce the risk of damage on sensitive artworks by decreasing the beam intensity or to routinely acquire elemental maps at various scales. While many programs are available to process PIXE maps acquired with nuclear microprobes, a software to process the major and trace elements PIXE maps point by point using GUPIX is not available. The present paper describes three programs developed for the AGLAE facility to process numerous maps obtained with multiple detectors. AGLAEMAP allows to handle maps and pixel groups within maps, TRAUPIXE to process quantitatively PIXE spectra of all pixels and DATAIMAGING to display the resulting quantitative elemental maps. The benefits of this software suite are demonstrated by processing a dataset acquired on a pellet of geostandard reference material and on a terre mêlée pottery shard sample created by the famous ceramist Bernard Palissy (1510–1589), highlighting chemical elements present in this polychrome ceramic.

  4. Programs for visualization, handling and quantification of PIXE maps at the AGLAE facility

    Energy Technology Data Exchange (ETDEWEB)

    Pichon, L., E-mail: laurent.pichon@culture.fr [Centre de recherche et de restauration des musées de France, C2RMF, Palais du Louvre – Porte des Lions, 14 Quai François Mitterrand, 75001 Paris (France); Fédération de recherche NewAGLAE, FR3506 CNRS, Ministère de la Culture et de la Communication, Chimie ParisTech, Palais du Louvre, 75001 Paris (France); Calligaro, T. [Centre de recherche et de restauration des musées de France, C2RMF, Palais du Louvre – Porte des Lions, 14 Quai François Mitterrand, 75001 Paris (France); Fédération de recherche NewAGLAE, FR3506 CNRS, Ministère de la Culture et de la Communication, Chimie ParisTech, Palais du Louvre, 75001 Paris (France); PSL Research University, Chimie ParisTech-CNRS, Institut de Recherche Chimie Paris, UMR8247, 75005 Paris (France); Lemasson, Q.; Moignard, B.; Pacheco, C. [Centre de recherche et de restauration des musées de France, C2RMF, Palais du Louvre – Porte des Lions, 14 Quai François Mitterrand, 75001 Paris (France); Fédération de recherche NewAGLAE, FR3506 CNRS, Ministère de la Culture et de la Communication, Chimie ParisTech, Palais du Louvre, 75001 Paris (France)

    2015-11-15

    The external beam setup of the AGLAE facility has been developed in order to combine PIXE with PIGE, EBS and recently IBIL for the analysis of cultural heritage artefacts. The upgraded external beam end-station integrates five large solid angle X-ray detectors either to reduce the risk of damage on sensitive artworks by decreasing the beam intensity or to routinely acquire elemental maps at various scales. While many programs are available to process PIXE maps acquired with nuclear microprobes, a software to process the major and trace elements PIXE maps point by point using GUPIX is not available. The present paper describes three programs developed for the AGLAE facility to process numerous maps obtained with multiple detectors. AGLAEMAP allows to handle maps and pixel groups within maps, TRAUPIXE to process quantitatively PIXE spectra of all pixels and DATAIMAGING to display the resulting quantitative elemental maps. The benefits of this software suite are demonstrated by processing a dataset acquired on a pellet of geostandard reference material and on a terre mêlée pottery shard sample created by the famous ceramist Bernard Palissy (1510–1589), highlighting chemical elements present in this polychrome ceramic.

  5. Radiation safety program in high dose rate brachytherapy facility at INHS Asvini

    Directory of Open Access Journals (Sweden)

    Kirti Tyagi

    2014-01-01

    Full Text Available Brachytherapy concerns primarily the use of radioactive sealed sources which are inserted into catheters or applicators and placed directly into tissue either inside or very close to the target volume. The use of radiation in treatment of patients involves both benefits and risks. It has been reported that early radiation workers had developed radiation induced cancers. These incidents lead to continuous work for the improvement of radiation safety of patients and personnel The use of remote afterloading equipment has been developed to improve radiation safety in the delivery of treatment in brachytherapy. The widespread adoption of high dose rate brachytherapy needs appropriate quality assurance measures to minimize the risks to both patients and medical staff. The radiation safety program covers five major aspects: quality control, quality assurance, radiation monitoring, preventive maintenance, administrative measures and quality audit. This paper will discuss the radiation safety program developedfor a high dose rate brachytherapy facility at our centre which may serve as a guideline for other centres intending to install a similar facility.

  6. NIST Accelerator Facilities And Programs In Support Of Industrial Radiation Research

    International Nuclear Information System (INIS)

    Bateman, F.B.; Desrosiers, M.F.; Hudson, L.T.; Coursey, B.M.; Bergstrom, P.M. Jr.; Seltzer, S.M.

    2003-01-01

    NIST's Ionizing Radiation Division maintains and operates three electron accelerators used in a number of applications including waste treatment and sterilization, radiation hardness testing, detector calibrations and materials modification studies. These facilities serve a large number of governmental, academic and industrial users as well as an active intramural research program. They include a 500 kV cascaded-rectifier accelerator, a 2.5 MV electron Van de Graaff accelerator and a 7 to 32 MeV electron linac, supplying beams ranging in energy from a few keV up to 32 MeV. In response to the recent anthrax incident, NIST along with the US Postal Service and the Armed Forces Radiobiology Research Institute (AFRRI) are working to develop protocols and testing procedures for the USPS mail sanitization program. NIST facilities and personnel are being employed in a series of quality-assurance measurements for both electron- and photon-beam sanitization. These include computational modeling, dose verification and VOC (volatile organic compounds) testing using megavoltage electron and photon sources

  7. LEU-HTR critical experiment program for the PROTEUS facility in Switzerland

    International Nuclear Information System (INIS)

    Brogli, R.; Bucher, K.H.; Chawla, R.; Foskolos, K.; Luchsinger, H.; Mathews, D.; Sarlos, G.; Seiler, R.

    1990-01-01

    New critical experiments in the framework of an IAEA Coordinated Research Program on 'Validation of Safety Related Reactor Physics Calculations for Low Enriched HTRs' are planned at the PSI PROTEUS facility. The experiments are designed to supplement the experimental data base and reduce the design and licensing uncertainties for small- and medium-sized helium-cooled reactors using low-enriched uranium (LEU) and graphite high temperature fuel. The main objectives of the new experiments are to provide first-of-a-kind high quality experimental data on: 1) The criticality of simple, easy to interpret, single core region LEU HTR systems for several moderator-to-fuel ratios and several lattice geometries; 2) the changes in reactivity, neutron balance components and control rod effectiveness caused by water ingress into this type of reactor, and 3) the effects of the boron and/or hafnium absorbers that are used to modify the reactivity and the power distributions in typical HTR systems. Work on the design and licensing of the modified PROTEUS critical facility is now in progress with the HTR experiments scheduled to begin early in 1991. Several international partners will be involved in the planning, execution and analysis of these experiments in order to insure that they are relevant and cost effective with respect to the various gas cooled reactor national programs. (author)

  8. MGR COMPLIANCE PROGRAM GUIDANCE PACKAGE FOR RADIATION PROTECTION EQUIPMENT, INSTRUMENTATION, AND FACILITIES

    International Nuclear Information System (INIS)

    2000-01-01

    This Compliance Program Guidance Package identifies the regulatory guidance and industry codes and standards addressing radiation protection equipment, instrumentation, and support facilities considered to be appropriate for radiation protection at the Monitored Geologic Repository (MGR). Included are considerations relevant to radiation monitoring instruments, calibration, contamination control and decontamination, respiratory protection equipment, and general radiation protection facilities. The scope of this Guidance Package does not include design guidance relevant to criticality monitoring, area radiation monitoring, effluent monitoring, and airborne radioactivity monitoring systems since they are considered to be the topics of specific design and construction requirements (i.e., ''fixed'' or ''built-in'' systems). This Guidance Package does not address radiation protection design issues; it addresses the selection and calibration of radiation monitoring instrumentation to the extent that the guidance is relevant to the operational radiation protection program. Radon and radon progeny monitoring instrumentation is not included in the Guidance Package since such naturally occurring radioactive materials do not fall within the NRC's jurisdiction at the MGR

  9. LEU-HTR critical experiment program for the PROTEUS facility in Switzerland

    Energy Technology Data Exchange (ETDEWEB)

    Brogli, R; Bucher, K H; Chawla, R; Foskolos, K; Luchsinger, H; Mathews, D; Sarlos, G; Seiler, R [Paul Scherrer Institute, Laboratory for Reactor Physics and System Technology Wuerenlingen and Villigen, Villigen PSI (Switzerland)

    1990-07-01

    New critical experiments in the framework of an IAEA Coordinated Research Program on 'Validation of Safety Related Reactor Physics Calculations for Low Enriched HTRs' are planned at the PSI PROTEUS facility. The experiments are designed to supplement the experimental data base and reduce the design and licensing uncertainties for small- and medium-sized helium-cooled reactors using low-enriched uranium (LEU) and graphite high temperature fuel. The main objectives of the new experiments are to provide first-of-a-kind high quality experimental data on: 1) The criticality of simple, easy to interpret, single core region LEU HTR systems for several moderator-to-fuel ratios and several lattice geometries; 2) the changes in reactivity, neutron balance components and control rod effectiveness caused by water ingress into this type of reactor, and 3) the effects of the boron and/or hafnium absorbers that are used to modify the reactivity and the power distributions in typical HTR systems. Work on the design and licensing of the modified PROTEUS critical facility is now in progress with the HTR experiments scheduled to begin early in 1991. Several international partners will be involved in the planning, execution and analysis of these experiments in order to insure that they are relevant and cost effective with respect to the various gas cooled reactor national programs. (author)

  10. Experimental platforms in support of the ASTRID program: existing and planned facilities - 15126

    International Nuclear Information System (INIS)

    Gastaldi, O.; Rodriguez, G.; Ayrault, L.; Collard, B.; Dumesnil, J.; Dujet, F.; Journeau, C.; Latge, C.; Sanseigne, E.; Serre, F.; Tkatschenko, I.; Willermoz, G.

    2015-01-01

    The sodium cooled fast reactors (SFR) French program currently focused on the design of the ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) reactor in different fields: energy conversion system, instrumentation for continuous monitoring, In Service Inspection and Repair, core design, fuel handling, thermo hydraulic, severe accidents, large flow electromagnetic pumps... Even if the French experimental prototype implies the development of innovative techniques, concepts and feedback of operations of SFRs are important, the new challenges coming from the objectives to meet GEN-IV requirements need some research and development. To achieve this goal, the generation four French SFR program includes the development of technological platforms with experimental facilities to develop and evaluate innovative options and also qualify some ASTRID specific components. The needs in terms of development, validation and qualification of techniques, components or systems to be used on ASTRID have been reviewed exhaustively in 2014. It allowed to consolidate or to precise the experimental purposes of the four CEA platforms regrouping technological facilities with different strategy of erection. PAPIRUS platform (largely already constructed) is dedicated to in-sodium experimental testing; GISEH platform (also largely already constructed) is devoted to water and air tests in support to hydraulic, thermal-hydraulic and fluid-structure interaction studies; CHEOPS platform (detailed studies and realization contract launched in 2014 aiming at commissioning and start up in 2018) deals with in sodium research and development and some qualifications requiring large scale; and last, PLINIUS-2 platform (commissioning and start up in 2019) concerns prototypic corium behavior studies in severe accident conditions and mitigation device qualification. This paper presents the four platforms and for each of them the experimental needs which are covered by their facilities

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

    Science.gov (United States)

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

    2018-05-01

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

  12. A Qualitative Study Investigating Facility Managers' Perceptions of the Classroom Learning Environment

    Science.gov (United States)

    Parr, Eric Shannon

    2017-01-01

    Facility managers have the challenge of adhering to community college policies and procedures while fulfilling requirements of administration, students, and teachers concerning specific needs of classroom aesthetics. The role of facility manager and how specific entities affect perceptions of the design and implementation of classroom aesthetics…

  13. Upper plenum break LOCA investigation in the ISB-VVER and PSB-VVER facilities

    Energy Technology Data Exchange (ETDEWEB)

    Blinkov, V. N.; Melikhov, O. I.; Lipatov, I. A.; Nikonov, S. M.; Dremin, G. I.; Galchanskaya, S. A.; Gashenko, M. P.; Rovnov, A. A.; Kapustin, A. V.; Elkin, I. V. [EREC, Moscow (Russian Federation)

    2003-07-01

    The capability to define the actual NPP transient/accident scenario depends to a great extent on facilities' scaling and reliability of the system thermalhydraulic codes which, in turn, are assessed against the experimental data taken in the same facilities. At the present time, it is received fact that the rigorous modeling of the cumulative set of all thermalhydraulic processes in the plant primary and secondary sides during accident is unfeasible. Therefore, the extrapolation of the facilities loops behavior to the actual systems constitutes a fundamental problem in this area. In the paper, some aspects for the problem have been discussed in the course of comparative analysis of the data derived from the 11 % upper plenum break LOCA tests performed in the PSB-VVER and ISB-VVER integral test facilities under the close scenarios. Both facilities, PSB-VVER and ISB-VVER, are modeled the same VVER-1000 reactor in different scales. The thermalhydraulic behavior of the primary systems in both facilities has been discussed in the paper, and shown to be similar. Also, the attention has been focused upon the discrepancies in the significant variables trends. The discrepancies are shown to be caused by influence of peculiarities of the facilities hardware and due to the scale factor. The scaling study is an important aspect of the thermalhydraulic codes verification procedure. Being qualified against the experimentally simulated accident sequence in two test facilities of different scales, the thermalhydraulic codes will be capable of evaluation of the prototype behavior to greater accuracy.

  14. Investigations on photoelectrochemical performance of boron doped ZnO nanorods synthesized by facile hydrothermal technique

    Science.gov (United States)

    Sharma, Akash; Chakraborty, Mohua; Thangavel, R.

    2018-05-01

    Undoped and 10% Boron (B)-doped Zinc Oxide nanorods (ZnO NRs) on Tin doped Indium Oxide (ITO) coated glass substrates were synthesized using facile sol-gel, spin coating and hydrothermal method. The impact of adding Boron on the structural, optical properties, surface morphology and photoelectrochemical (PEC) performances of the ZnO NRs have been investigated. The XRD pattern confirmed the formation of pure hexagonal phase with space group P63mc (186). The same can also be clearly observed form the FESEM images. The UV-Vis study shows the narrowing in band gap from 3.22 eV to 3.19 eV with incorporation of Boron in ZnO matrix. The B-doped ZnO NRs sample shows an enhanced photocurrent density of 1.31 mA/cm2 at 0.5 V (vs. Ag/AgCl), which is more than 171% enhancement compared to bare ZnO NRs (0.483 mA/cm2) in 0.1 M Na2SO4 aqueous solution. The results clearly indicates that the boron doped ZnO NRs can be used as an efficient photoelectrode material for photoelectrochemical cell.

  15. Reconnaissance hydrogeologic investigation of the Defense Waste Processing Facility and Vicinity, Savannah River Plant, South Carolina

    International Nuclear Information System (INIS)

    Dennehy, K.F.; Prowell, D.C.; McMahon, P.B.

    1989-01-01

    The purposes of this report are two-fold: (1) to define the hydrogeologic conditions in the vicinity of the defense waste processing facility (DWPF) and, (2) to evaluate the potential for movement of a concentrated salt-solution waste if released at or near the DWPF. These purposes were accomplished by assembling and evaluating existing hydrogeologic data; collecting additional geologic, hydrologic, and water-quality data; developing a local geologic framework; developing a conceptual model of the local ground-water flow system; and by performing laboratory experiments to determine the mobility of salt-solution waste in surface and near-surface sediments. Although the unconsolidated sediments are about 1000 ft thick in the study area, only the Tertiary age sediments, or upper 300 ft are discussed in this report. The top of the Ellenton Formation acts as the major confining unit between the overlying aquifers in Tertiary sediments and the underlying aquifers in Cretaceous sediments; therefore, the Ellenton Formation is the vertical limit of our hydrogeologic investigation. The majority of the hydrologic data for this study come from monitoring wells at the saltstone disposal site (SDS) in Z Area (fig. 3). No recent water-level data were collected in S Area owing to the removal of S Area monitoring wells prior to construction at the DWPF. 46 refs., 26 figs., 7 tabs

  16. Investigation and Development of Control Laws for the NASA Langley Research Center Cockpit Motion Facility

    Science.gov (United States)

    Coon, Craig R.; Cardullo, Frank M.; Zaychik, Kirill B.

    2014-01-01

    The ability to develop highly advanced simulators is a critical need that has the ability to significantly impact the aerospace industry. The aerospace industry is advancing at an ever increasing pace and flight simulators must match this development with ever increasing urgency. In order to address both current problems and potential advancements with flight simulator techniques, several aspects of current control law technology of the National Aeronautics and Space Administration (NASA) Langley Research Center's Cockpit Motion Facility (CMF) motion base simulator were examined. Preliminary investigation of linear models based upon hardware data were examined to ensure that the most accurate models are used. This research identified both system improvements in the bandwidth and more reliable linear models. Advancements in the compensator design were developed and verified through multiple techniques. The position error rate feedback, the acceleration feedback and the force feedback were all analyzed in the heave direction using the nonlinear model of the hardware. Improvements were made using the position error rate feedback technique. The acceleration feedback compensator also provided noteworthy improvement, while attempts at implementing a force feedback compensator proved unsuccessful.

  17. Computational investigation of reshock strength in hydrodynamic instability growth at the National Ignition Facility

    Science.gov (United States)

    Bender, Jason; Raman, Kumar; Huntington, Channing; Nagel, Sabrina; Morgan, Brandon; Prisbrey, Shon; MacLaren, Stephan

    2017-10-01

    Experiments at the National Ignition Facility (NIF) are studying Richtmyer-Meshkov and Rayleigh-Taylor hydrodynamic instabilities in multiply-shocked plasmas. Targets feature two different-density fluids with a multimode initial perturbation at the interface, which is struck by two X-ray-driven shock waves. Here we discuss computational hydrodynamics simulations investigating the effect of second-shock (``reshock'') strength on instability growth, and how these simulations are informing target design for the ongoing experimental campaign. A Reynolds-Averaged Navier Stokes (RANS) model was used to predict motion of the spike and bubble fronts and the mixing-layer width. In addition to reshock strength, the reshock ablator thickness and the total length of the target were varied; all three parameters were found to be important for target design, particularly for ameliorating undesirable reflected shocks. The RANS data are compared to theoretical models that predict multimode instability growth proportional to the shock-induced change in interface velocity, and to currently-available data from the NIF experiments. Work performed under the auspices of the U.S. D.O.E. by Lawrence Livermore National Laboratory under Contract No. DE-AC52-07NA27344. LLNL-ABS-734611.

  18. Facile synthesis and electron transport properties of NiO nanostructures investigated by scanning tunneling microscopy

    Directory of Open Access Journals (Sweden)

    Govind Mallick

    2017-08-01

    Full Text Available Due to their unique chemical, thermal, electronic and photonic properties, low -dimensional transition metal oxides, especially NiO, have attracted great deal of attention for potential applications in a wide range of technologies, such as, sensors, electrochromic coatings and self-healing materials. However, their synthesis involves multi-step complex procedures that in addition to being expensive, further introduce impurities. Here we present a low cost facile approach to synthesize uniform size NiO nanoparticles (NPs from hydrothermally grown Ni(OH2. Detailed transmission electron microscopic analysis reveal the average size of NiO NPs to be around 29 nm. The dimension of NiO NP is also corroborated by the small area scanning tunneling microscope (STM measurements. Further, we investigate electron transport characteristics of newly synthesized Ni(OH2 and NiO nanoparticles on p-type Si substrate using scanning tunneling microscopy. The conductivity of Ni(OH2 and NiO are determined to be 1.46x10-3 S/cm and 2.37x10-5 S/cm, respectively. The NiO NPs exhibit a lower voltage window (∼0.7 V electron tunneling than the parent Ni(OH2.

  19. Report of Animal Investigation Program activities for the Baneberry Event

    International Nuclear Information System (INIS)

    Smith, D.D.; Black, S.C.; Giles, K.R.; Moghissi, A.A.

    1975-11-01

    On December 18, 1970, an underground nuclear test, conducted at the Nevada Test Site, released radioactive materials into the atmosphere with resultant on-site and off-site contamination. The Animal Investigation Program of the National Environmental Research Center, Las Vegas developed studies to document the distribution of fission and activation products in the tissue of domestic and wild animals residing within contaminated areas on and surrounding the Nevada Test Site. A study of radioiodine secretion in milk from cows at the experimental dairy farm, including urine and fecal excretion from four of them, was started about 24 hours after the venting. A grazing intake study, which utilized fistulated steers, was also carried out. The analytical data collected from these studies are presented in this report

  20. RCRA Facility investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1991-09-01

    This report describes the borehole geophysical logging performed at selected monitoring wells at waste area grouping (WAG) 6 of Oak Ridge National Laboratory in support of the WAG 6 Resource Conservation and Recovery Act Facility Investigation (RFI). It identifies the locations and describes the methods, equipment used in the effort, and the results of the activity. The actual logs for each well logged are presented in Attachment 1 through 4 of the TM. Attachment 5 provide logging contractor service literature and Attachment 6 is the Oak Ridge National Laboratory (ORNL) Procedure for Control of a Nuclear Source Utilized in Geophysical logging. The primary objectives of the borehole geophysical logging program were to (1) identify water-bearing fractured bedrock zones to determine the placement of the screen and sealed intervals for subsequent installation, and (2) further characterize local bedrock geology and hydrogeology and gain insight about the deeper component of the shallow bedrock aquifer flow system. A secondary objective was to provide stratigraphic and structural correlations with existing logs for Hydraulic Head Monitoring Station (HHMS) wells, which display evidence of faulting

  1. Energy management: a program of energy conservation for the community college facility. [Handbook

    Energy Technology Data Exchange (ETDEWEB)

    Various Authors

    1978-01-01

    This handbook developes helps for assessing and improving the energy efficiency of the community-college facility. The TEEM approach (Total Educational Energy Management) is a labor-intensive approach which requires the commitment and participation of all segments of the college community. The TEEM program presented here defines a series of tasks selected, ordered, and implemented in such a way as to achieve two basic objectives: (1) reducing campus energy requirements, and (2) meeting those reduced energy requirements more efficiently without adversely affecting the quality of educational programs. This guide to large-scale energy conservation on college campuses includes step-by-step procedures for establishing a program task force, defining specific tasks, and assigning responsibilities. Action plans are developed, energy consumption monitored, goals set, and conservation measures implemented. A series of appendices provides more detailed information, charts, and worksheets related to all aspects of energy use. The TEEM program provides the basic structure for achieving a significant reduction in campus energy costs.

  2. Physics Division Argonne National Laboratory description of the programs and facilities.

    Energy Technology Data Exchange (ETDEWEB)

    Thayer, K.J. [ed.

    1999-05-24

    The ANL Physics Division traces its roots to nuclear physics research at the University of Chicago around the time of the second world war. Following the move from the University of Chicago out to the present Argonne site and the formation of Argonne National Laboratory: the Physics Division has had a tradition of research into fundamental aspects of nuclear and atomic physics. Initially, the emphasis was on areas such as neutron physics, mass spectrometry, and theoretical studies of the nuclear shell model. Maria Goeppert Maier was an employee in the Physics Division during the time she did her Nobel-Prize-winning work on the nuclear shell model. These interests diversified and at the present time the research addresses a wide range of current problems in nuclear and atomic physics. The major emphasis of the current experimental nuclear physics research is in heavy-ion physics, centered around the ATLAS facility (Argonne Tandem-Linac Accelerator System) with its new injector providing intense, energetic ion beams over the fill mass range up to uranium. ATLAS is a designated National User Facility and is based on superconducting radio-frequency technology developed in the Physics Division. A small program continues in accelerator development. In addition, the Division has a strong program in medium-energy nuclear physics carried out at a variety of major national and international facilities. The nuclear theory research in the Division spans a wide range of interests including nuclear dynamics with subnucleonic degrees of freedom, dynamics of many-nucleon systems, nuclear structure, and heavy-ion interactions. This research makes contact with experimental research programs in intermediate-energy and heavy-ion physics, both within the Division and on the national and international scale. The Physics Division traditionally has strong connections with the nation's universities. We have many visiting faculty members and we encourage students to participate in our

  3. Investigation of primary-to-secondary leakage accident on the PSB-VVER integral test facility

    International Nuclear Information System (INIS)

    Lipatov, I.A.; Dremin, G.I.; Galtchanskaya, S.A.; Chmal, I.I.; Moloshnikov, A.S.; Gorbunov, Y.S.; Antonova, A.I.; Elkin, I.V.

    2001-01-01

    The full text follows. The paper presents the main results from the test on primary-to-secondary leakage of 100 mm in equivalent diameter. The test was performed on the PSB-VVER integral test facility. PSB-VVER is a 4-loops scaled down model of primary system of NPP with VVER-1000 Russian type reactor. Volume - power scale is about 1/300 while elevation scale is 1/1. All components of the primary system of the reference NPP are modeled on PSB-VVER. Both passive (accumulators) and active (high and low pressure) ECCSs, pressurizer spray and relief circuits, feed water system and atmospheric dumping system (ADS) as well as the primary circuit gas remove emergency system are also simulated. The primary-to-secondary leakage was simulated using an external break line which connects the upper part of the hot header to SG water volume. The break line included a break nozzle (a cylindrical channel d = 5.8 mm, l/d = 10 with sharp inlet edge), quick-acting valve and two-phase mass flow rate measurement system. In addition loss of off-site power at the moment when a scram-signal is generated was assumed in the experiment. Thus the accident is to be considered as a beyond-design-basic one. The loss of off-site power results in the following: -main circulation pump shutdown; -pressurizer heaters switching off; -HPIS water cooling flow rate and number of points of water injection are reduced The study focuses on the adequacy of the associated accident management (AM) procedure developed by EDO ''GIDROPRESS'' as a General Designer of VVER-type reactors. The AM-procedure was adopted to the PSB-VVER test facility conditions using CATHARE (France) and DINAMIKA (Russia) codes analysis. The AM-procedure in PSB-VVER is as follows: after about 30 min of the onset of the accident, when the accident type and the localization of the SG affected become evident for the operator, he closes all the main steam isolation valves, inhibits the ADS actuation in the affected SG and begins to remove

  4. Investigation of primary-to-secondary leakage accident on the PSB-VVER integral test facility

    Energy Technology Data Exchange (ETDEWEB)

    Lipatov, I.A.; Dremin, G.I.; Galtchanskaya, S.A.; Chmal, I.I.; Moloshnikov, A.S.; Gorbunov, Y.S.; Antonova, A.I. [Electrogorsk Research and Engineering Center, EREC, Moscow (Russian Federation); Elkin, I.V. [RRC ' ' Kurchatov Institute, Moscow (Russian Federation)

    2001-07-01

    The full text follows. The paper presents the main results from the test on primary-to-secondary leakage of 100 mm in equivalent diameter. The test was performed on the PSB-VVER integral test facility. PSB-VVER is a 4-loops scaled down model of primary system of NPP with VVER-1000 Russian type reactor. Volume - power scale is about 1/300 while elevation scale is 1/1. All components of the primary system of the reference NPP are modeled on PSB-VVER. Both passive (accumulators) and active (high and low pressure) ECCSs, pressurizer spray and relief circuits, feed water system and atmospheric dumping system (ADS) as well as the primary circuit gas remove emergency system are also simulated. The primary-to-secondary leakage was simulated using an external break line which connects the upper part of the hot header to SG water volume. The break line included a break nozzle (a cylindrical channel d = 5.8 mm, l/d = 10 with sharp inlet edge), quick-acting valve and two-phase mass flow rate measurement system. In addition loss of off-site power at the moment when a scram-signal is generated was assumed in the experiment. Thus the accident is to be considered as a beyond-design-basic one. The loss of off-site power results in the following: -main circulation pump shutdown; -pressurizer heaters switching off; -HPIS water cooling flow rate and number of points of water injection are reduced The study focuses on the adequacy of the associated accident management (AM) procedure developed by EDO ''GIDROPRESS'' as a General Designer of VVER-type reactors. The AM-procedure was adopted to the PSB-VVER test facility conditions using CATHARE (France) and DINAMIKA (Russia) codes analysis. The AM-procedure in PSB-VVER is as follows: after about 30 min of the onset of the accident, when the accident type and the localization of the SG affected become evident for the operator, he closes all the main steam isolation valves, inhibits the ADS actuation in the affected SG

  5. 40 CFR 122.24 - Concentrated aquatic animal production facilities (applicable to State NPDES programs, see § 123...

    Science.gov (United States)

    2010-07-01

    ... NATIONAL POLLUTANT DISCHARGE ELIMINATION SYSTEM Permit Application and Special NPDES Program Requirements... 40 Protection of Environment 21 2010-07-01 2010-07-01 false Concentrated aquatic animal production facilities (applicable to State NPDES programs, see § 123.25). 122.24 Section 122.24 Protection of...

  6. Qualification requirements and training programs for nonreactor nuclear facility personnel in the Operations Division of the Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Preston, E.L.; Culbert, W.H.; Baldwin, M.E.; McCormack, K.E.; Rivera, A.L.; Setaro, J.A.

    1985-11-01

    This document describes the program for training, retraining, and qualification of nonreactor nuclear operators in the Operations Division of the Oak Ridge National Laboratory. The objective of the program is to provide the Operators and Supervisors of nuclear facilities the knowledge and skills needed to perform assigned duties in a safe and efficient manner and to comply with US Department of Energy Order 5480.1A Chapter V. This order requires DOE nuclear facilities to maintain formal training programs for their operating staff and documentation of that training.

  7. Qualification requirements and training programs for nonreactor nuclear facility personnel in the Operations Division of the Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Preston, E.L.; Culbert, W.H.; Baldwin, M.E.; McCormack, K.E.; Rivera, A.L.; Setaro, J.A.

    1985-11-01

    This document describes the program for training, retraining, and qualification of nonreactor nuclear operators in the Operations Division of the Oak Ridge National Laboratory. The objective of the program is to provide the Operators and Supervisors of nuclear facilities the knowledge and skills needed to perform assigned duties in a safe and efficient manner and to comply with US Department of Energy Order 5480.1A Chapter V. This order requires DOE nuclear facilities to maintain formal training programs for their operating staff and documentation of that training

  8. Accounting for variations in ART program sustainability outcomes in health facilities in Uganda: a comparative case study analysis.

    Science.gov (United States)

    Zakumumpa, Henry; Bennett, Sara; Ssengooba, Freddie

    2016-10-18

    Uganda implemented a national ART scale-up program at public and private health facilities between 2004 and 2009. Little is known about how and why some health facilities have sustained ART programs and why others have not sustained these interventions. The objective of the study was to identify facilitators and barriers to the long-term sustainability of ART programs at six health facilities in Uganda which received donor support to commence ART between 2004 and 2009. A case-study approach was adopted. Six health facilities were purposively selected for in-depth study from a national sample of 195 health facilities across Uganda which participated in an earlier study phase. The six health facilities were placed in three categories of sustainability; High Sustainers (2), Low Sustainers (2) and Non- Sustainers (2). Semi-structured interviews with ART Clinic managers (N = 18) were conducted. Questionnaire data were analyzed (N = 12). Document review augmented respondent data. Based on the data generated, across-case comparative analyses were performed. Data were collected between February and June 2015. Several distinguishing features were found between High Sustainers, and Low and Non-Sustainers' ART program characteristics. High Sustainers had larger ART programs with higher staffing and patient volumes, a broader 'menu' of ART services and more stable program leadership compared to the other cases. High Sustainers associated sustained ART programs with multiple funding streams, robust ART program evaluation systems and having internal and external program champions. Low and Non Sustainers reported similar barriers of shortage and attrition of ART-proficient staff, low capacity for ART program reporting, irregular and insufficient supply of ARV drugs and a lack of alignment between ART scale-up and their for-profit orientation in three of the cases. We found that ART program sustainability was embedded in a complex system involving dynamic interactions

  9. PWM CONTROLLER'S MODELS FOR INVESTIGATION ACS IN SPICEFAMILY ECAD PROGRAMS

    Directory of Open Access Journals (Sweden)

    O. V. VASYLENKO

    2018-05-01

    Full Text Available Purpose. To improve simulation and design of Automatic Control Systems in the SPICE-compatible programs and to obtain separate economic and universal macromodels of PWM controller. Development of an PWM controller economical macromodel for the study of automatic control systems (ACS in computer-aided design (ECAD  programs, which does not generate algorithmic failures in comparison with the existing models of PWM. Findings. Analysis of SPICE-family applications’ mathematical basis allowed to classifying existing models of PWM-controllers, defining their suitability for ACS simulation. The criteria for the synthesis of new models have been defined. For the SPICE 3G algorithms, the Switch and Averaged models based on behavioral elements has been developed. Universal and economical PWM controller macromodel based on the simple algorithm for determining the output signal with minimum numbers of input parameters has been designed. For the Automated Measuring magnetic susceptibility System, the macromodel of quasi-PWM signal generator have been designed, which is used in the compensation subsystem. This model is different from the existing ones: it synthesizes the staircase output signal instead the pulse one, thus, there is direct control of the amplitude of the output signal, which is taken averaged. The adequacy of the models is confirmed as comparison of the simulation results during investigations of the model already existing in the SPICE program, as well as the results of experiments with real ACS. The modeling of the PWM controller was carried out on the basis of behavioral elements from the ECAD library, simulation (solution of algebra-differential equations systems with programming elements is based on SPICE algorithms. The object of the study was the simulation process of ACS with the pulse-width principle of adjusting the output value. The subject of the research are the models of PWM controllers. Originality. The new macromodel of PWM

  10. An experimental investigation of 1% SBLOCA on PSB-VVER test facility

    Energy Technology Data Exchange (ETDEWEB)

    Lipatov, I.A.; Dremin, G.I.; Galtchanskaia, S.A.; Gorbunov, Yu.S. [Electrogorsk Research and Engineering Center, EREC, Electrogorsk (Russian Federation); Elkin, I.V. [Russian Research Centre Kurchatov Inst., Moscow (Russian Federation)

    2001-07-01

    The paper presents the results of the three tests carried out in the PSB-VVER large-scale integral test facility. The PSB-VVER test facility is a four loop, full pressure scaled down model bearing structural similarities to the primary system of the NRP with VVER-1000 Russian design reactor. Volume-power scale is 1/300 while elevation scale is 1/1. (orig.)

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

    Science.gov (United States)

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

    2006-07-01

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

  12. Investigating Students' Beliefs about Arabic Language Programs at Kuwait University

    Science.gov (United States)

    Al-Shaye, Shaye S.

    2009-01-01

    The current study attempted to identify students' of Arabic programs beliefs about their chosen programs. To achieve this purpose, a survey was developed to collect the data from randomly selected students in liberal-arts and education-based programs at Kuwait University. The results showed that students were statistically differentiated as a…

  13. SITE: a methodology for assessment of energy facility siting patterns. Regional studies program

    International Nuclear Information System (INIS)

    Frigerio, N.A.; Habegger, L.J.; King, R.F.; Hoover, L.J.; Clark, N.A.; Cobian, J.M.

    1975-08-01

    The timely development of the nation's energy production capacity in a manner that minimizes potential adverse local and regional impacts associated with energy facilities requires the use of sophisticated techniques for evaluation of siting alternatives and fuel cycle options. This report is a documentation of the computerized SITE methodology that has been developed for evaluating health, environmental, and socioeconomic impacts related to utilization of alternate sites for energy production within a region of interest. The cost, impact, and attribute vectors, which are generated and displayed on density maps, can be used in a multiparameter overlay process to identify preferable siting areas. The assessment of clustered facilities in energy centers is also possible within the SITE analysis framework. An application of the SITE methodology to Northern Illinois is presented. Also included is a description of the ongoing extension of SITE for the accumulative evaluation of alternative regional energy siting patterns and fuel cycle options. An appendix provides documentation and user information for the SITE computer program

  14. IOTA (Integrable Optics Test Accelerator): facility and experimental beam physics program

    Science.gov (United States)

    Antipov, S.; Broemmelsiek, D.; Bruhwiler, D.; Edstrom, D.; Harms, E.; Lebedev, V.; Leibfritz, J.; Nagaitsev, S.; Park, C. S.; Piekarz, H.; Piot, P.; Prebys, E.; Romanov, A.; Ruan, J.; Sen, T.; Stancari, G.; Thangaraj, C.; Thurman-Keup, R.; Valishev, A.; Shiltsev, V.

    2017-03-01

    The Integrable Optics Test Accelerator (IOTA) is a storage ring for advanced beam physics research currently being built and commissioned at Fermilab. It will operate with protons and electrons using injectors with momenta of 70 and 150 MeV/c, respectively. The research program includes the study of nonlinear focusing integrable optical beam lattices based on special magnets and electron lenses, beam dynamics of space-charge effects and their compensation, optical stochastic cooling, and several other experiments. In this article, we present the design and main parameters of the facility, outline progress to date and provide the timeline of the construction, commissioning and research. The physical principles, design, and hardware implementation plans for the major IOTA experiments are also discussed.

  15. IOTA (Integrable Optics Test Accelerator): Facility and experimental beam physics program

    International Nuclear Information System (INIS)

    Antipov, Sergei; Broemmelsiek, Daniel; Bruhwiler, David; Edstrom, Dean; Harms, Elvin

    2017-01-01

    The Integrable Optics Test Accelerator (IOTA) is a storage ring for advanced beam physics research currently being built and commissioned at Fermilab. It will operate with protons and electrons using injectors with momenta of 70 and 150 MeV/c, respectively. The research program includes the study of nonlinear focusing integrable optical beam lattices based on special magnets and electron lenses, beam dynamics of space-charge effects and their compensation, optical stochastic cooling, and several other experiments. In this article, we present the design and main parameters of the facility, outline progress to date and provide the timeline of the construction, commissioning and research. Finally, the physical principles, design, and hardware implementation plans for the major IOTA experiments are also discussed.

  16. A flexible testing facility for high-power targets (Tiara FP7 program)

    CERN Document Server

    Fusco, Y.; Samec, K.; Kadi, Y.

    2014-01-01

    Building on recent experience in the field of applied physics, TIARA Work package n° 9 focuses on target applications for accelerators in Europe. A roadmap for target development has been derived from major achievements in the EU-FP6 and EU-FP7 programs such as the MEGAPIE and EURISOL experiments. The TIARA management board concluded that a worthwhile continuation of such projects would be in the development of a flexible material irradiation facility easily transportable and which could be installed in different laboratories. The power is limited to 100 kW in a very compact arrangement so as to obtain the best neutron economy from a moderate beam power which is more likely to be found in laboratories across Europe. The challenges posed by such a compact design and accompanying calculations are presented in the current work.

  17. Environmental monitoring program of the uranium enrichment facility Almirante Alvaro Alberto

    International Nuclear Information System (INIS)

    Hiromoto, G.; Jacomino, V.M.F.; Venturini, L.; Moreira, S.R.D.; Gordon, A.M.P.L.; Duarte, C.L.; Pocequilo, B.R.S.; Mazzilli, B.P.

    1988-11-01

    In this report, the Environmental Monitoring Program of the Uranium Enrichment Facility Almirante Alvaro Alberto is outlined and the results obtained during the preoperational period are presented. Information concerning the population distribution, the use of water and land, the local agricultural production and the local meteorology are also available. In order to evaluate the levels of the background radiation, sample of water, air and biological and terrestrial indicators were analysed. Measurements were performed of natural gamma emitters concentrations levels and of uranium in air, surface water, precipitation, groundwater, river sediment, soil, grass, vegetation and various foodstuffs. For direct measurement of background radiation levels a solid state dosimeter network was used. Results are also presented for the analysis of non radioactive pollutants in the water samples and for the particles and gaseous fluorides concentration in the atmosphere. (author) [pt

  18. SP-100 Program: space reactor system and subsystem investigations

    International Nuclear Information System (INIS)

    Harty, R.B.

    1983-01-01

    For a space reactor power system, a comprehensive safety program will be required to assure that no undue risk is present. This report summarizes the nuclear safety review/approval process that will be required for a space reactor system. The documentation requirements are presented along with a summary of the required contents of key documents. Finally, the aerospace safety program conducted for the SNAP-10A reactor system is summarized. The results of this program are presented to show the type of program that can be expected and to provide information that could be usable in future programs

  19. Data gathering in support of phase O program for waste heat utilization from nuclear enrichment facilities, Ohio

    International Nuclear Information System (INIS)

    1978-01-01

    The gathering of demographic, community development, and economic data for the region impacted by the Pikeville (Ohio) Nuclear Enrichment Facility is described. These data are to be used for establishing possible community uses, e.g., space heating, domestic water heating, and industrial uses, of waste heat from the facility. It was concluded that although the economic feasibility of such waste heat utilization remains to be proven, the community would cooperate in a feasibility demonstration program

  20. Investigation system for the study of computer programs structure

    International Nuclear Information System (INIS)

    Aboulker, Francis

    1968-10-01

    This document describes a set of three programs allowing to obtain the symbolic list of a machine loaded program with comments for each reconstitution. These programs are as follows: - TRAD makes the dump of the program to be rebuilt with a decomposition of each instruction when possible; - RETAB uses TRAD's result and data cards to implement the information (symbolic names) and comments. Several runs can be done as the appropriate elements are progressively determined. - TASS uses RETAB results to eliminate the duplicate information and to implement the definitive information. It establishes the reference table of symbols. These programs are written in META-SYMBOL language. They are self-loadable and translatable. They do not use programmed operators. They are defined to process the SYMBOL or META-SYMBOL programs of the 90-40 machine but their principles remain global and can apply to any machine [fr

  1. Implementation of Best Practices in Obesity Prevention in Child Care Facilities: The Arizona Empower Program, 2013-2015.

    Science.gov (United States)

    Papa, Jillian; Agostinelli, Joan; Rodriguez, Gertrudes; Robinson, Deborah

    2017-09-07

    Obesity is a major health concern in every US age group. Approximately one in 4 children in Arizona's Special Supplemental Nutrition Program for Women, Infants, and Children is overweight or obese. The Arizona Department of Health Services developed the Empower program to promote healthy environments in licensed child care facilities. The program consists of 10 standards, including one standard for each of these 5 areas: physical activity and screen time, breastfeeding, fruit juice and water, family-style meals, and staff training. The objective of this evaluation was to determine the level of implementation of these 5 Empower standards. A self-assessment survey was completed from July 2013 through June 2015 by 1,850 facilities to evaluate the level of implementation of 5 Empower standards. We calculated the percentage of facilities that reported the degree to which they implemented each standard and identified common themes in comments recorded in the survey. All facilities reported either full or partial implementation of the 5 standards. Of 1,678 facilities, 21.7% (n = 364) reported full implementation of all standards, and 78.3% (n = 1,314) reported at least partial implementation. Staff training, which has only one component, had the highest level of implementation: 77.4% (n = 1,299) reported full implementation. Only 44.0% (n = 738) reported full implementation of the standard on a breastfeeding-friendly environment. Arizona child care facilities have begun to implement the Empower program, but facilities will need more education, technical assistance, and support in some areas to fully implement the program.

  2. Chemical inventory control program for mixed and hazardous waste facilities at SRS

    International Nuclear Information System (INIS)

    Ades, M.J.; Vincent, A.M. III.

    1997-01-01

    Mixed Waste (MW) and Hazardous Waste (HW) are being stored at the Savannah River Site (SRS) pending onsite and/or offsite treatment and disposal. The inventory control for these wastes has recently been brought under Technical Safety Requirements (TSR) in accordance with DOE Order 5480.22. With the TSRs was the question of the degree of rigor with which the inventory is to be tracked, considering that the variety of chemicals present, or that could be present, numbers in the hundreds. This paper describes the graded approach program to track Solid Waste (SW) inventories relative to TSRs. The approach uses a ratio of the maximum anticipated chemical inventory to the permissible inventory in accordance with Emergency Response Planning Guideline (ERPG) limits for on- and off-site receptors. A specific threshold ratio can then be determined. The chemicals above this threshold ratio are to be included in the chemical inventory control program. The chemicals that fall below the threshold ratio are managed in accordance with existing practice per State and RCRA hazardous materials requirements. Additionally, the facilities are managed in accordance with process safety management principles, specifically using process hazards analyses, which provides safety assurance for even the small quantities that may be excluded from the formal inventory control program. The method yields a practical approach to chemical inventory control, while maintaining appropriate chemical safety margins. The resulting number of specific chemicals that require inclusion in a rigorous inventory control program is greatly reduced by about 80%, thereby resulting in significant reduction in chemical data management while preserving appropriate safety margins

  3. Using classification tree modelling to investigate drug prescription practices at health facilities in rural Tanzania

    Directory of Open Access Journals (Sweden)

    Kajungu Dan K

    2012-09-01

    Full Text Available Abstract Background Drug prescription practices depend on several factors related to the patient, health worker and health facilities. A better understanding of the factors influencing prescription patterns is essential to develop strategies to mitigate the negative consequences associated with poor practices in both the public and private sectors. Methods A cross-sectional study was conducted in rural Tanzania among patients attending health facilities, and health workers. Patients, health workers and health facilities-related factors with the potential to influence drug prescription patterns were used to build a model of key predictors. Standard data mining methodology of classification tree analysis was used to define the importance of the different factors on prescription patterns. Results This analysis included 1,470 patients and 71 health workers practicing in 30 health facilities. Patients were mostly treated in dispensaries. Twenty two variables were used to construct two classification tree models: one for polypharmacy (prescription of ≥3 drugs on a single clinic visit and one for co-prescription of artemether-lumefantrine (AL with antibiotics. The most important predictor of polypharmacy was the diagnosis of several illnesses. Polypharmacy was also associated with little or no supervision of the health workers, administration of AL and private facilities. Co-prescription of AL with antibiotics was more frequent in children under five years of age and the other important predictors were transmission season, mode of diagnosis and the location of the health facility. Conclusion Standard data mining methodology is an easy-to-implement analytical approach that can be useful for decision-making. Polypharmacy is mainly due to the diagnosis of multiple illnesses.

  4. RCRA Facility Investigation/Remedial Investigation Report for Gunsite 720 Rubble Pit Unit (631-16G) - March 1996

    Energy Technology Data Exchange (ETDEWEB)

    Palmer, E. [Westinghouse Savannah River Company, AIKEN, SC (United States)

    1996-03-01

    Gunsite 720 Rubble Pit Unit is located on the west side of SRS. In the early to mid 1980`s, while work was being performed in this area, nine empty, partially buried drums, labeled `du Pont Freon 11`, were found. As a result, Gunsite 720 became one of the original waste units specified in the SRS RCRA Facility Assessment (RFA). The drums were excavated on July 30, 1987 and placed on a pallet at the unit. Both the drums and pallet were removed and disposed of in October 1989. The area around the drums was screened during the excavation and the liquid (rainwater) that collected in the excavated drums was sampled prior to disposal. No evidence of hazardous materials was found. Based on the review of the analytical data and screening techniques used to evaluate all the chemicals of potential concern at Gunsite 720 Rubble Pit Unit, it is recommended that no further remedial action be performed at this unit.

  5. RCRA Facility Investigation/Remedial Investigation Report for Gunsite 720 Rubble Pit Unit (631-16G) - March 1996

    International Nuclear Information System (INIS)

    Palmer, E.

    1996-03-01

    Gunsite 720 Rubble Pit Unit is located on the west side of SRS. In the early to mid 1980's, while work was being performed in this area, nine empty, partially buried drums, labeled 'du Pont Freon 11', were found. As a result, Gunsite 720 became one of the original waste units specified in the SRS RCRA Facility Assessment (RFA). The drums were excavated on July 30, 1987 and placed on a pallet at the unit. Both the drums and pallet were removed and disposed of in October 1989. The area around the drums was screened during the excavation and the liquid (rainwater) that collected in the excavated drums was sampled prior to disposal. No evidence of hazardous materials was found. Based on the review of the analytical data and screening techniques used to evaluate all the chemicals of potential concern at Gunsite 720 Rubble Pit Unit, it is recommended that no further remedial action be performed at this unit

  6. Borehole Calibration Facilities to Support Gamma Logging for Hanford Subsurface Investigation and Contaminant Monitoring - 13516

    International Nuclear Information System (INIS)

    McCain, R.G.; Henwood, P.D.; Pope, A.D.; Pearson, A.W.

    2013-01-01

    Repeated gamma logging in cased holes represents a cost-effective means to monitor gamma-emitting contamination in the deep vadose zone over time. Careful calibration and standardization of gamma log results are required to track changes and to compare results over time from different detectors and logging systems. This paper provides a summary description of Hanford facilities currently available for calibration of logging equipment. Ideally, all logging organizations conducting borehole gamma measurements at the Hanford Site will take advantage of these facilities to produce standardized and comparable results. (authors)

  7. Borehole Calibration Facilities to Support Gamma Logging for Hanford Subsurface Investigation and Contaminant Monitoring - 13516

    Energy Technology Data Exchange (ETDEWEB)

    McCain, R.G.; Henwood, P.D.; Pope, A.D.; Pearson, A.W. [S M Stoller Corporation, 2439 Robertson Drive, Richland, WA 99354 (United States)

    2013-07-01

    Repeated gamma logging in cased holes represents a cost-effective means to monitor gamma-emitting contamination in the deep vadose zone over time. Careful calibration and standardization of gamma log results are required to track changes and to compare results over time from different detectors and logging systems. This paper provides a summary description of Hanford facilities currently available for calibration of logging equipment. Ideally, all logging organizations conducting borehole gamma measurements at the Hanford Site will take advantage of these facilities to produce standardized and comparable results. (authors)

  8. Results of the F/H Effluent Treatment Facility biological monitoring program, July 1987--July 1991

    International Nuclear Information System (INIS)

    Specht, W.L.

    1992-07-01

    As required by the South Carolina Department of Health and Environmental Control (SCDHEC) under NPDES Permit SCO000175, biological monitoring was conducted in Upper Three Runs Creek to determine if discharges from the F/H Effluent Treatment Facility have adversely impacted the biotic community of the receiving stream. Data included in this summary report encompass July 1987 through July 1991. As originally designed, the F/H ETF was not expected to remove all of the mercury from the wastewater; therefore, SCDHEC specified that studies be conducted to determine if mercury was bioaccumulating in aquatic biota. Subsequent to approval of the biological monitoring program, an ion exchange column was added to the F/H ETF specifically to remove mercury, which eliminated mercury from the F/H ETF effluent. The results of the biological monitoring program indicate that at the present rate of discharge, the F/H ETF effluent has not adversely affected the receiving stream with respect to any of the parameters that were measured. The effluent is not toxic at the in-stream waste concentration and there is no evidence of mercury bioaccumulation

  9. Fuzzy linear programming based optimal fuel scheduling incorporating blending/transloading facilities

    Energy Technology Data Exchange (ETDEWEB)

    Djukanovic, M.; Babic, B.; Milosevic, B. [Electrical Engineering Inst. Nikola Tesla, Belgrade (Yugoslavia); Sobajic, D.J. [EPRI, Palo Alto, CA (United States). Power System Control; Pao, Y.H. [Case Western Reserve Univ., Cleveland, OH (United States)]|[AI WARE, Inc., Cleveland, OH (United States)

    1996-05-01

    In this paper the blending/transloading facilities are modeled using an interactive fuzzy linear programming (FLP), in order to allow the decision-maker to solve the problem of uncertainty of input information within the fuel scheduling optimization. An interactive decision-making process is formulated in which decision-maker can learn to recognize good solutions by considering all possibilities of fuzziness. The application of the fuzzy formulation is accompanied by a careful examination of the definition of fuzziness, appropriateness of the membership function and interpretation of results. The proposed concept provides a decision support system with integration-oriented features, whereby the decision-maker can learn to recognize the relative importance of factors in the specific domain of optimal fuel scheduling (OFS) problem. The formulation of a fuzzy linear programming problem to obtain a reasonable nonfuzzy solution under consideration of the ambiguity of parameters, represented by fuzzy numbers, is introduced. An additional advantage of the FLP formulation is its ability to deal with multi-objective problems.

  10. Investigating the Influence of Various Stormwater Runoff Control Facilities on Runoff Control Efficiency in a Small Catchment Area

    Directory of Open Access Journals (Sweden)

    Rei Itsukushima

    2018-02-01

    Full Text Available Urbanization causes an increase in the flood discharge because of the infiltration capacity. Furthermore, extreme precipitation events have been an increasing concern for many regions worldwide. This study aimed to investigate the influence of different outflow control facilities on runoff reduction in a small watershed. We focused on the soil-improvement technology and rainwater tanks as outflow control facilities and conducted a runoff calculation using a rainfall event of a magnitude that is likely to occur once in a hundred years. The calculation showed that the soil-improvement technology reduced runoff during long-term continuous rainfall, whereas in a concentrated short-term rainfall event, a significant difference in the runoff reduction effect between rainfall tanks of various volumes was observed. Since effective countermeasures for runoff reduction differ depending on the rainfall distribution pattern, we suggested both facilities for storing initial rainfall and initiating countermeasures for penetration improvement over the long term.

  11. Experimental Investigation In The PANDA Facility Of The Impact Of A Hydrogen Release On Passive Containment Cooling Systems

    Energy Technology Data Exchange (ETDEWEB)

    Auban, O.; Paladino, D.; Candreia, P.; Huggenberger, M.; Strassberger, H.J

    2003-03-01

    The large-scale, thermal-hydraulics PANDA facility has been used in the past for investigating passive decay-heat removal systems and related containment phenomena for a number of next-generation Light Water Reactors. Passive Containment Condenser (PCC) systems operate by transferring heat via steam condensation from inside the containment to outside, and serve to mitigate pressure build-up in the event of steam discharge from the primary circuit. Five new integral tests have recently been performed in the context of the 5th European Framework Program project TEMPEST. One main objective was to assess the influence of a light gas (hydrogen) on the performance of the Passive Containment Cooling System (PCCS). Hydrogen release in the case of a severe accident is simulated in PANDA by injecting helium with steam into the Drywell. In addition, the impact of a new accident-mitigating design feature, the Drywell Gas Re-Circulation System (DGRS), on the long-term containment behaviour was tested. Another important objective was also to provide relevant data for the validation of modern 3/4 mainly Computational Fluid Dynamics (CFD) 3/4 codes. The paper reports main observations from two of these new integral tests in which standard PANDA instrumentation has provided important data concerning system response when helium is released in the course of the transient. The results show that some important stratification phenomena have occurred, as a result of the buoyant flow generated by the helium injection. The resulting temperature and concentration measurements show how helium is being distributed in the Drywell (DW) volume during the helium injection phase, and how helium is retained or vented out of these vessels once the injection stops. The paper includes some discussion concerning the influence of gas mixing and stratification and the effect of the DGRS on PCC performance and system pressure build-up. (author)

  12. How to Investigate Drug Use in Health Facilities. Selected Drug Use ...

    African Journals Online (AJOL)

    This short WHO manual outlines methods for evaluating drug use indicators in health facilities. The broad areas of ... Washington: American Psychiatric Press, Inc. 1991. ISBN 0-88048-114-5. This book is ... discussion of different symptom categories using the DSM. (Diagnostic Statistical Manual) as a base. The definition of.

  13. Experimental data from a full-scale facility investigating radiant and convective terminals

    DEFF Research Database (Denmark)

    Le Dreau, Jerome; Heiselberg, Per; Jensen, Rasmus Lund

    The objective of this technical report is to provide information on the accuracy of the experiments performed in “the Cube” (part I, II and III). Moreover, this report lists the experimental data, which have been monitored in the test facility (part IV). These data are available online and can be...

  14. An Investigation of the Effects of a Facility Dog on Student Learning and the Learning Environment

    Science.gov (United States)

    Bradley, Jordana

    2013-01-01

    According to No Child Left Behind, teachers must consider alternative teaching strategies to improve student achievement. The use of a facility dog as an instructional enhancement is an innovative teaching approach that deserves further research. The theoretical framework for the study was human-animal bond theory, which postulates that…

  15. Horonobe Underground Research Laboratory project. Plans of investigations during shaft and drift excavation (Construction of underground facilities: Phase II)

    International Nuclear Information System (INIS)

    2005-06-01

    Horonobe Underground Research Laboratory Project is planned for over 20 years to establish the scientific and technical basis for the underground disposal of high-level radioactive wastes in Japan. The investigations are conducted by JNC in three phases, from the surface (Phase I), during the construction of the underground facilities (Phase II), and using the facilities (Phase III). This report concerns the investigation plans for Phase II. During excavation of shafts and drifts, detailed geological and borehole investigation will be conducted and the geological model constructed in Phase I is evaluated and revised by newly acquired data of geophysical and geological environment. Detailed in-situ experiments, as well as the effects of shaft excavation, are also done to study long-term changes, rock properties, groundwater flow and chemistry to ensure the reliability of repository technology and establish safety assessment methodology. (S. Ohno)

  16. Investigating Difficulties of Learning Computer Programming in Saudi Arabia

    Science.gov (United States)

    Alakeel, Ali M.

    2015-01-01

    Learning computer programming is one of the main requirements of many educational study plans in higher education. Research has shown that many students face difficulties acquiring reasonable programming skills during their first year of college. In Saudi Arabia, there are twenty-three state-owned universities scattered around the country that…

  17. INVESTIGATION OF THE TOTAL ORGANIC HALOGEN ANALYTICAL METHOD AT THE WASTE SAMPLING CHARACTERIZATION FACILITY (WSCF)

    International Nuclear Information System (INIS)

    DOUGLAS JG; MEZNARICH HD, PHD; OLSEN JR; ROSS GA; STAUFFER M

    2008-01-01

    Total organic halogen (TOX) is used as a parameter to screen groundwater samples at the Hanford Site. Trending is done for each groundwater well, and changes in TOX and other screening parameters can lead to costly changes in the monitoring protocol. The Waste Sampling and Characterization Facility (WSCF) analyzes groundwater samples for TOX using the United States Environmental Protection Agency (EPA) SW-846 method 9020B (EPA 1996a). Samples from the Soil and Groundwater Remediation Project (S and GRP) are submitted to the WSCF for analysis without information regarding the source of the sample; each sample is in essence a 'blind' sample to the laboratory. Feedback from the S and GRP indicated that some of the WSCF-generated TOX data from groundwater wells had a number of outlier values based on the historical trends (Anastos 2008a). Additionally, analysts at WSCF observed inconsistent TOX results among field sample replicates. Therefore, the WSCF lab performed an investigation of the TOX analysis to determine the cause of the outlier data points. Two causes were found that contributed to generating out-of-trend TOX data: (1) The presence of inorganic chloride in the groundwater samples: at inorganic chloride concentrations greater than about 10 parts per million (ppm), apparent TOX values increase with increasing chloride concentration. A parallel observation is the increase in apparent breakthrough of TOX from the first to the second activated-carbon adsorption tubes with increasing inorganic chloride concentration. (2) During the sample preparation step, excessive purging of the adsorption tubes with oxygen pressurization gas after sample loading may cause channeling in the activated-carbon bed. This channeling leads to poor removal of inorganic chloride during the subsequent wash step with aqueous potassium nitrate. The presence of this residual inorganic chloride then produces erroneously high TOX values. Changes in sample preparation were studied to more

  18. RCRA facility investigation/corrective measures study work plan for the 100-DR-1 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1992-09-01

    Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et. al. 1990a), signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. Also included in the Tri-Party Agreement are 55 Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) facilities that will be closed or permitted to operate in accordance with RCRA regulations. Some of the TSD facilities are included in the operable units. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-DR-1 source operable unit Source operable units include facilities and unplanned release sites that are potential sources of contamination

  19. The Radioactive Ion Beams in Brazil (RIBRAS) facility. Description, program, main results, future plans

    Energy Technology Data Exchange (ETDEWEB)

    Lepine-Szily, A.; Lichtenthaeler, R.; Guimaraes, V. [Instituto de Fisica, Universidade de Sao Paulo (Brazil)

    2014-08-15

    RIBRAS (Radioactive Ion Beams in Brazil) is a facility installed at the Institute of Physics of the University of Sao Paulo (IFUSP), Brazil. The RIBRAS system consists of two superconducting solenoids and uses the ''in-flight method'' to produce radioactive ion beams using the primary beam provided by the 8UD Pelletron Tandem of IFUSP. The ion beams produced so far by RIBRAS are {sup 6}He, {sup 8}Li, {sup 7}Be, {sup 10}Be, {sup 8}B, {sup 12}B with intensities that can vary from 10{sup 4} to 10{sup 6} pps. Initially the experimental program covered the study of elastic and inelastic scattering with the objective to study the interaction potential and the reaction mechanisms between weakly bound (RIB) and halo ({sup 6}He and {sup 8}B) projectiles on light, medium and heavy mass targets. With highly purified beams, the study of resonant elastic scattering and resonant transfer reactions, using inverse kinematics and thick targets, has also been included in our experimental program. Also, transfer reactions of astrophysical interest and fusion reactions induced by halo nuclei are part of the near-future research program. Our recent results on elastic scattering, alpha-particle production and total reaction cross sections, as well as the resonant elastic and transfer reactions, are presented. Our plans for the near future are related to the installation of a new beam line and a cave for gamma-ray detection. We intend to place in operation a large area neutron detector available in our laboratory. The long-range plans could be the move of the RIBRAS system to the more energetic beam line of the LINAC post-accelerator (10MeV/nucleon primary beams) still in construction in our laboratory. (orig.)

  20. The Radioactive Ion Beams in Brazil (RIBRAS) facility. Description, program, main results, future plans

    Science.gov (United States)

    Lépine-Szily, A.; Lichtenthäler, R.; Guimarães, V.

    2014-08-01

    RIBRAS (Radioactive Ion Beams in Brazil) is a facility installed at the Institute of Physics of the University of São Paulo (IFUSP), Brazil. The RIBRAS system consists of two superconducting solenoids and uses the "in-flight method" to produce radioactive ion beams using the primary beam provided by the 8UD Pelletron Tandem of IFUSP. The ion beams produced so far by RIBRAS are 6He, 8Li, 7Be, 10Be, 8B, 12B with intensities that can vary from 104 to 106 pps. Initially the experimental program covered the study of elastic and inelastic scattering with the objective to study the interaction potential and the reaction mechanisms between weakly bound (RIB) and halo (6He and 8B projectiles on light, medium and heavy mass targets. With highly purified beams, the study of resonant elastic scattering and resonant transfer reactions, using inverse kinematics and thick targets, has also been included in our experimental program. Also, transfer reactions of astrophysical interest and fusion reactions induced by halo nuclei are part of the near-future research program. Our recent results on elastic scattering, alpha-particle production and total reaction cross sections, as well as the resonant elastic and transfer reactions, are presented. Our plans for the near future are related to the installation of a new beam line and a cave for gamma-ray detection. We intend to place in operation a large area neutron detector available in our laboratory. The long-range plans could be the move of the RIBRAS system to the more energetic beam line of the LINAC post-accelerator (10MeV/nucleon primary beams) still in construction in our laboratory.

  1. The Annual Neutron School: Program and Facility for Nuclear Science and Technology

    International Nuclear Information System (INIS)

    Dingle, C.A.M.; Bautista, U.M.; Jecong, J.F.M.; Hila, F.C.; Astronomo, A.A.; Olivares, R.U.; Guillermo, N.R.D.; Ramo, M.E.S.K.V.; Saligan, P.P.

    2015-01-01

    The core realization of the mandate of the Philippine Nuclear Research Institute (PNRI) is the establishment and utilization of major nuclear facilities in lieu of the decommissioned research reactor. To address the need for manpower in the future, the applied physics research section (APRS) of the PNRI has initiated capacity building in the use and operation of small neutron sources which attempts to re-establish, develop and sustain expertise in nuclear science and technology. These activities have provided the theoretical and experimental training of young professionals and scientist of the institute which, consequently, resulted in the conceptualization of the Annual Neutron School (ANS).The ANS provides training and teaching environments for the young generation who will operate, utilize and regulate future nuclear facilities. More importantly, it demonstrates and presents the acquired knowledge and research outputs by the staff via “train a trainer” concept to an audience of junior undergraduate students. The successful implementation of the ANS has been participated by selected universities within Metro Manila and was able to train a number of students since its establishment in 2013. The program offers training, education, and R & D in the basic nuclear instrumentation and techniques which includes (1) characterization of different neutron sources – AmBe, PuBe and Cf-252; (2) development of Neutron Activation Analysis (NAA) technique using a portable neutron source for non-destructive elemental analysis; (3) utilization of MCNP (Monte Carlo N-Particle) code for verification of experimental data on neutron characterization, radiation dosimetry, detector design, calibration and efficiency and TRIGA fuel assembly configuration for sub-critical experiments. (author)

  2. Using a new, free spectrograph program to critically investigate acoustics

    Science.gov (United States)

    Ball, Edward; Ruiz, Michael J.

    2016-11-01

    We have developed an online spectrograph program with a bank of over 30 audio clips to visualise a variety of sounds. Our audio library includes everyday sounds such as speech, singing, musical instruments, birds, a baby, cat, dog, sirens, a jet, thunder, and screaming. We provide a link to a video of the sound sources superimposed with their respective spectrograms in real time. Readers can use our spectrograph program to view our library, open their own desktop audio files, and use the program in real time with a computer microphone.

  3. Joint Assessment of Renewable Energy and Water Desalination Research Center (REWDC) Program Capabilities and Facilities In Radioactive Waste Management

    International Nuclear Information System (INIS)

    Bissani, M; Fischer, R; Kidd, S; Merrigan, J

    2006-01-01

    The primary goal of this visit was to perform a joint assessment of the Renewable Energy and Water Desalination Center's (REWDC) program in radioactive waste management. The visit represented the fourth technical and scientific interaction with Libya under the DOE/NNSA Sister Laboratory Arrangement. Specific topics addressed during the visit focused on Action Sheet P-05-5, ''Radioactive Waste Management''. The Team, comprised of Mo Bissani (Team Lead), Robert Fischer, Scott Kidd, and Jim Merrigan, consulted with REWDC management and staff. The team collected information, discussed particulars of the technical collaboration and toured the Tajura facility. The tour included the waste treatment facility, waste storage/disposal facility, research reactor facility, hot cells and analytical labs. The assessment team conducted the first phase of Task A for Action Sheet 5, which involved a joint assessment of the Radioactive Waste Management Program. The assessment included review of the facilities dedicated to the management of radioactive waste at the Tourja site, the waste management practices, proposed projects for the facility and potential impacts on waste generation and management

  4. An Investigation into the Effects of the Hangar Queen Program

    National Research Council Canada - National Science Library

    Larson, Kelly

    2002-01-01

    .... By consolidating the studies performed on cannibalizations (CANNs) and the HQ program, this paper attempts to provide an understanding of the rationale and effects/benefits of the different HQ thresholds...

  5. PETER loop. Multifunctional test facility for thermal hydraulic investigations of PWR fuel elements

    International Nuclear Information System (INIS)

    Ganzmann, I.; Hille, D.; Staude, U.

    2009-01-01

    The reliable fuel element behavior during the complete fuel cycle is one of the fundamental prerequisites of a safe and efficient nuclear power plant operation. The fuel element behavior with respect to pressure drop and vibration impact cannot be simulated by means of fluid-structure interaction codes. Therefore it is necessary to perform tests using fuel element mock-ups (1:1). AREVA NP has constructed the test facility PETER (PWR fuel element tests in Erlangen) loop. The modular construction allows maximum flexibility for any type of fuel elements. Modern measuring instrumentation for flow, pressure and vibration characterization allows the analysis of cause and consequences of thermal hydraulic phenomena. PETER loop is the standard test facility for the qualification of dynamic fuel element behavior in flowing fluid and is used for failure mode analysis.

  6. An investigation into the possibilities and utility of an IKO gamma-ray facility, pt. 2

    International Nuclear Information System (INIS)

    Hicks, R.S.

    1977-01-01

    The bremsstrahlung tagging technique is discussed. Experiments using this technique have already been performed at Illinois, Stanford, Hamburg and Daresburg. A brief survey is given. The instrumentation requirements of a photon-tagging facility are considered. Count rate estimates are presented. It is concluded that competitive count rates should be obtained for photon scattering and neutron spectrometry in the giant resonance and for hadron photoproduction in the delta resonance region

  7. A facility for the experimental investigation of single substance two phase flow

    International Nuclear Information System (INIS)

    Maeder, P.F.; Dickinson, D.A.; Nikitopoulos, D.E.; DiPippo, R.

    1985-01-01

    The paper describes a research facility dedicated to single-substance two-phase flow. The working fluid is dichlorotetrafluoroethane (or refrigerant R-114), allowing both operation at manageable pressures, temperatures and flowrates, and application of results to practical situations through similarity. Operation is in the blowdown mode. The control and data acquisition systems are fully automated and computer controlled. A range of flow conditions from predominantly liquid flow to high velocity, high void fraction choked flow can be attained

  8. 78 FR 38594 - Medicare and Medicaid Programs; Requirements for Long Term Care Facilities; Hospice Services

    Science.gov (United States)

    2013-06-27

    .... The LTC facility regulations clearly specify what services the facility is required to provide to... professional caregivers and are often paid by third-party payers, such as Medicaid. These facilities are... benefit. In regulations at 42 CFR 418.112(c), we specify what must be included in a written agreement...

  9. Evaluation of the Color Me Healthy Program in Influencing Nutrition and Physical Activity in Mississippi Preschool Child Care Facilities

    Science.gov (United States)

    Huye, Holly F.; Bankston, Sarah; Speed, Donna; Molaison, Elaine F.

    2014-01-01

    Purpose/Objectives: The purpose of this research was to determine the level of implementation and perceived value in creating knowledge and behavior change from the Color Me Healthy (CMH) training program in child care centers, family day carehomes, or Head Start facilities throughout Mississippi. Methods: A two-phase survey was used to initially…

  10. The GEOTREF program, a new approach for geothermal investigation

    Science.gov (United States)

    Gérard, Frédéric; Viard, Simon; Garcia, Michel

    2017-04-01

    The GEOTREF is an R&D program supported by the ADEME, French environmental agency and by the «Investissement d'Avenir », a French government program to found innovative projects. The GEOTREF program aims to develop an integrated analysis of high temperature geothermal reservoir in volcanic context. It is a collaborative program between nine research laboratories and two industrial partners. This program is supported for four years and funds 12 PhDs and 5 post-doctoral grants in various fields: geology, petrography, petrophysics, geophysics, geochemistry, reservoir modelling. The first three years are dedicated to the exploration phases that will lead to the drilling implantation. The project has two main objectives. 1.- Developing innovative and interactive methods and workflows leading to develop prospection and exploration in per volcanic geothermal target. This objective implicates: Optimization of the targeting to mitigate financial risks Adapting oil and gas exploration methods to geothermal energy, especially in peri-volcanic context. 2.- Applying this concept to different prospects in the Caribbean and South America The first target zone is located in Guadeloupe, an island of the active arc of the subduction zone where the Atlantic plate subducts under the Caribbean one. The GEOTREF prospect zone is on the Basse Terre Island in its south part closed to the Soufriere volcano, the active volcanic system. On the same island a geothermal field is exploited in Bouillante, just northward from the GEOTREF targeting area.

  11. RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1991-09-01

    This report presents compiled information concerning a facility investigation of waste area group 6(WAG-6), of the solid waste management units (SWMU's) at Oak Ridge National Laboratory (ORNL). The WAG is a shallow ground disposal area for low-level radioactive wastes and chemical wastes. The report contains information on hydrogeological data, contaminant characterization, radionuclide concentrations, risk assessment and baseline human health evaluation including a toxicity assessment, and a baseline environmental evaluation

  12. Print Advertising of Educational Services: an investigation on the impact of the pictures facilities and testimonial about attitudes

    OpenAIRE

    Ayrosa, Eduardo André Teixeira; Facó, Marcos Henrique

    2010-01-01

    Just like other services organizations, some higher education institutions have invested in printed advertising to attract applicants. The services management literature suggests that using stimuli such as pictures of the facilities and alumni testimonials may help to turn tangible the offer of services so strongly intangible as higher education. In the present work, the impact of two different types of cue on prospects' attitudes is investigated. The cue paradigm (Olson & Jacoby 1972) has be...

  13. RCRA Facility Investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    1991-09-01

    This report presents compiled information concerning a facility investigation of waste area group 6(WAG-6), of the solid waste management units (SWMU'S) at Oak Ridge National Laboratory (ORNL). The WAG is a shallow ground disposal area for low-level radioactive wastes and chemical wastes. The report contains information on hydrogeological data, contaminant characterization, radionuclide concentrations, risk assessment from doses to humans and animals and associated cancer risks, exposure via food chains, and historical data

  14. INVESTIGATION OF THE TOTAL ORGANIC HALOGEN ANALYTICAL METHOD AT THE WASTE SAMPLING AND CHARACTERIZATION FACILITY

    International Nuclear Information System (INIS)

    Douglas, J.G.; Meznarich, H.K.; Olsen, J.R.; Ross, G.A.; Stauffer, M.

    2009-01-01

    Total organic halogen (TOX) is used as a parameter to screen groundwater samples at the Hanford Site. Trending is done for each groundwater well, and changes in TOX and other screening parameters can lead to costly changes in the monitoring protocol. The Waste Sampling and Characterization Facility (WSCF) analyzes groundwater samples for TOX using the United States Environmental Protection Agency (EPA) SW-S46 method 9020B (EPA 1996a). Samples from the Soil and Groundwater Remediation Project (SGRP) are submitted to the WSCF for analysis without information regarding the source of the sample; each sample is in essence a ''blind'' sample to the laboratory. Feedback from the SGRP indicated that some of the WSCF-generated TOX data from groundwater wells had a number of outlier values based on the historical trends (Anastos 200Sa). Additionally, analysts at WSCF observed inconsistent TOX results among field sample replicates. Therefore, the WSCF lab performed an investigation of the TOX analysis to determine the cause of the outlier data points. Two causes were found that contributed to generating out-of-trend TOX data: (1) The presence of inorganic chloride in the groundwater samples: at inorganic chloride concentrations greater than about 10 parts per million (ppm), apparent TOX values increase with increasing chloride concentration. A parallel observation is the increase in apparent breakthrough of TOX from the first to the second activated-carbon adsorption tubes with increasing inorganic chloride concentration. (2) During the sample preparation step, excessive purging of the adsorption tubes with oxygen pressurization gas after sample loading may cause channeling in the activated carbon bed. This channeling leads to poor removal of inorganic chloride during the subsequent wash step with aqueous potassium nitrate. The presence of this residual inorganic chloride then produces erroneously high TOX values. Changes in sample preparation were studied to more effectively

  15. Material testing facilities and programs for plasma-facing component testing

    Science.gov (United States)

    Linsmeier, Ch.; Unterberg, B.; Coenen, J. W.; Doerner, R. P.; Greuner, H.; Kreter, A.; Linke, J.; Maier, H.

    2017-09-01

    Component development for operation in a large-scale fusion device requires thorough testing and qualification for the intended operational conditions. In particular environments are necessary which are comparable to the real operation conditions, allowing at the same time for in situ/in vacuo diagnostics and flexible operation, even beyond design limits during the testing. Various electron and neutral particle devices provide the capabilities for high heat load tests, suited for material samples and components from lab-scale dimensions up to full-size parts, containing toxic materials like beryllium, and being activated by neutron irradiation. To simulate the conditions specific to a fusion plasma both at the first wall and in the divertor of fusion devices, linear plasma devices allow for a test of erosion and hydrogen isotope recycling behavior under well-defined and controlled conditions. Finally, the complex conditions in a fusion device (including the effects caused by magnetic fields) are exploited for component and material tests by exposing test mock-ups or material samples to a fusion plasma by manipulator systems. They allow for easy exchange of test pieces in a tokamak or stellarator device, without opening the vessel. Such a chain of test devices and qualification procedures is required for the development of plasma-facing components which then can be successfully operated in future fusion power devices. The various available as well as newly planned devices and test stands, together with their specific capabilities, are presented in this manuscript. Results from experimental programs on test facilities illustrate their significance for the qualification of plasma-facing materials and components. An extended set of references provides access to the current status of material and component testing capabilities in the international fusion programs.

  16. A resource facility for kinetic analysis: modeling using the SAAM computer programs.

    Science.gov (United States)

    Foster, D M; Boston, R C; Jacquez, J A; Zech, L

    1989-01-01

    Kinetic analysis and integrated system modeling have contributed significantly to understanding the physiology and pathophysiology of metabolic systems in humans and animals. Many experimental biologists are aware of the usefulness of these techniques and recognize that kinetic modeling requires special expertise. The Resource Facility for Kinetic Analysis (RFKA) provides this expertise through: (1) development and application of modeling technology for biomedical problems, and (2) development of computer-based kinetic modeling methodologies concentrating on the computer program Simulation, Analysis, and Modeling (SAAM) and its conversational version, CONversational SAAM (CONSAM). The RFKA offers consultation to the biomedical community in the use of modeling to analyze kinetic data and trains individuals in using this technology for biomedical research. Early versions of SAAM were widely applied in solving dosimetry problems; many users, however, are not familiar with recent improvements to the software. The purpose of this paper is to acquaint biomedical researchers in the dosimetry field with RFKA, which, together with the joint National Cancer Institute-National Heart, Lung and Blood Institute project, is overseeing SAAM development and applications. In addition, RFKA provides many service activities to the SAAM user community that are relevant to solving dosimetry problems.

  17. Results from phase 2 of the radioiodine test facility experimental program

    International Nuclear Information System (INIS)

    Ball, J.M.; Kupferschmid, W.C.H.; Wren, J.C.

    1996-01-01

    A series of intermediate-scale experiments were conducted in the Radioiodine Test Facility (RTF) in a vinyl-painted, zinc-primer coated, carbon steel vessel in order to assess the effects of vinyl surfaces on iodine volatility in both the presence and absence of radiation. This test series, Phase 2 of a larger, comprehensive program assessing a variety of containment surfaces, also examined the effects of organic (i.e., methyl ethyl ketone) and inorganic (i.e., hydrazine) additives, pH, and venting on the aqueous chemistry and volatility of solutions initially containing cesium iodide. These tests have clearly demonstrated that organics are released to the aqueous phase from the vinyl coating and that, under radiation conditions, these organics can have a significant effect on the formation of volatile iodine species. In particular, the RTF results suggest that radiolytic decomposition of the released organics results in dramatic reductions in pH and dissolved oxygen concentration, which in turn are responsible for increased formation of molecular iodine and organic iodides. When the pH was maintained at 10 (Test 3), much lower iodine volatility was observed; low iodine volatility was also observed in the absence of radiation. This test series also demonstrated that vinyl surfaces, particularly those in contact with the gas phase, were a sink for iodine. (author) 4 figs., 6 tabs., 17 refs

  18. Results from phase 2 of the radioiodine test facility experimental program

    Energy Technology Data Exchange (ETDEWEB)

    Ball, J M; Kupferschmid, W C.H.; Wren, J C [Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs.

    1996-12-01

    A series of intermediate-scale experiments were conducted in the Radioiodine Test Facility (RTF) in a vinyl-painted, zinc-primer coated, carbon steel vessel in order to assess the effects of vinyl surfaces on iodine volatility in both the presence and absence of radiation. This test series, Phase 2 of a larger, comprehensive program assessing a variety of containment surfaces, also examined the effects of organic (i.e., methyl ethyl ketone) and inorganic (i.e., hydrazine) additives, pH, and venting on the aqueous chemistry and volatility of solutions initially containing cesium iodide. These tests have clearly demonstrated that organics are released to the aqueous phase from the vinyl coating and that, under radiation conditions, these organics can have a significant effect on the formation of volatile iodine species. In particular, the RTF results suggest that radiolytic decomposition of the released organics results in dramatic reductions in pH and dissolved oxygen concentration, which in turn are responsible for increased formation of molecular iodine and organic iodides. When the pH was maintained at 10 (Test 3), much lower iodine volatility was observed; low iodine volatility was also observed in the absence of radiation. This test series also demonstrated that vinyl surfaces, particularly those in contact with the gas phase, were a sink for iodine. (author) 4 figs., 6 tabs., 17 refs.

  19. Image quality of mammography in Croatian nationwide screening program: Comparison between various types of facilities

    International Nuclear Information System (INIS)

    Brnić, Zoran; Blašković, Darko; Klasić, Branimir; Ramač, Jelena Popić; Flegarić-Bradić, Mirjana; Štimac, Damir; Lubina, Ivan Zvonimir; Brnić, Vedran; Faj, Dario

    2012-01-01

    Purpose: The study was aimed to provide objective evidence about the mammographic image quality in Croatia, to compare it between different types of MG facilities and to identify the most common deficiencies and possible reasons as well as the steps needed to improve image quality. Materials and methods: A total of 420 mammographic examinations collected from 84 mammographic units participating in the Croatian nationwide breast cancer screening program were reviewed in terms of four image quality categories: identification of patient and examination, breast positioning and compression, exposure and contrast, and artifacts. Those were rated using image evaluating system based on American College of Radiology and European Commission proposals. The results were compared among different types of mammographic units, and common image quality deficiencies were identified. Results: Total image quality scores of 12.8, 16.1, 13.0 and 13.7 were found for general hospitals, university hospitals, private clinics and public healthcare centres, respectively. Average score for all mammographic units was 13.5 (out of 25 points). University hospitals were significantly better than all other mammography units in overall image quality, which was mostly contributed by better breast positioning practices. Private clinics showed the worst results in identification, exposure, contrast and artifacts. Conclusions: Serious deficiencies in identification and breast positioning, which might compromise breast cancer screening outcome, were detected in our material. They occur mainly due to subjective reasons and could be corrected through additional staff training and improvement of working discipline.

  20. Initial design for an experimental investigation of strongly coupled plasma behavior in the Atlas facility

    International Nuclear Information System (INIS)

    Munson, C.P.; Benage, J.F. Jr.; Taylor, A.J.; Trainor, R.J. Jr.; Wood, B.P.; Wysocki, F.J.

    1999-01-01

    Atlas is a high current (approximately 30 MA peak, with a current risetime approximately 4.5 microsec), high energy (E stored = 24 MJ, E load = 3--6 MJ), pulsed power facility which is being constructed at Los Alamos National Laboratory with a scheduled completion date in the year 2000. When operational, this facility will provide a platform for experiments in high pressure shocks (> 20 Mbar), adiabatic compression (ρ/ρ 0 > 5, P > 10 Mbar), high magnetic fields (approximately 2,000 T), high strain and strain rates (var e psilon > 200%, dvar e psilon/dt approximately 10 4 to 10 6 s -1 ), hydrodynamic instabilities of materials in turbulent regimes, magnetized target fusion, equation of state, and strongly coupled plasmas. For the strongly coupled plasma experiments, an auxiliary capacitor bank will be used to generate a moderate density (< 0.1 solid), relatively cold (approximately 1 eV) plasma by ohmic heating of a conducting material of interest such as titanium. This stargate plasma will be compressed against a central column containing diagnostic instrumentation by a cylindrical conducting liner that is driven radially inward by current from the main Atlas capacitor bank. The plasma is predicted to reach densities of approximately 1.1 times solid, achieve ion and electron temperatures of approximately 10 eV, and pressures of approximately 4--5 Mbar. This is a density/temperature regime which is expected to experience strong coupling, but only partial degeneracy. X-ray radiography is planned for measurements of the material density at discrete times during the experiments; diamond Raman measurements are anticipated for determination of the pressure. In addition, a neutron resonance spectroscopic technique is being evaluated for possible determination of the temperature (through low percentage doping of the titanium with a suitable resonant material). Initial target plasma formation experiments are being planned on an existing pulsed power facility at LANL and

  1. Investigation of water accumulation in an offgas test facility HEPA housing

    International Nuclear Information System (INIS)

    Speed, D.L.; Burns, D.B.; Van Pelt, W.B.; Burns, H.H.

    1997-01-01

    The Consolidated Incineration Facility, at the Department of Energy's Savannah River Site, is designed to treat solid and liquid RCRA hazardous and mixed wastes generated by site operations and clean-up activities. During CIF's pretrial burn campaigns in 1995, an appreciable amount of water was recovered from the HEPA housings. Questions were immediately raised as to the source of the water, and the degree of wetness of the filters during operation. There are two primary issues involved: Water could reduce the life expectancy and performance of the HEPA filters, housing, and associated ducting, and wet HEPAs also present radiological concerns for personnel during filter change-out. A similar phenomenon was noted at the Offgas Components Test Facility (OCTF), a 1/10 scale pilot of CIF's air pollution control system. Tests at OCTF indicated the water's most likely origin to be vapor condensing out from the flue gas stream due to excessive air in-leakage at housing door seals, ducting flanges, and actual holes in the ducting. The rate of accumulation bears no statistical correlation to such process parameters as steam flow, reheater outlet temperature and offgas velocity in the duct. Test results also indicated that the HEPA filter media is moistened by the initial process flow while the facility is being brought on line. However, even when the HEPA filters were manually drenched prior to startup, they became completely dry within four hours of the time steam was introduced to the reheater. Finally, no demonstrable relationship was found between the degree of filter media wetness and filter dP

  2. Dismantling of Irradiation Facility Selfshielded of Investigation Model MPX- γ-25M

    International Nuclear Information System (INIS)

    Soguero, D.; Rapado, M.; Prieto, E.; Desdin, L.; Guerra, M.; Castillo, J.

    2011-01-01

    In this paper is described the dismantling a category I selfshielded gamma irradiation facility model MPX - γ - 25M. The following specific objectives were established: a) identify aspects of the insurance contract, human and technical resources b) assess the radiological situation of the process and c) analyze potential radiological extraordinary events in each step of the process, ensuring appropriate responses, based on an evaluation of process safety. The assessment of radiological events can serve as a reference for addressing the process of dismantling other similar irradiators. (Author)

  3. An investigation into the possibilities and utility of an IKO gamma-ray facility, pt. 1

    International Nuclear Information System (INIS)

    Hicks, R.

    1976-01-01

    Experiments on nuclei using purely electromagnetic probes are transparent in that the interaction is among the simplest and best understood in nuclear physics. This report is directed to the possible capabilities and applications of an IKO photon facility. Particular emphasis is given to the bremsstrahlung monochromator. This is a device for identifying or tagging the energies of individual photons in a γ-ray beam that is continuous in energy. In this study the various experimental techniques for producing beams of photons are discussed

  4. Nuclear magnetic resonance facility for investigation of a disk of the body

    International Nuclear Information System (INIS)

    Clow, H.; Walters, P.E.

    1979-01-01

    By means of the facility there can be determined the distribution of the water content or of the relaxation-time constants in cross-sectional deils or volumes of the patient. The magnetic field applied is described in form of pulses. In order to achieve the required equal field integrals there is performed an inquiry on the magnetic field at times predetermined for the gradient-pulse shape. The gradient-pulse shape itself is sinusoidal or deformed-sinusoidal. In the circuit for field measurement and error signal there are used Yttrium-Iron-Garnet (YIG) oscillator probes. (RW) [de

  5. A nuclear physics program at the Rare Isotope Beams Accelerator Facility in Korea

    Directory of Open Access Journals (Sweden)

    Chang-Bum Moon

    2014-02-01

    Full Text Available This paper outlines the new physics possibilities that fall within the field of nuclear structure and astrophysics based on experiments with radioactive ion beams at the future Rare Isotope Beams Accelerator facility in Korea. This ambitious multi-beam facility has both an Isotope Separation On Line (ISOL and fragmentation capability to produce rare isotopes beams (RIBs and will be capable of producing and accelerating beams of wide range mass of nuclides with energies of a few to hundreds MeV per nucleon. The large dynamic range of reaccelerated RIBs will allow the optimization in each nuclear reaction case with respect to cross section and channel opening. The low energy RIBs around Coulomb barrier offer nuclear reactions such as elastic resonance scatterings, one or two particle transfers, Coulomb multiple-excitations, fusion-evaporations, and direct capture reactions for the study of the very neutron-rich and proton-rich nuclides. In contrast, the high energy RIBs produced by in-flight fragmentation with reaccelerated ions from the ISOL enable to explore the study of neutron drip lines in intermediate mass regions. The proposed studies aim at investigating the exotic nuclei near and beyond the nucleon drip lines, and to explore how nuclear many-body systems change in such extreme regions by addressing the following topics: the evolution of shell structure in areas of extreme proton to neutron imbalance; the study of the weak interaction in exotic decay schemes such as beta-delayed two-neutron or two-proton emission; the change of isospin symmetry in isobaric mirror nuclei at the drip lines; two protons or two neutrons radioactivity beyond the drip lines; the role of the continuum states including resonant states above the particle-decay threshold in exotic nuclei; and the effects of nuclear reaction rates triggered by the unbound proton-rich nuclei on nuclear astrophysical processes.

  6. Employee Assistance Programs: A Systemic Investigation of Their Use.

    Science.gov (United States)

    Gerstein, Lawrence H.; Bayer, Gregory A.

    1988-01-01

    Reviews three articles from the EAP Digest which discuss the low employee-penetration rate of employee assistance programs. Claims low rates may be a result of environmental, employee, and supervisory attitudes about referral and intervention responsibilities. Concludes future of counselors as feasible service providers hinges partly on successful…

  7. Investigation of Storage Options for Scientific Computing on Grid and Cloud Facilities

    International Nuclear Information System (INIS)

    Garzoglio, Gabriele

    2012-01-01

    In recent years, several new storage technologies, such as Lustre, Hadoop, OrangeFS, and BlueArc, have emerged. While several groups have run benchmarks to characterize them under a variety of configurations, more work is needed to evaluate these technologies for the use cases of scientific computing on Grid clusters and Cloud facilities. This paper discusses our evaluation of the technologies as deployed on a test bed at FermiCloud, one of the Fermilab infrastructure-as-a-service Cloud facilities. The test bed consists of 4 server-class nodes with 40 TB of disk space and up to 50 virtual machine clients, some running on the storage server nodes themselves. With this configuration, the evaluation compares the performance of some of these technologies when deployed on virtual machines and on “bare metal” nodes. In addition to running standard benchmarks such as IOZone to check the sanity of our installation, we have run I/O intensive tests using physics-analysis applications. This paper presents how the storage solutions perform in a variety of realistic use cases of scientific computing. One interesting difference among the storage systems tested is found in a decrease in total read throughput with increasing number of client processes, which occurs in some implementations but not others.

  8. HEPCloud, a New Paradigm for HEP Facilities: CMS Amazon Web Services Investigation

    Energy Technology Data Exchange (ETDEWEB)

    Holzman, Burt [Fermilab; Bauerdick, Lothar A.T. [Fermilab; Bockelman, Brian [Nebraska U.; Dykstra, Dave [Fermilab; Fisk, Ian [New York U.; Fuess, Stuart [Fermilab; Garzoglio, Gabriele [Fermilab; Girone, Maria [CERN; Gutsche, Oliver [Fermilab; Hufnagel, Dirk [Fermilab; Kim, Hyunwoo [Fermilab; Kennedy, Robert [Fermilab; Magini, Nicolo [Fermilab; Mason, David [Fermilab; Spentzouris, Panagiotis [Fermilab; Tiradani, Anthony [Fermilab; Timm, Steve [Fermilab; Vaandering, Eric W. [Fermilab

    2017-09-29

    Historically, high energy physics computing has been performed on large purpose-built computing systems. These began as single-site compute facilities, but have evolved into the distributed computing grids used today. Recently, there has been an exponential increase in the capacity and capability of commercial clouds. Cloud resources are highly virtualized and intended to be able to be flexibly deployed for a variety of computing tasks. There is a growing nterest among the cloud providers to demonstrate the capability to perform large-scale scientific computing. In this paper, we discuss results from the CMS experiment using the Fermilab HEPCloud facility, which utilized both local Fermilab resources and virtual machines in the Amazon Web Services Elastic Compute Cloud. We discuss the planning, technical challenges, and lessons learned involved in performing physics workflows on a large-scale set of virtualized resources. In addition, we will discuss the economics and operational efficiencies when executing workflows both in the cloud and on dedicated resources.

  9. Knowledge management awareness in a research and development facility: Investigating employee perceptions

    Directory of Open Access Journals (Sweden)

    Andrea Potgieter

    2013-12-01

    Objectives: This study aimed to understand Sasol R&D employees’ perceptions of knowledge management (KM. The study also assessed the attitude of Sasol R&D management towards KM. Method: The target population for this research included different levels of seniority and education in Sasol R&D. A questionnaire was distributed to a sample of 150 employees in R&D and 50 more who work closely with R&D in support functions. Results: It was found that the importance of KM is understood by Sasol R&D employees and management. It was established that Sasol R&D management regard KM as important, but that their commitment to KM initiatives is not necessarily evident for employees. A concern highlighted by the study was that employees were not aware of the duties of the identified KM champions within their facility. Conclusion: It was suggested that Sasol R&D employees should be made aware of the duties of KM champions. It was also established that Sasol R&D management needs to be more visible in their support of KM initiatives. Recommendations based on the findings of the study can assist Sasol R&D, and other facilities attempting to implement a KM strategy, to gain insight into the perceptions of employees and the role management needs to play in the facilitation of this process.

  10. Initial design for an experimental investigation of strongly coupled plasma behavior in the ATLAS facility

    CERN Document Server

    Munson, C P; Taylor, A J; Trainor, R J; Wood, B P; Wysocki, F J

    1999-01-01

    Summary form only given. Atlas is a high current (~30 MA peak, with a current risetime ~4.5 mu sec), high energy (E/sub stored/=24 MJ, E /sub load/=3-6 MJ), pulsed power facility which is being constructed at Los Alamos National Laboratory with a scheduled completion date in the year 2000. When operational, this facility will provide a platform for experiments in high pressure shocks (>20 Mbar), adiabatic compression ( rho / rho /sub 0/>5, P>10 Mbar), high magnetic fields (~2000 T), high strain and strain rates ( epsilon >200, d epsilon /dt~10/sup 4/ to 10/sup 6/ s/sup -1/), hydrodynamic instabilities of materials in turbulent regimes, magnetized target fusion, equation of state, and strongly coupled plasmas. For the strongly coupled plasma experiments, an auxiliary capacitor bank will be used to generate a moderate density (<0.1 solid), relatively cold (~1 eV) plasma by ohmic heating of a conducting material of interest such as titanium. This target plasma will be compressed against a central column conta...

  11. Nevada Nuclear Waste Storage Investigations: Exploratory Shaft Facility fluids and materials evaluation

    Energy Technology Data Exchange (ETDEWEB)

    West, K.A.

    1988-11-01

    The objective of this study was to determine if any fluids or materials used in the Exploratory Shaft Facility (ESF) of Yucca Mountain will make the mountain unsuitable for future construction of a nuclear waste repository. Yucca Mountain, an area on and adjacent to the Nevada Test Site in southern Nevada, USA, is a candidate site for permanent disposal of high-level radioactive waste from commercial nuclear power and defense nuclear activities. To properly characterize Yucca Mountain, it will be necessary to construct an underground test facility, in which in situ site characterization tests can be conducted. The candidate repository horizon at Yucca Mountain, however, could potentially be compromised by fluids and materials used in the site characterization tests. To minimize this possibility, Los Alamos National Laboratory was directed to evaluate the kinds of fluids and materials that will be used and their potential impacts on the site. A secondary objective was to identify fluids and materials, if any, that should be prohibited from, or controlled in, the underground. 56 refs., 19 figs., 11 tabs.

  12. Nevada Nuclear Waste Storage Investigations: Exploratory Shaft Facility fluids and materials evaluation

    International Nuclear Information System (INIS)

    West, K.A.

    1988-11-01

    The objective of this study was to determine if any fluids or materials used in the Exploratory Shaft Facility (ESF) of Yucca Mountain will make the mountain unsuitable for future construction of a nuclear waste repository. Yucca Mountain, an area on and adjacent to the Nevada Test Site in southern Nevada, USA, is a candidate site for permanent disposal of high-level radioactive waste from commercial nuclear power and defense nuclear activities. To properly characterize Yucca Mountain, it will be necessary to construct an underground test facility, in which in situ site characterization tests can be conducted. The candidate repository horizon at Yucca Mountain, however, could potentially be compromised by fluids and materials used in the site characterization tests. To minimize this possibility, Los Alamos National Laboratory was directed to evaluate the kinds of fluids and materials that will be used and their potential impacts on the site. A secondary objective was to identify fluids and materials, if any, that should be prohibited from, or controlled in, the underground. 56 refs., 19 figs., 11 tabs

  13. The experimental facility for investigation of MHD heat transfer in perspective coolants in nuclear energetics.

    Science.gov (United States)

    Batenin, B. M.; Belyaev, I. A.; Birukov, D. A.; Frick, P. G.; Nikitina, I. S.; Manchkha, S. P.; Pyatnitskaya, N. Yu; Razuvanov, N. G.; Sviridov, E. V.; Sviridov, V. G.

    2017-11-01

    Paper presents the current results of work conducted by a joint research group of MPEI-JIHT RAS for experimental study of liquid metals heat transfer. The team of specialists of MPEI-JIHT RAS put into operation a new mercury MHD facility RK-3. The main components of this stand are: a unique electromagnet, created by specialists of the Budker Institute of Nuclear Physics (BINP), and a sealed liquid-metal circuit. The facility will be explored lifting and standpipe flow of liquid metal in a transverse magnetic field in channels of different forms. For the experiments on the study of heat transfer and hydrodynamics of flows for measuring characteristics such as temperature, speed, pulse characteristics, probe method is used. Presents the first experimental results obtained for a pipe in a transverse magnetic field. During the experiments with various flow parameters data was obtained and processed with constructing temperature fields, dimensionless wall temperature distributions and heat transfer coefficients along the perimeter of the work area. Modes with low frequency pulsations of temperature were discovered. The boundaries where low frequency temperature fluctuations occur were defined in a circular tube.

  14. A 10-TW Pulsed Facility "PIRIT" for Investigation of Short-Wave Radiation Generation.

    Science.gov (United States)

    Popkov, N F; Ryaslov, E A; Kargin, V I; Pikar', A S; Kotel'nikov, D V; Melkozerov, A V

    1995-01-01

    The results of experiments with a plasma x-ray source in the PIRIT-2000 facility are presented in this paper. The facility is designed with module capacitive energy storage energizing vacuum inductive storage. The formation of a rapidly growing current pulse as well as its commutation on a load was carried out by a plasma opening switch. A vacuum diode as well as various types of plasma loads can be used for the generation of a high-power x-ray flux. The storage energy of a 54-module capacitive storage is up to 2 MJ, its inductance is 15 nH, and its output voltage is 500 kV. The peak current in the plasma load constituted 4 MA with a 150-ns rise time. The maximum integral energy output of x radiation measured by an open thermocouple calorimeter was as high as 100 kJ, while the primary storage energy was 1 MJ. The plasma load usage at a current of 4 MA ensured a 100-kJ generation in x-ray radiation and the density of the radiation flux at a distance of 1 m from the source was as much as 0.8 J/cm2, while near the source it was 10 J/cm2.

  15. Methods and results of implementing a commercially available videotaped health physics training program in a multi-disciplined DOE facility

    International Nuclear Information System (INIS)

    O'Neal, B.L.

    1979-01-01

    Sandia, a prime contractor for DOE, is a multi-disciplined research and development laboratory. Its various activities include the operations of two nuclear reactors, several multi-kilocurie gamma irradiation facilities, a transuranic hot cell facility, various and numerous particle accelerators and x-ray generators, and many other areas involving employees working with or around radioactive materials or radiation producing machines. Since March 1979, Sandia has conducted a formalized basic radiation safety training program using a commercially available videotaped training package. The videotapes are generic in nature and are accompanied with hard copy text material, vu-graphs, quizzes, and an instructor's guide. Sandia's overall training program and the methods, results, and problem areas of implementing an off the shelf, commercially available videotaped training program are described. Results are summarized using an instructor/course/student evaluation form

  16. Grande Ronde Endemic Spring Chinook Salmon Supplementation Program: Facility Operation and Maintenance and Monitoring and Evaluation, 2000 Annual Report.

    Energy Technology Data Exchange (ETDEWEB)

    Boe, Stephen J.; Lofy, Peter T. (Confederated Tribes of the Umatilla Indian Reservation, Pendleton, OR)

    2003-03-01

    This is the third annual report of a multi-year project to operate adult collection and juvenile acclimation facilities on Catherine Creek and the upper Grande Ronde River for Snake River spring chinook salmon. These two streams have historically supported populations that provided significant tribal and non-tribal fisheries. Supplementation using conventional and captive broodstock techniques is being used to restore fisheries in these streams. Statement of Work Objectives for 2000: (1) Participate in implementation of the comprehensive multiyear operations plan for the Grande Ronde Endemic Spring Chinook Supplementation Program (GRESCP). (2) Plan for recovery of endemic summer steelhead populations in Catherine Creek and the upper Grande Ronde River. (3) Ensure proper construction and trial operation of semi-permanent adult and juvenile facilities for use in 2000. (4) Collect summer steelhead. (5) Collect adult endemic spring chinook salmon broodstock. (6) Acclimate juvenile spring chinook salmon prior to release into the upper Grande Ronde River and Catherine Creek. (7) Document accomplishments and needs to permitters, comanagers, and funding agency. (8) Communicate project results to the scientific community. (9) Plan detailed GRESCP Monitoring and Evaluation for future years. (10) Monitor adult population abundance and characteristics of Grande Ronde River spring chinook salmon populations and incidentally-caught summer steelhead and bull trout. (11) Monitor condition, movement, and mortality of spring chinook salmon acclimated at remote facilities. (12) Monitor water quality at facilities. (13) Participate in Monitoring & Evaluation of the captive brood component of the Program to document contribution to the Program.

  17. RCRA facility investigation/corrective measures study work plan for the 100-HR-3 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1992-09-01

    Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order, signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. Also included in the Tri-Party Agreement are 55 Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) facilities that will be closed or permitted to operate in accordance with RCRA regulations, under the authority of Chapter 173-303 Washington Administrative Code (WAC). Some of the TSD facilities are included in the operable units. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-HR-3 operable unit. The 100-HR-3 operable unit underlies the D/DR and H Areas, the 600 Area between them, and the six source operable units these areas contain. The 100-HR-3 operable unit includes all contamination found in the aquifer soils and water within its boundary. Source operable units include facilities and unplanned release sites that are potential sources of contamination. Separate work plans have been initiated for the 100-DR-1 (DOE-RL 1992a) and 100-HR-1 (DOE-RL 1992b) source operable units

  18. Initial design for an experimental investigation of strongly coupled plasma behavior in the Atlas facility

    Energy Technology Data Exchange (ETDEWEB)

    Munson, C.P.; Benage, J.F. Jr.; Taylor, A.J.; Trainor, R.J. Jr.; Wood, B.P.; Wysocki, F.J.

    1999-07-01

    Atlas is a high current ({approximately} 30 MA peak, with a current risetime {approximately} 4.5 {micro}sec), high energy (E{sub stored} = 24 MJ, E{sub load} = 3--6 MJ), pulsed power facility which is being constructed at Los Alamos National Laboratory with a scheduled completion date in the year 2000. When operational, this facility will provide a platform for experiments in high pressure shocks (> 20 Mbar), adiabatic compression ({rho}/{rho}{sub 0} > 5, P > 10 Mbar), high magnetic fields ({approximately} 2,000 T), high strain and strain rates ({var_epsilon} > 200%, d{var_epsilon}/dt {approximately} 10{sup 4} to 10{sup 6} s{sup {minus}1}), hydrodynamic instabilities of materials in turbulent regimes, magnetized target fusion, equation of state, and strongly coupled plasmas. For the strongly coupled plasma experiments, an auxiliary capacitor bank will be used to generate a moderate density (< 0.1 solid), relatively cold ({approximately} 1 eV) plasma by ohmic heating of a conducting material of interest such as titanium. This stargate plasma will be compressed against a central column containing diagnostic instrumentation by a cylindrical conducting liner that is driven radially inward by current from the main Atlas capacitor bank. The plasma is predicted to reach densities of {approximately} 1.1 times solid, achieve ion and electron temperatures of {approximately} 10 eV, and pressures of {approximately} 4--5 Mbar. This is a density/temperature regime which is expected to experience strong coupling, but only partial degeneracy. X-ray radiography is planned for measurements of the material density at discrete times during the experiments; diamond Raman measurements are anticipated for determination of the pressure. In addition, a neutron resonance spectroscopic technique is being evaluated for possible determination of the temperature (through low percentage doping of the titanium with a suitable resonant material). Initial target plasma formation experiments are

  19. ISS Biotechnology Facility - Overview of Analytical Tools for Cellular Biotechnology Investigations

    Science.gov (United States)

    Jeevarajan, A. S.; Towe, B. C.; Anderson, M. M.; Gonda, S. R.; Pellis, N. R.

    2001-01-01

    The ISS Biotechnology Facility (BTF) platform provides scientists with a unique opportunity to carry out diverse experiments in a microgravity environment for an extended period of time. Although considerable progress has been made in preserving cells on the ISS for long periods of time for later return to Earth, future biotechnology experiments would desirably monitor, process, and analyze cells in a timely way on-orbit. One aspect of our work has been directed towards developing biochemical sensors for pH, glucose, oxygen, and carbon dioxide for perfused bioreactor system developed at Johnson Space Center. Another aspect is the examination and identification of new and advanced commercial biotechnologies that may have applications to on-orbit experiments.

  20. Thermal hydraulic behavior of a PWR under beyond-design-basis accident conditions: Conclusions from an experimental program in a 4-loop test facility (PKL)

    International Nuclear Information System (INIS)

    Umminger, K.J.; Kastner, W.; Mandl, R.M.; Weber, P.

    1993-01-01

    Within the scope of German reactor safety research, extensive experiments covering the behavior of nuclear power plants under accident conditions have been carried out in the PKL test facility which simulates a 4-loop, 1,300 MWe KWU-designed PWR. While the investigations dealing with design-basis accidents and with the efficiency of the emergency core cooling systems have been largely completed, the main interest nowadays concentrates on the investigation of beyond-design-basis accidents to demonstrate the safety margins of nuclear power plants and to investigate the contribution of the built-in safety features for a further reduction of the residual risk. The thermal hydraulic behavior of a PWR under these extreme accident conditions was experimentally investigated within the PKL III B test program. This paper presents the fundamental findings with some of the most important results being discussed in detail. Future plans are also outlined

  1. 25 CFR 170.152 - What transit facilities and activities are eligible for IRR Program funding?

    Science.gov (United States)

    2010-04-01

    ... development, such as bus shelters in shopping centers, parking lots, pedestrian improvements, and support facilities that incorporate other community services; (h) Passenger shelters, bus stop signs, and similar..., buildings, facilities, buses, vans, water craft, and other vehicles for use in mass transportation; (b...

  2. Selecting Television Programs for Language Learning: Investigating Television Programs from the Same Genre

    Science.gov (United States)

    Webb, Stuart

    2011-01-01

    The scripts of 288 television episodes were analysed to determine the extent to which vocabulary reoccurs in television programs from the same subgenres and unrelated television programs from different genres. Episodes from two programs from each of the following three subgenres of the American drama genre: medical, spy/action, and criminal…

  3. Emission Facilities - Erosion & Sediment Control Facilities

    Data.gov (United States)

    NSGIC Education | GIS Inventory — An Erosion and Sediment Control Facility is a DEP primary facility type related to the Water Pollution Control program. The following sub-facility types related to...

  4. Yearly program of safety research in nuclear power facilities from fiscal 1981 to 1985

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    Nuclear safety research plans for nuclear power facilities and others from fiscal 1981 to 1985 are presented for the following areas: the safety of LWR fuel, loss-of-coolant accidents, the structural safety of LWR installations, the reduction of radioactive material release from nuclear power facilities, the stochastic safety evaluation of nuclear power facilities, the aseismicity of nuclear power facilities, the safety of nuclear fuel facilities, and the safety of nuclear fuel transport vessels. In the respective areas, the needs for research and the outline of research works are summarized. Then, about the major research works in each area, the purpose, contents, term and responsible institution of the research are given. (Mori, K.)

  5. European Facility for Antiproton and Ion Research (FAIR): the new international center for fundamental physics and its research program

    International Nuclear Information System (INIS)

    Fortov, Vladimir E; Sharkov, Boris Yu; Stöker, H

    2012-01-01

    The Facility for Antiproton and Ion Research (FAIR) accelerator center at Darmstadt, Germany, will provide the international scientific community with unique experimental opportunities of a scope and scale out of reach for any other large-scale facility in the world. With its staff of over 2500, it is expected to fundamentally expand our knowledge of hadron, nuclear, and atomic physics and their application to cosmology, astrophysics, and technology. In this review, the design details of the accelerator complex are discussed and the experimental research program for FAIR is presented. Particular attention is paid to experiments on the extreme state of matter arising from the isochoric heating of a material by heavy-ion beams. One of the largest facilities of its kind in Europe, FAIR is a part of the strategic development roadmap for the European Strategic Forum on Research Infrastructures (ESFRI). (physics of our days)

  6. Project description: ORNL PWR blowdown heat transfer separate-effects program, Thermal-Hydraulic Test Facility (THTF)

    International Nuclear Information System (INIS)

    1976-02-01

    The ORNL Pressurized-Water Reactor Blowdown Heat Transfer (PWR-BDHT) Program is an experimental separate-effects study of the relations among the principal variables that can alter the rate of blowdown, the presence of flow reversal and rereversal, time delay to critical heat flux, the rate at which dryout progresses, and similar time-related functions that are important to LOCA analysis. Primary test results will be obtained from the Thermal-Hydraulic Test Facility (THTF), a large nonnuclear pressurized-water loop that incorporates a 49-rod electrically heated bundle. Supporting experiments will be carried out in two additional test loops - the Forced Convection Test Facility (FCTF), a small high-pressure facility in which single heater rods can be tested in annular geometry; and an air-water loop which is used to evaluate two-phase flow-measuring instrumentation

  7. Clinical Investigation Program. Annual Progress Report. Volume 1

    Science.gov (United States)

    1994-01-20

    Components Surgical Day, Bethesda, MD, in April 1993. 2. Planned for FY-94 The Department of Clinical Investigation hopes to maintain the essence of the...sclerosing cholangitis after choledochojejun- ostomy : radiographic and biochemical improvement with antibiotic therapN. Am J Gastroenterol 1993;88:1635

  8. Oak Ridge Reservation Federal Facility Agreement for the Environmental Restoration Program. Volume 1, Quarterly report, October--December 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-01

    This Oak Ridge Reservation Federal Facility Agreement Quarterly Report for the Environmental Restoration Program was prepared to satisfy requirements for progress reporting on Environmental Restoration Program (ER) activities as specified in the Oak Ridge Reservation Federal Facility Agreement (FFA) established between the US Department of Energy (DOE), the US Environmental Protection Agency, and the Tennessee Department of Environment and Conservation. The reporting period covered in this document is October through December 1995. This work was performed under Work Breakdown Structure 1.4.12.2.3.04 (Activity Data Sheet 8304). Publication of this document meets two FFA milestones. The FFA Quarterly Report meets an FFA milestone defined as 30 days following the end of the applicable reporting period. Appendix A of this report meets the FFA milestone for the Annual Removal Action Report for the period FYs 1991--95. This document provides information about ER Program activities conducted on the Oak Ridge Reservation under the FFA. Specifically, it includes information on milestones scheduled for completion during the reporting period, as well as scheduled for completion during the next reporting period (quarter); accomplishments of the ER Program; concerns related to program work; and scheduled activities for the next quarter. It also provides a listing of the identity and assigned tasks of contractors performing ER Program work under the FFA.

  9. Final work plan : Phase I investigation of potential contamination at the former CCC/USDA grain storage facility in Savannah, Missouri.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M.; Environmental Science Division

    2007-10-12

    . This work will be performed in accord with the Intergovernmental Agreement established between the Farm Service Agency of the USDA and MoDNR, to address carbon tetrachloride contamination potentially associated with a number of former CCC/USDA grain storage facilities in Missouri. The investigative activities at Savannah will be conducted on behalf of the CCC/USDA by the Environmental Science Division of Argonne National Laboratory. Argonne is a nonprofit, multidisciplinary research center operated by UChicago Argonne, LLC, for the U.S. Department of Energy (DOE). The CCC/USDA has entered into an agreement with the DOE, under which Argonne provides technical assistance to the CCC/USDA with environmental site characterization and remediation at its former grain storage facilities. The site characterization at Savannah will take place in phases. This approach is recommended by the CCC/USDA and Argonne, so that information obtained and interpretations developed during each incremental stage of the investigation can be used most effectively to guide subsequent phases of the program. This site-specific Work Plan outlines the specific technical objectives and scope of work proposed for Phase I of the Savannah investigation. This Work Plan also includes the community relations plan to be followed throughout the CCC/USDA program at the Savannah site. Argonne is developing a Master Work Plan specific to operations in the state of Missouri. In the meantime, Argonne will issue a Provisional Master Work Plan (PMWP; Argonne 2007) that will be submitted to the MoDNR for review and approval. The agency has already reviewed and approved (with minor changes) the present Master Work Plan (Argonne 2002) under which Argonne currently operates in Kansas. The PMWP (Argonne 2007) will provide detailed information and guidance on the investigative technologies, analytical methodologies, quality assurance-quality control measures, and general health and safety policies to be employed by

  10. Final work plan : phase I investigation of potential contamination at the former CCC/USDA grain storage facility in Montgomery City, Missouri.

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, L. M.; Environmental Science Division

    2010-08-16

    former grain storage facility, the CCC/USDA will conduct investigations to (1) characterize the source(s), extent, and factors controlling the possible subsurface distribution and movement of carbon tetrachloride at the Montgomery City site and (2) evaluate the health and environmental threats potentially represented by the contamination. This work will be performed in accord with the Intergovernmental Agreement established between the Farm Service Agency of the USDA and the MoDNR, to address carbon tetrachloride contamination potentially associated with a number of former CCC/USDA grain storage facilities in Missouri. The investigations at Montgomery City will be conducted on behalf of the CCC/USDA by the Environmental Science Division of Argonne National Laboratory. Argonne is a nonprofit, multidisciplinary research center operated by UChicago Argonne, LLC, for the U.S. Department of Energy (DOE). The CCC/USDA has entered into an agreement with DOE, under which Argonne provides technical assistance to the CCC/USDA with environmental site characterization and remediation at its former grain storage facilities. The site characterization at Montgomery City will take place in phases. This approach is recommended by the CCC/USDA and Argonne, so that information obtained and interpretations developed during each incremental stage of the investigation can be used most effectively to guide subsequent phases of the program. This site-specific Work Plan outlines the specific technical objectives and scope of work proposed for Phase I of the Montgomery City investigation. This Work Plan also includes the community relations plan to be followed throughout the CCC/USDA program at the Montgomery City site. Argonne is developing a Master Work Plan specific to operations in the state of Missouri. In the meantime, Argonne has issued a Provisional Master Work Plan (PMWP; Argonne 2007) that has been reviewed and approved by the MoDNR for current use. The PMWP (Argonne 2007) provides

  11. Experimental investigation on the behaviour of pressure suppression containment systems by the SOPRE-1 facility

    International Nuclear Information System (INIS)

    Cerullo, N.; Delli Gatti, A.; Marinelli, M.; Mazzini, M.; Mazzoni, A.; Sbrana, A.; Todisco, P.

    1977-01-01

    The SOPRE-1 test facility is an integral model (scale 1:13) of a MARK II pressure suppression containment system. It was set up at the University of Pisa in order to study the pressure-temperature transient in pressure suppression containment systems during LOCAs. Knowledge of this transient is necessary to perform a correct structural analysis of reactor containment. The containment system behaviour is studied by changing the principal parameters which affect the transient (blow-down mass and energy release, suppression pool water temperature, vent pipe number and submergence heat transfer coefficients). The first series of tests involved: A) 13 tests with break area of 1.8 cm 2 , B) 8 tests with break area of 20.0 cm 2 . The following experimental conditions were changed: - position of the simulated break (from liquid or steam zone), - water pressure (20-85 Kgsub(p)/cm 2 ) and mass (45-70Kg) in the vessel model. Tests A): the CONTEMPT codes correctly forecast the pressure-temperature history, both in dry- and in wet-well. Tests B): the experimental runs have shown that increasing of blow-down flowrate produces dry-well pressure spatial differences and anomalous vent pipe behaviour. This results in damped oscillations of dry- and wet-well pressure, probably due to alterbating air bubble over-expansion and collapse, and in vent pipe opening and reclosing. (Auth.)

  12. Facile synthesis of S, N co-doped carbon dots and investigation of their photoluminescence properties.

    Science.gov (United States)

    Zhang, Yue; He, Junhui

    2015-08-21

    A facile one-pot approach to prepare photoluminescent carbon dots (CDs) was developed through hydrothermal treatment of cysteine and citric acid. The obtained CDs show stable and bright blue emission with a quantum yield of 54% and an average lifetime of 11.61 ns. Moreover, the two-photon induced upconversion fluorescence of the CDs was observed and demonstrated. Interestingly, both down and up conversion fluorescence of the CDs show excitation-independent emission, which is quite different from most of the previously reported CDs. Ultrafast spectroscopy was also employed here to study the photoluminescence (PL) properties of the CDs. After characterization using various spectroscopic techniques, a unique PL mechanism for the as-prepared CDs' fluorescence was proposed accordingly. In addition, the influence of various metal ions on the CD fluorescence was examined and no quenching phenomena were observed. Meanwhile, gold nanoparticles (Au NPs) were found to be good quenchers of CD fluorescence and their quenching behavior was fitted to the Stern-Volmer equation. This provides new opportunities for fluorescence sensor designs and light energy conversion applications. Finally, the as-prepared CDs were inkjet-printed to form a desirable pattern, which is useful for fluorescent patterns, and anti-counterfeiting labeling.

  13. Chlorine-36 investigations of groundwater infiltration in the Exploratory Studies Facility at Yucca Mountain, Nevada

    International Nuclear Information System (INIS)

    Levy, S.S.; Fabryka-Martin, J.T.; Dixon, P.R.; Liu, B.; Turin, H.J.; Wolfsberg, A.V.

    1997-01-01

    Chlorine-36, including the natural cosmogenic component and the component produced during atmospheric nuclear testing in the 1950's and 1960's (bomb pulse), is being used as an isotopic tracer for groundwater infiltration studies at Yucca Mountain, a potential nuclear waste repository. Rock samples have been collected systematically in the Exploratory Studies Facility (ESF), and samples were also collected from fractures, faults, and breccia zones. Isotopic ratios indicative of bomb-pulse components in the water ( 36 Cl/Cl values > 1,250 x 10 -15 ), signifying less than 40-yr travel times from the surface, have been detected at a few locations within the Topopah Spring Tuff, the candidate host rock for the repository. The specific features associated with the high 36 Cl/Cl values are predominantly cooling joints and syngenetic breccias, but most of the sites are in the general vicinity of faults. The non-bomb pulse samples have 36 Cl/Cl values interpreted to indicate groundwater travel times of at least a few thousand to possibly several hundred thousand years. Preliminary numerical solute-travel experiments using the FEHM (Finite Element Heat and Mass transfer) code demonstrate consistency between these interpreted ages and the observed 36 Cl/Cl values but do not validate the interpretations

  14. Investigation of small break loss-of-coolant phenomena in a small scale nonnuclear test facility

    International Nuclear Information System (INIS)

    Cozzuol, J.M.; Fauble, T.J.; Harvego, E.A.

    1980-01-01

    A small-scale nonnuclear integral test facility designed to simulate a pressurized water reactor (PWR) system was used to evaluate the effects of a small break loss-of-coolant accident (LOCA) on the system thermal-hydraulic response. The experiment approximated a 2.5% (11-cm diameter) communicative break in the cold leg of a PWR, and included initial conditions which were similar to conditions in a PWR operating at full power. The 2.5% break size ensured that the nominal break flow rate was greater than the high pressure injection system (HPIS) flow rate, thus providing the potential for a continuous system depressurization. The sequence of events was similar to that used in evaluation model analysis of small break loss-of-coolant accidents, and included simulated reactor scram and loss of offsite power. Comparisions of experimental data with computer code calculations are used to demonstrate the capabilities and limitations of integral system calculations used to predict phenomena which can be important in the assessment of a small break LOCA in a PWR

  15. Radiation-induced bystander effects. Mechanisms, biological implications, and current investigations at the Leipzig LIPSION facility

    International Nuclear Information System (INIS)

    Oesterreicher, J.; Prise, K.M.; Michael, B.D.; Vogt, J.; Butz, T.; Tanner, J.M.

    2003-01-01

    Background: The bystander effect is a relatively new area of radiobiological research, which is aimed at studying post-radiation changes in neighboring non-hit cells or tissues. The bystander effect of ionizing irradiation is important after low-dose irradiation in the range of up to 0.2 Gy, where a higher incidence of stochastic damage was observed than was expected from a linear-quadratic model. It is also important when the irradiation of a cell population is highly non-uniform. Objective: This review summarizes most of the important results and proposed bystander effect mechanisms as well as their impact on theory and clinical practice. The literature, in parts contradictory, is collected, the main topics are outlined, and some basic papers are described in more detail. In order to illustrate the microbeam technique, which is considered relevant for the bystander effect research, the state of the Leipzig LIPSION nanoprobe facility is described. Results: The existence of a radiation-induced bystander effect is now generally accepted. The current state of knowledge on it is summarized here. Several groups worldwide are working on understanding its different aspects and its impact on radiobiology and radiation protection. Conclusion: The observation of a bystander effect has posed many questions, and answering them is a challenging topic for radiobiology in the future. (orig.)

  16. Radiation-induced bystander effects. Mechanisms, biological implications, and current investigations at the Leipzig LIPSION facility

    Energy Technology Data Exchange (ETDEWEB)

    Oesterreicher, J. [Dept. of Nuclear Solid State Physics, Univ. of Leipzig (Germany); Dept. of Radiobiology and Immunology, Purkyne Military Medical Academy, Hradec Kralove (Czech Republic); Prise, K.M.; Michael, B.D. [Gray Cancer Inst., Mount Vernon Hospital, Northwood, Middlesex (United Kingdom); Vogt, J.; Butz, T. [Dept. of Nuclear Solid State Physics, Univ. of Leipzig (Germany); Tanner, J.M. [Clinic and Polyclinic of Radiation Oncology, Martin Luther Univ. Halle-Wittenberg (Germany)

    2003-02-01

    Background: The bystander effect is a relatively new area of radiobiological research, which is aimed at studying post-radiation changes in neighboring non-hit cells or tissues. The bystander effect of ionizing irradiation is important after low-dose irradiation in the range of up to 0.2 Gy, where a higher incidence of stochastic damage was observed than was expected from a linear-quadratic model. It is also important when the irradiation of a cell population is highly non-uniform. Objective: This review summarizes most of the important results and proposed bystander effect mechanisms as well as their impact on theory and clinical practice. The literature, in parts contradictory, is collected, the main topics are outlined, and some basic papers are described in more detail. In order to illustrate the microbeam technique, which is considered relevant for the bystander effect research, the state of the Leipzig LIPSION nanoprobe facility is described. Results: The existence of a radiation-induced bystander effect is now generally accepted. The current state of knowledge on it is summarized here. Several groups worldwide are working on understanding its different aspects and its impact on radiobiology and radiation protection. Conclusion: The observation of a bystander effect has posed many questions, and answering them is a challenging topic for radiobiology in the future. (orig.)

  17. Investigation of public exposure resulted from the radioiodine delay tank facility of nuclear medicine department

    Energy Technology Data Exchange (ETDEWEB)

    Yusof, Mohd Fahmi Mohd, E-mail: mfahmi@usm.my; Ali, Abdul Muhaimin Mat; Abdullah, Reduan; Idris, Abdullah Waidi [School of Health Sciences, Universiti Sains Malaysia, 16150 Kota Bharu, Kelantan (Malaysia)

    2016-01-22

    The study is carried out to assess the exposure rate that could contribute to public exposure in a radioiodine ward delay tank facility of Radiotherapy, Oncology and Nuclear Medicine, Department, Hospital Universiti Sains Malaysia (HUSM). The exposure rate at several locations including the delay tank room, doorway and at the public walking route was measured using Victoreen 415P-RYR survey meter. The radioactive level of the {sup 131}I waste was measured using Captus 3000 well counting system. The results showed that exposure rate and total count of the delay tank sample increased when the radioiodine ward was fully occupied with patient and reduced when the ward was vacant. Occupancy of radioiodine ward for two consecutive weeks had dramatically increased the exposure rate around the delay tank and radioactive level of {sup 131}I waste. The highest exposure rate and radioactive level was recorded when the ward was occupied for two consecutive weeks with 177.00 µR/h and 58.36 kcpm respectively. The exposure rate decreased 15.76 % when the door of the delay tank room was closed. The exposure rate at public walking route decreased between 15.58 % and 36.92 % as the distance increased between 1 and 3 m.

  18. Stacking faults enriched silver nanowires: facile synthesis, catalysis and SERS investigations.

    Science.gov (United States)

    Xu, Minmin; Yang, Fengzhu; Yuan, Yaxian; Guo, Qinghua; Ren, Bin; Yao, Jianlin; Gu, Renao

    2013-10-01

    A facile approach based on seed-mediated method for synthesis of stacking faults enriched Ag nanowires (SFEANWs) was successfully developed. SFEANWs were formed and attached onto the seed (α-Fe2O3/Au) surfaces through the reduction of AgNO3 by ascorbic acid (AA) in the presence of sodium polyacrylate (PAANa). Their length can be tuned with different concentrations of AgNO3 or PAANa. According to the effects of seeds and PAANa, the plausible growth mechanism of SFEANWs was discussed. The catalytic activity of SFEANWs comparing with fivefold twinned Ag nanowires (FFTANWs) was evaluated through reducing p-nitrophenol by NaBH4. The activation energy of the classical reaction catalyzed by SFEANWs was calculated through the Arrhenius equation. In addition, these SFEANWs exhibited excellent surface enhanced Raman scattering (SERS) activities due to the hot spots located in the cross of the twist wires. The detection limit of by SERS for 1,4-benzenedithiol (1,4-BDT) was estimated about 10(-7) mol/L. Copyright © 2013 Elsevier Inc. All rights reserved.

  19. Research Program to Investigate the Fundamental Chemistry of Technetium

    International Nuclear Information System (INIS)

    Edelstein, Norman M.; Burns, Carol J.; Shuh, David D.; Lukens, Wayne

    2000-01-01

    Technetium (99Tc, half-life = 2.13x105 years, b-emitter) is one of the radionuclides of major concern for nuclear waste disposal. This concern is due to the long half-life of 99Tc, the ease with which pertechnetate, TcO4 -, migrates in the geosphere, and the corresponding regulatory considerations. The problem of mobility of pertechnetate in the environment is compounded by the fact that pertechnetate is the thermodynamically stable form of technetium in aerobic environments. These two factors present challenges for the safe, long term immobilization of technetium in waste forms. Because of the stability of pertechnetate, technetium has been assumed to exist as pertechnetate in the aqueous phase of nuclear waste tanks. However, recent studies indicate that a significant fraction of the technetium is in a different chemical form. This program addresses the fundamental solution chemistry of technetium in the waste tank environment, and in a second part, the stability of technetium in various waste forms. The chemistry of this element will be studied in aqueous solutions at high pH, with various added salts such as nitrate, nitrite, and organic complexants, and as a function of radiation dose, to determine whether radiolysis effects can reduce TcO4 -. A separate facet of this research is the search for chemical forms of technetium that may be thermodynamically and/or kinetically stable and may be incorporated in various waste forms for long term storage. This phase of the program will address the problem of the possible oxidation of lower valent technetium species in various waste form matrices and the subsequent leaching of the highly soluble TcO4 -

  20. RCRA facility investigation/corrective measures study work plan for the 100-HR-1 operable unit, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1992-09-01

    Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US. Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order, signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-HR-1 source operable unit. Source operable units include facilities and unplanned release sites that are potential sources of contamination. The 100-HR-3 operable unit underlies the D/DR and H Areas, the 600 Area between them, and the six source operable units these areas contain. The 100-HR-3 operable unit includes all contamination found in the aquifer soils and water within its boundary. Separate work plans have been initiated for the 100-HR-3 groundwater operable unit (DOE-RL 1992a) and the 100-DR-1 (DOE-RL 1992b) source operable units

  1. Clinical Investigation Program RCS-MED-300 (R1)

    Science.gov (United States)

    1988-09-30

    deprivation noted in the history or physical. Subjects agree to participate in the study. The independent variable is touch which if present is administered...INVESTIGATORS: MAJ Lynn Whittington , MC KEY WORDS: Intubation, pediatric training Study Objective: This training is designed to teach physicians and other health...with a high stress job are medical interns. Interns are sleep deprived , eat poorly, and have a high degree of emotional stress due to the novelty of

  2. Young Investigator Program: Modular Paradigm for Scalable Quantum Information

    Science.gov (United States)

    2016-03-04

    actuator When both direct driving and a quantum controller are available, one can take advantage of both to achieve faster driving of the qubit. In...pointing to advantages to be found in particular geometries for larger quantum information architectures. • We investigated the effect of dephasing and...Montangero, T. Calarco, F. Nori, and M. B. Plenio, “Scal- able quantum computation via local control of only two qubits,” Phys. Rev. A, vol. 81, no. 4, p

  3. I Scratch and Sense but Can I Program? An Investigation of Learning with a Block Based Programming Language

    Science.gov (United States)

    Simpkins, N. K.

    2014-01-01

    This article reports an investigation into undergraduate student experiences and views of a visual or "blocks" based programming language and its environment. An additional and central aspect of this enquiry is to substantiate the perceived degree of transferability of programming skills learnt within the visual environment to a typical…

  4. Site study plan for Exploratory shaft facilities design foundation boreholes (shaft surface facility foundation borings), Deaf Smith County Site, Texas: Surface-based geotechnical field program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-12-01

    This site study plan describes the Exploratory Shaft Facilities (ESF) Design Foundation Boreholes field activities to be conducted during early stages of Site Characterization at the Deaf Smith County, Texas, site. The field program has been designed to provide data useful in addressing information/data needs resulting from federal/state/local regulations, and repository program requirements. Approximately 50 foundation boreholes will be drilled within the ESP location to provide data necessary for design of the ESF and to satisfy applicable shaft permitting requirements. Soils and subsurface rock will be sampled as the foundation boreholes are advanced. Soil samples or rock core will be taken through the Blackwater Draw and Ogallala Formations and the Dockum Group. Hydrologic testing will be performed in boreholes that penetrates the water table. In-situ elastic properties will be determined from both the soil strata and rock units along the length of the boreholes. Field methods/tests are chosen that provide the best or only means of obtaining the required data. The Salt Repository Project (SRP) Networks specify the schedule under which the program will operate. Drilling will not begin until after site ground water baseline conditions have been established. The Technical Field Services Contractor is responsible for conducting the field program of drilling and testing. Samples and data will be handled and reported in accordance with established SRP procedures. A quality assurance program will be utilized to assure that activities affecting quality are performed correctly and that the appropriate documentation is maintained. 25 refs., 10 figs., 6 tabs

  5. E-SCAPE: A scale facility for liquid-metal, pool-type reactor thermal hydraulic investigations

    Energy Technology Data Exchange (ETDEWEB)

    Van Tichelen, Katrien, E-mail: kvtichel@sckcen.be [SCK-CEN, Boeretang 200, 2400 Mol (Belgium); Mirelli, Fabio, E-mail: fmirelli@sckcen.be [SCK-CEN, Boeretang 200, 2400 Mol (Belgium); Greco, Matteo, E-mail: mgreco@sckcen.be [SCK-CEN, Boeretang 200, 2400 Mol (Belgium); Viviani, Giorgia, E-mail: giorgiaviviani@gmail.com [University of Pisa, Lungarno Pacinotti 43, 56126 Pisa (Italy)

    2015-08-15

    Highlights: • The E-SCAPE facility is a thermal hydraulic scale model of the MYRRHA fast reactor. • The focus is on mixing and stratification in liquid-metal pool-type reactors. • Forced convection, natural convection and the transition are investigated. • Extensive instrumentation allows validation of computational models. • System thermal hydraulic and CFD models have been used for facility design. - Abstract: MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) is a flexible fast-spectrum research reactor under design at SCK·CEN. MYRRHA is a pool-type reactor with lead bismuth eutectic (LBE) as primary coolant. The proper understanding of the thermal hydraulic phenomena occurring in the reactor pool is an important issue in the design and licensing of the MYRRHA system and liquid-metal cooled reactors by extension. Model experiments are necessary for understanding the physics, for validating experimental tools and to qualify the design for the licensing. The E-SCAPE (European SCAled Pool Experiment) facility at SCK·CEN is a thermal hydraulic 1/6-scale model of the MYRRHA reactor, with an electrical core simulator, cooled by LBE. It provides experimental feedback to the designers on the forced and natural circulation flow patterns. Moreover, it enables to validate the computational methods for their use with LBE. The paper will elaborate on the design of the E-SCAPE facility and its main parameters. Also the experimental matrix and the pre-test analysis using computational fluid dynamics (CFD) and system thermal hydraulics codes will be described.

  6. Insights gained from NRC research investigations at the Maxey Flats LLW SLB facility

    International Nuclear Information System (INIS)

    O'Donnell, E.

    1983-01-01

    The NRC funded program of research at Maxey Flats was done to assist an Agreement State in assessing the performance of the site. That program has yielded both site specific insights and generic insights which are likely to be useful in licensing future sites. They are as follows: Site Specific Insights: (1) The principal pathway of water entry into burial trenches at Maxey Flats is through the trench caps. (2) Sampling of vegetation, soils, and streams adjoining the site indicates that the small but measureable amounts of radionuclides found offsite were from surface runoff or the site evaporator. (3) There is limited onsite subsurface movement of radionuclides where open fractures intersect burial trenches. Generic Insights: (1) Tritium in the plant transpiration stream appears useful for mapping trench boundaries. (2) Trees offer a promising means of monitoring subsurface radionuclide movement in fractured rocks of low permeability. (3) Complexing with EDTA appears to be a potentially important mechanism that increases mobility of such radionuclides as Co-60, Pu-238, Am-241, and Sr-90. (4) Changes in soil solution chemistry encountered as leachate moves from trenches generally reduce the solubility of migrating radionuclides. (5) Agronomic management techniques appear promising as a means to control deep water percolation through waste burial trench caps. 18 references

  7. TAMU-TRAP facility - program for the study of fundamental weak interaction

    International Nuclear Information System (INIS)

    Shidling, P.D.; Mehlman, M.; Melconian, Dan; Fenker, Ben; Behling, R.S.

    2012-01-01

    Primary goal of the TAMU-TRAP facility is to test the Standard Model (SM) for a possible admixture of a scalar (S) or tensor (T) type of interaction in T = 2 superallowed β-delayed proton emitters. This information will be inferred from the shape of the proton energy spectrum. The main component of the facility are an RFQ cooler/buncher for cooling and bunching the ions, a Penning trap system with two cylindrical Penning traps. Additional goals for this system are mass measurements, lifetime measurements, and ft-values. A brief overview of the TAMU-TRAP set-up and T-REX upgrade facility will be presented. (author)

  8. Biological investigations of the Sandia National Laboratories Sol se Mete Aerial Cable Facility

    Energy Technology Data Exchange (ETDEWEB)

    Sullivan, R.M.

    1994-10-01

    This report provides results of a comprehensive biological field survey performed on the Sandia National Laboratories Aerial Cable Facility, at the east end of Kirtland Air Force Base (KAFB), Bernalillo County, New Mexico. This survey was conducted late September through October, 1991. ACF occupies a 440-acre tract of land withdrawn by the US Forest Service (USFS) for use by KAFB, and in turn placed under operational control of SNL by the Department of Energy (DOE). All land used by SNL for ACF is part of a 15,851-acre tract of land withdrawn by the US Forest Service. In addition, a number of different organizations use the 15,851-acre area. The project area used by SNL encompasses portions of approximately six sections (3,840 acres) of US Forest Service land located within the foothills of the west side of the Manzano Mountains (East Mesa). The biological study area is used by the KAFB, the US Department of Interior, and SNL. This area includes: (1) Sol se Mete Springs and Canyon, (2) East Anchor Access Road, (3) East Anchor Site, (4) Rocket Sled Track, (5) North Arena, (6) East Instrumentation Site and Access Road, (7) West Anchor Access Road, (8) West Anchor Site, (9) South Arena, (10) Winch Sites, (11) West Instrumentation Sites, (12) Explosive Assembly Building, (13) Control Building, (14) Lurance Canyon Road and vicinity. Although portions of approximately 960 acres of withdrawn US Forest Service land have been altered, only 700 acres have been disturbed by activities associated with ACF; approximately 2,880 acres consist of natural habitat. Absence of grazing by livestock and possibly native ungulates, and relative lack of human disturbance have allowed this area to remain in a more natural vegetative state relative to the condition of private range lands throughout New Mexico. This report evaluates threatened and endangered species found on ACF, as well as a comprehensive assessment of biological habitats.

  9. Experimental investigation on the behavior of pressure suppression containment systems by the SOPRE-1 facility

    International Nuclear Information System (INIS)

    Cerullo, N.; Delli Gatti, A.; Marinelli, M.; Mazzini, M.; Mazzoni, A.; Sbrana, A.; Todisco, P.

    1977-01-01

    The SOPRE-1 test facility is an integral model (scale 1:13) of a MARK II pressure suppression containment system. It was set up at the University of Pisa in order to study the pressure-temperature transient in pressure suppression containment systems during LOCAs. Knowledge of this transient is necessary to perform a correct structural analysis of reactor containment. The containment system behavior is studied by changing the principal parameters which affect the transient (blow-down mass and energy release, suppression pool water temperature, vent pipe number and submergence, heat transfer coefficients). The first series of tests involved: A) 13 tests with break area of 1.8 cm 2 , B) 8 tests with break area of 20.0 cm 2 . The following experimental conditions were changed: position of the simulated break (from liquid or steam zone), water pressure (20-85 Kg/cm 2 ) and mass (45-70 Kg) in the vessel model. Tests A): the CONTEMPT codes correctly forecast the pressure-temperature history, both in dry- and in wet-well. Tests B): the experimental runs have shown that increasing of blow-down flowrate produces dry-well pressure spatial differences and anomalous vent pipe behavior. This results in damped oscillations of dry- and wet-well pressure, probably due to alternating air bubble over-expansion and collapse, and in vent pipe opening and reclosing. Dry-well pressure maxima at the end of blow-down are greater than those forecasted by currently applied codes: these codes use an homogeneous model, and do not take into account the above mentioned dynamic phenomena. In some tests other interesting phenomena were observed, such as some local pressure peaks in the suppression pool greater than dry-well pessure maxima at the end of blow-down. At present, all these phenomena are under study; they could be important for the structural analysis of containment systems

  10. LMFBR. Off normal, transient test facilities and programs in the USA

    International Nuclear Information System (INIS)

    Herbst, R.J.

    1985-01-01

    The United States fast breeder reactor development program has included operational transient analyses and experiments to verify the predicted performance of core components. Operational transient testing has focused on off-normal operation during Plant Protection System terminated transient-overpower events. In-pile and out-of-pile tests have been used to simulate predicted thermal and mechanical strain cycles and measure component response. The spectrum of reactivity ramp rates investigated in TOP tests has recently been expanded to include rates of less than $0.1/s. These slow ramp rate studies are being done in cooperation with the Japanese. The US has also cooperated with the UK in the transient testing of Prototype Fast Reactor fuel pins

  11. SU-F-T-169: A Periodic Quality Assurance Program for a Spot-Scanning Proton Treatment Facility

    Energy Technology Data Exchange (ETDEWEB)

    Mundy, D; Tryggestad, E; Beltran, C; Furutani, K; Gilson, G; Ito, S; Johnson, J; Kruse, J; Remmes, N; Tasson, A; Whitaker, T; Herman, M [Mayo Clinic, Rochester, MN (United States)

    2016-06-15

    Purpose: To develop daily and monthly quality assurance (QA) programs in support of a new spot-scanning proton treatment facility using a combination of commercial and custom equipment and software. Emphasis was placed on efficiency and evaluation of key quality parameters. Methods: The daily QA program was developed to test output, spot size and position, proton beam energy, and image guidance using the Sun Nuclear Corporation rf-DQA™3 device and Atlas QA software. The program utilizes standard Atlas linear accelerator tests repurposed for proton measurements and a custom jig for indexing the device to the treatment couch. The monthly QA program was designed to test mechanical performance, image quality, radiation quality, isocenter coincidence, and safety features. Many of these tests are similar to linear accelerator QA counterparts, but many require customized test design and equipment. Coincidence of imaging, laser marker, mechanical, and radiation isocenters, for instance, is verified using a custom film-based device devised and manufactured at our facility. Proton spot size and position as a function of energy are verified using a custom spot pattern incident on film and analysis software developed in-house. More details concerning the equipment and software developed for monthly QA are included in the supporting document. Thresholds for daily and monthly tests were established via perturbation analysis, early experience, and/or proton system specifications and associated acceptance test results. Results: The periodic QA program described here has been in effect for approximately 9 months and has proven efficient and sensitive to sub-clinical variations in treatment delivery characteristics. Conclusion: Tools and professional guidelines for periodic proton system QA are not as well developed as their photon and electron counterparts. The program described here efficiently evaluates key quality parameters and, while specific to the needs of our facility

  12. SU-F-T-169: A Periodic Quality Assurance Program for a Spot-Scanning Proton Treatment Facility

    International Nuclear Information System (INIS)

    Mundy, D; Tryggestad, E; Beltran, C; Furutani, K; Gilson, G; Ito, S; Johnson, J; Kruse, J; Remmes, N; Tasson, A; Whitaker, T; Herman, M

    2016-01-01

    Purpose: To develop daily and monthly quality assurance (QA) programs in support of a new spot-scanning proton treatment facility using a combination of commercial and custom equipment and software. Emphasis was placed on efficiency and evaluation of key quality parameters. Methods: The daily QA program was developed to test output, spot size and position, proton beam energy, and image guidance using the Sun Nuclear Corporation rf-DQA™3 device and Atlas QA software. The program utilizes standard Atlas linear accelerator tests repurposed for proton measurements and a custom jig for indexing the device to the treatment couch. The monthly QA program was designed to test mechanical performance, image quality, radiation quality, isocenter coincidence, and safety features. Many of these tests are similar to linear accelerator QA counterparts, but many require customized test design and equipment. Coincidence of imaging, laser marker, mechanical, and radiation isocenters, for instance, is verified using a custom film-based device devised and manufactured at our facility. Proton spot size and position as a function of energy are verified using a custom spot pattern incident on film and analysis software developed in-house. More details concerning the equipment and software developed for monthly QA are included in the supporting document. Thresholds for daily and monthly tests were established via perturbation analysis, early experience, and/or proton system specifications and associated acceptance test results. Results: The periodic QA program described here has been in effect for approximately 9 months and has proven efficient and sensitive to sub-clinical variations in treatment delivery characteristics. Conclusion: Tools and professional guidelines for periodic proton system QA are not as well developed as their photon and electron counterparts. The program described here efficiently evaluates key quality parameters and, while specific to the needs of our facility

  13. Technical Approach and Plan for Transitioning Spent Nuclear Fuel (SNF) Project Facilities to the Environmental Restoration Program

    International Nuclear Information System (INIS)

    SKELLY, W.A.

    1999-01-01

    This document describes the approach and process in which the 100-K Area Facilities are to be deactivated and transitioned over to the Environmental Restoration Program after spent nuclear fuel has been removed from the K Basins. It describes the Transition Project's scope and objectives, work breakdown structure, activity planning, estimated cost, and schedule. This report will be utilized as a planning document for project management and control and to communicate details of project content and integration

  14. Investigation of ADAMO performance in the ZEUS calorimeter reconstruction program

    International Nuclear Information System (INIS)

    Kowalski, H.; Poser, T.; Stanco, L.; Tscheslog, E.

    1989-01-01

    The ADAMO package has been investigated for the reconstruction of jets simulated in the ZEUS calorimeter. The feasibility of ADAMO routines was tested under various aspects. The study was based on different versions of a cluster algorithm using ADAMO tools or direct BOS memory management tools. In particular, the amount of CPU time needed by each of the versions was determined. Results are quite promising and support an extensive use of the ADAMO package in the software development of high energy physics experiments. (orig.)

  15. Investigating GEAR-Up College Readiness Program's Influence on Postsecondary Decisions of Rural Hispanic Youth

    Science.gov (United States)

    Boydstun, Kelli Dawn

    2016-01-01

    This qualitative case study investigated how the GEAR-Up college readiness program influenced the postsecondary decisions of Hispanic students who participated in the GEAR-Up program for the recommended six-year period in a rural school district in Texas. It was not known how long-term participation in the GEAR-Up program at a rural school…

  16. The U.S. DOE new production reactor/heavy water reactor facility pollution prevention/waste minimization program

    International Nuclear Information System (INIS)

    Kaczmarsky, Myron M.; Tsang, Irving; Stepien, Walter P.

    1992-01-01

    A Pollution Prevention/Waste Minimization Program was established during the early design phase of the U.S. DOE's New Production Reactor/Heavy Water Reactor Facility (NPR/HWRF) to encompass design, construction, operation and decommissioning. The primary emphasis of the program was given to waste elimination, source reduction and/or recycling to minimize the quantity and toxicity of material before it enters the waste stream for treatment or disposal. The paper discusses the regulatory and programmatic background as it applies to the NPR/HWRF and the waste assessment program developed as a phased approach to pollution prevention/waste minimization for the NPR/HWRF. Implementation of the program will be based on various factors including life cycle cost analysis, which will include costs associated with personnel, record keeping, transportation, pollution control equipment, treatment, storage, disposal, liability, compliance and oversight. (author)

  17. A proposed emergency management program for acute care facilities in response to a highly virulent infectious disease.

    Science.gov (United States)

    Petinaux, Bruno; Ferguson, Brandy; Walker, Milena; Lee, Yeo-Jin; Little, Gary; Parenti, David; Simon, Gary

    2016-01-01

    To address the organizational complexities associated with a highly virulent infectious disease (HVID) hazard, such as Ebola Virus Disease (EVD), an acute care facility should institute an emergency management program rooted in the fundamentals of mitigation, preparedness, response, and recovery. This program must address all known facets of the care of a patient with HVID, from unannounced arrival to discharge. The implementation of such a program not only serves to mitigate the risks from an unrecognized exposure but also serves to prepare the organization and its staff to provide for a safe response, and ensure a full recovery. Much of this program is based on education, training, and infection control measures along with resourcing for appropriate personal protective equipment which is instrumental in ensuring an organized and safe response of the acute care facility in the service to the community. This emergency management program approach can serve as a model in the care of not only current HVIDs such as EVD but also future presentations in our healthcare setting.

  18. How to implement security controls for an information security program at CBRN facilities

    International Nuclear Information System (INIS)

    Lenaeus, Joseph D.; O'Neil, Lori Ross; Leitch, Rosalyn M.; Glantz, Clifford S.; Landine, Guy P.; Bryant, Janet L.; Lewis, John; Mathers, Gemma; Rodger, Robert; Johnson, Christopher

    2015-01-01

    This document was prepared by PNNL within the framework of Project 19 of the European Union Chemical Biological Radiological and Nuclear Risk Mitigation Centres of Excellence Initiative entitled, ''Development of procedures and guidelines to create and improve secure information management systems and data exchange mechanisms for CBRN materials under regulatory control.'' It provides management and workers at CBRN facilities, parent organization managers responsible for those facilities, and regulatory agencies (governmental and nongovernmental) with guidance on the best practices for protecting information security. The security mitigation approaches presented in this document were chosen because they present generally accepted guidance in an easy-to-understand manner, making it easier for facility personnel to grasp key concepts and envision how security controls could be implemented by the facility. This guidance is presented from a risk management perspective.

  19. Power Burst Facility/Boron Neutron Capture Therapy Program for cancer treatment

    Energy Technology Data Exchange (ETDEWEB)

    Ackermann, A.L. (ed.); Dorn, R.V. III.

    1990-09-01

    This monthly bulletin describes activities in the following project areas during this reporting period: supporting technology development, large animal model studies, neutron source and facility preparation, administration and common support, and PBF operations. (FI)

  20. How to implement security controls for an information security program at CBRN facilities

    Energy Technology Data Exchange (ETDEWEB)

    Lenaeus, Joseph D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); O' Neil, Lori Ross [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Leitch, Rosalyn M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Glantz, Clifford S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Landine, Guy P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Bryant, Janet L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lewis, John [National Nuclear Lab., Workington (United Kingdom); Mathers, Gemma [National Nuclear Lab., Workington (United Kingdom); Rodger, Robert [National Nuclear Lab., Workington (United Kingdom); Johnson, Christopher [National Nuclear Lab., Workington (United Kingdom)

    2015-12-01

    This document was prepared by PNNL within the framework of Project 19 of the European Union Chemical Biological Radiological and Nuclear Risk Mitigation Centres of Excellence Initiative entitled, ''Development of procedures and guidelines to create and improve secure information management systems and data exchange mechanisms for CBRN materials under regulatory control.'' It provides management and workers at CBRN facilities, parent organization managers responsible for those facilities, and regulatory agencies (governmental and nongovernmental) with guidance on the best practices for protecting information security. The security mitigation approaches presented in this document were chosen because they present generally accepted guidance in an easy-to-understand manner, making it easier for facility personnel to grasp key concepts and envision how security controls could be implemented by the facility. This guidance is presented from a risk management perspective.

  1. Appendix E: Supplemental Risk Management Program Guidance for Ammonia Refrigeration Facilities

    Science.gov (United States)

    Additional information for food processors, food distributors, refrigerated warehouses, and any other facility that has an ammonia refrigeration system. Includes details on exemption for farms, threshold quantity, and offsite consequence analysis.

  2. Annual summary report on surveillance and maintenance activities of the surplus contaminated facilities program at Oak Ridge National Laboratory for period ending September 30, 1991

    International Nuclear Information System (INIS)

    Cannon, T.R.; Ford, M.K.; Holder, L. Jr.

    1991-09-01

    The Surplus Contaminated Facilities Program (SCFP) was established at the Oak Ridge National Laboratory (ORNL) in 1985 to provide support for inactive contaminated facilities that were largely abandoned by the programs which they formerly served. This support provides for routine surveillance and maintenance (S ampersand M) and special projects beyond a routine nature when such actions are needed to ensure adequate protection of personnel or the environment. The facilities included in the program had been used for research, technology development, isotope production and processing, and waste management. Support for facilities in the SCFP has previously been provided by the Department of Energy's (DOE's) Office of Energy Research: Multiprogram Energy Laboratories -- Facilities Support (ERKG) because of multiprogram use of the facilities or because of the landlord responsibility of Energy Research. Recently, an integrated Decontamination and Decommissioning (D ampersand D) program within the DOE Office of Environmental Restoration and Waste Management has been established to collectively manage the former Surplus Facilities Management Program, Defense D ampersand D Program, and the KG-funded, ORNL-originated SCFP. This report gives an overview of the S ampersand M planning, routine S ampersand M, and special maintenance project activities which have occurred at the SCFP facilities during the 1991 Fiscal Year

  3. Investigating the Optimal Management Strategy for a Healthcare Facility Maintenance Program

    Science.gov (United States)

    2004-03-01

    studying those phenomena in all their complexity (Leedy and Ormrod, 2001). According to Denzin and Lincoln (1994), qualitative research emphasizes...Ends process when marginal improvement becomes small. 35 Research Design Methodological Triangulation. Denzin and Lincoln (1994) suggest...holistic view of the setting. This dual view is referred to as methodological triangulation ( Denzin and Lincoln , 1994). A research design develops a

  4. Investigating the Optimal Management Strategy for a Healthcare Facility Maintenance Program

    National Research Council Canada - National Science Library

    Gaillard, Daria

    2004-01-01

    Reacting to the need to transform and the increasing pressure to outsource all non-core activities, Air Force Material Command Surgeon General discontinued its previous use of full service contracts...

  5. Facility Reliability and Maintainability: An Investigation of the Air Force Civil Engineering Recurring Work Program

    Science.gov (United States)

    1989-09-01

    18:2). A recent survey by the Strategic Air Command (SAC) Mechanical Fquipment Management Evaluation Team ( MEMET ) determined that equipment was...identified by MEMET included Maintenance Action Sheets (MAS) that reported work which was not completed, and other MAS which annotated recurring work...readily apparent. Problem Military. The Deputy Chief of Staff for Engineering and Services, HQ SAC, established the MEMET in 1984 in response to a

  6. Microdosimetric investigation of a fast neutron radiobiology facility utilising the d(4)-9Be reaction.

    Science.gov (United States)

    Waker, A J; Maughan, R L

    1986-11-01

    For fast neutron therapy and radiobiology beams, knowledge of the primary neutron spectrum is the most fundamental requirement for the definition of radiation quality. However, microdosimetric measurements in the form of single-event spectra not only complement the primary neutron spectrum as a statement of radiation quality but also provide a sensitive method of detecting changes in the radiation field in situations where it is no longer possible to have precise knowledge of the primary neutron spectrum, for example after collimator changes and in positions where the radiation field consists of a large scattered component. For the various collimator arrangements employed at the Gray Laboratory facility small perturbations of the radiation field are observed which can be related to a softening of the primary neutron spectrum with increasing field size of the collimator. Gamma fraction determinations are in very good agreement with measurements employing the dual chamber technique and also show small changes with collimator field size giving rise to gamma components ranging from 0.09 to 0.12, the higher values being measured for the larger field sizes. Quality changes represented by the shape of the measured event-size spectra and the derived microdosimetric parameters were greatest for off axis and phantom measurements. With increasing depth in water, yD was found to decrease from 47.3 keV micron-1 at 5 cm to 35.6 keV micron-1 at 15 cm depth, and the gamma fraction was found to increase from 0.23 to 0.40. Although there is no generally accepted and agreed method of relating microdosimetric information to biological effectiveness, the dual radiation theory in its original form (Kellerer and Rossi 1972) has been shown to be a very useful model for the assessment of the biological effectiveness of fast neutrons (Kellerer et al 1976). The microdosimetric parameter which is used in the dual radiation model is the dose mean specific energy corrected for saturation zeta

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

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  8. An arc facility for investigating non-LTE thermodynamic and transport phenomena in low and high pressure plasmas

    International Nuclear Information System (INIS)

    Sedghinisab, A.; Eddy, T.L.; Murray, R.T.

    1986-01-01

    This paper discusses a high pressure arc facility modified for computerized control and data acquisition to simplify measurements of non-LTE plasmas. The non-LTE methods have shown that numerous spectral lines and continuum must be accurately, precisely and quickly measured.The instrumentation uses a 1-m monochrometer with programmed wavelength slews and scans; oplasma scans; and monitoring of chamber pressure, current, voltages, and location. Multiple flows of various gases can be provided simultaneously. Plasma self absorption is determined via a concave back mirror and shutter with final alignment via computer plots. The raw data is corrected for absorption, zeroed, centered and smoothed. The net line intensity is then determined and Abeled prior to feeding into LTE or non-LTE analysis methods. Sample results are presented at 0.1,1 and 10 atm

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

    International Nuclear Information System (INIS)

    2001-01-01

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

  10. Remedidal investigation and feasibility study report for the Environmental Restoration Disposal Facility

    International Nuclear Information System (INIS)

    Roeck, F.V.

    1994-06-01

    The purpose of the remedial investigation (RI) is to collect data necessary to adequately characterize the site for the purpose of developing and evaluating effective remedial alternatives. To characterize the site, the lead agency shall, as appropriate, conduct field investigations, including treatability studies, and conduct a baseline risk assessment. The RI provides information to assess the risks to human health and the environment and to support the development, evaluation, and selection of appropriate response alternatives. The primary objective of the feasibility study (FS) is to ensure that appropriate remedial alternatives are developed and evaluated such that relevant information concerning the remedial action options can be presented to a decision-maker and an appropriate remedy selected. The lead agency may develop a feasibility study to address a specific site problem or the entire site. The development and evaluation of alternatives shall reflect the scope and complexity of the remedial action under consideration and the site problems being addressed. Development of alternatives shall be fully integrated with the site characterization activities of the remedial investigation described in paragraph (d) of this section. The lead agency shall include an alternatives screening step, when needed, to select a reasonable number of alternatives for detailed analysis

  11. Remedidal investigation and feasibility study report for the Environmental Restoration Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Roeck, F.V.

    1994-06-01

    The purpose of the remedial investigation (RI) is to collect data necessary to adequately characterize the site for the purpose of developing and evaluating effective remedial alternatives. To characterize the site, the lead agency shall, as appropriate, conduct field investigations, including treatability studies, and conduct a baseline risk assessment. The RI provides information to assess the risks to human health and the environment and to support the development, evaluation, and selection of appropriate response alternatives. The primary objective of the feasibility study (FS) is to ensure that appropriate remedial alternatives are developed and evaluated such that relevant information concerning the remedial action options can be presented to a decision-maker and an appropriate remedy selected. The lead agency may develop a feasibility study to address a specific site problem or the entire site. The development and evaluation of alternatives shall reflect the scope and complexity of the remedial action under consideration and the site problems being addressed. Development of alternatives shall be fully integrated with the site characterization activities of the remedial investigation described in paragraph (d) of this section. The lead agency shall include an alternatives screening step, when needed, to select a reasonable number of alternatives for detailed analysis.

  12. It is possible: availability of lymphedema case management in each health facility in Togo. Program description, evaluation, and lessons learned.

    Science.gov (United States)

    Mathieu, Els; Dorkenoo, Ameyo M; Datagni, Michael; Cantey, Paul T; Morgah, Kodjo; Harvey, Kira; Ziperstein, Joshua; Drexler, Naomi; Chapleau, Gina; Sodahlon, Yao

    2013-07-01

    Lymphatic filariasis (LF) is a vector-borne parasitic disease that can clinically manifest as disabling lymphedema. Although the LF elimination program aims to reduce disability and to interrupt transmission, there has been a scarcity of disease morbidity management programs, particularly on a national scale. This report describes the implementation of the first nationwide LF lymphedema management program. The program, which was initiated in Togo in 2007, focuses on patient behavioral change. Its goal is two-fold: to achieve a sustainable program on a national-scale, and to serve as a model for other countries. The program has five major components: 1) train at least one health staff in lymphedema care in each health facility in Togo; 2) inform people with a swollen leg that care is available at their dispensary; 3) train patients on self-care; 4) provide a support system to motivate patients to continue self-care by training community health workers or family members and providing in home follow-up; and 5) integrate lymphedema management into the curriculum for medical staff. The program achieved the inclusion of lymphedema management in the routine healthcare package. The evaluation after three years estimated that 79% of persons with a swollen leg in Togo were enrolled in the program. The adherence rate to the proposed World Health Organization treatment of washing, exercise, and leg elevation was more than 70% after three years of the program, resulting in a stabilization of the lymphedema stage and a slight decrease in reported acute attacks among program participants. Health staff and patients consider the program successful in reaching and educating the patients. After the external funding ended, the morbidity management program is maintained through routine Ministry of Health activities.

  13. Development of the COMPRE-A Program for Evaluating Proliferation Resistance (PR) and Physical Protection (PP) of the Nuclear Facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Sukhoon; Kim, Juyub; Shin, Kwangyoung [FNC Technology Co., Yongin (Korea, Republic of); Seo, Janghoon; Jang, Sungsoon; Yoo, Hosik [Korea Institute of Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

    2016-10-15

    In order to make up for the limitation inherent in these methodologies, a new methodology called 'Comprehensive Methodology for PR and PP Evaluation (COMPRE)' is being developed by the Korea Institute of Nuclear Non-proliferation and Control (KINAC). Currently, a project for improving a computational program implementing the COMPRE methodology is ongoing in KINAC, and the 'COMPRE-A (i.e. COMPRE-Advanced model)' program was developed as part of this project. This paper describes details of the COMPRE-A program developed for establishing the platform corresponding to features of the evaluation factor derived for COMPRE, and for enhancing easiness of the result analysis through embodying the visualization and comparison tools for the evaluation result. As part of the project for improving a computational program implementing the COMPRE methodology, the COMPRE-A program was developed. This program provides not only the platform corresponding to features of the evaluation factor derived for COMPRE but also the visualization and comparison tools for enhancing easiness of the result analysis. The V and V for the developed program was performed through comparison with the result obtained by using MS-Excel for a sample case consisting of three (3) measures, six (6) sections and twenty-six (26) attributes. From the comparison result, it was confirmed that the risk in aspects of PR and PP at nuclear facilities could be quantitatively evaluated within the acceptable range using the COMPRE-A program.

  14. Investigation of the radionuclide inventory and the production yields of the target stacks at the PEFP radioisotope production facility

    International Nuclear Information System (INIS)

    Yoon, Sang-Pil; Hong, In-Seok; Cho, Yong-Sub

    2010-01-01

    The Proton Engineering Frontier Project (PEFP) will construct a radioisotope production facility by using the nuclear reaction between the 100-MeV proton beam and the solid target. For investigating the radionuclide inventory and the production yield of the radioisotope production facility, we have optimized the thickness of the prototype target stacks by using a SRIM calculation. The target stacks consist of RbCl encapsulated in inconel alloy, Zn metal, and Ga metal encapsulated in niobium. Typical beam parameters were 300 μA and 95 hours. An inventory of all generated radionuclide activities is mandatory in order to prepare the operation scenario and design the hot cell. The Monte Carlo code MCNPX was used to investigate what radionuclide is generated. The obtained radionuclide inventory indicated that about 100 radionuclides were generated and that the total radioactivity of the irradiated target stacks was 1324.1 Ci at the end of the bombardment. The production yields of Sr-82, Cu-67, and Ge-68 were 3.79 Ci, 2.74 Ci, and 1.23 Ci at the end of the bombardment.

  15. Investigation of accident management procedures related to loss of feedwater and station blackout in PSB-VVER integral test facility

    Energy Technology Data Exchange (ETDEWEB)

    Bucalossi, A. [EC JRC, (JRC F.5) PO Box 2, 1755 ZG Petten (Netherlands); Del Nevo, A., E-mail: alessandro.delnevo@enea.it [ENEA, C.R. Brasimone, 40032 Camugnano (Italy); Moretti, F.; D' Auria, F. [GRNSPG, Universita di Pisa, via Diotisalvi 2, 56100 Pisa (Italy); Elkin, I.V.; Melikhov, O.I. [Electrogorsk Research and Engineering Centre, Electrogorsk, Moscow Region (Russian Federation)

    2012-09-15

    Highlights: Black-Right-Pointing-Pointer Four integral test facility experiments related to VVER-1000 reactor. Black-Right-Pointing-Pointer TH response of the VVER-1000 primary system following total loss of feedwater and station blackout scenarios. Black-Right-Pointing-Pointer Accident management procedures in case of total loss of feedwater and station blackout. Black-Right-Pointing-Pointer Experimental data represent an improvement of existing database for TH code validation. - Abstract: VVER 1000 reactors have some unique and specific features (e.g. large primary and secondary side fluid inventory, horizontal steam generators, core design) that require dedicated experimental and analytical analyses in order to assess the performance of safety systems and the effectiveness of possible accident management strategies. The European Commission funded project 'TACIS 2.03/97', Part A, provided valuable experimental data from the large-scale (1:300) PSB-VVER test facility, investigating accident management procedures in VVER-1000 reactor. A test matrix was developed at University of Pisa (responsible of the project) with the objective of obtaining the experimental data not covered by the OECD VVER validation matrix and with main focus on accident management procedures. Scenarios related to total loss of feed water and station blackout are investigated by means of four experiments accounting for different countermeasures, based on secondary cooling strategies and primary feed and bleed procedures. The transients are analyzed thoroughly focusing on the identification of phenomena that will challenge the code models during the simulations.

  16. Report of an investigation into deterioration of the Plutonium Fuel Form Fabrication Facility (PuFF) at the DOE Savannah River Site

    International Nuclear Information System (INIS)

    1991-10-01

    This investigations of the Savannah River Site's Plutonium Fuel Form fabrication facility located in Building 235-F was initiated in April 1991. The purpose of the investigation was to determine whether, as has been alleged, operation of the facility's argon inert gas system was terminated with the knowledge that continued inoperability of the argon system would cause accelerated corrosion damage to the equipment in the plutonium 238 processing cells. The investigation quickly established that the decision to discontinue operation of the argon system, by not repairing it, was merely one of the measures, and not the most important one, which led to the current deteriorated state of the facility. As a result, the scope of the investigation was broadened to more identify and assess those factors which contributed to the facility's current condition. This document discusses the backgrounds, results, and recommendations of this investigation

  17. Report of an investigation into deterioration of the Plutonium Fuel Form Fabrication Facility (PuFF) at the DOE Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    1991-10-01

    This investigations of the Savannah River Site's Plutonium Fuel Form fabrication facility located in Building 235-F was initiated in April 1991. The purpose of the investigation was to determine whether, as has been alleged, operation of the facility's argon inert gas system was terminated with the knowledge that continued inoperability of the argon system would cause accelerated corrosion damage to the equipment in the plutonium 238 processing cells. The investigation quickly established that the decision to discontinue operation of the argon system, by not repairing it, was merely one of the measures, and not the most important one, which led to the current deteriorated state of the facility. As a result, the scope of the investigation was broadened to more identify and assess those factors which contributed to the facility's current condition. This document discusses the backgrounds, results, and recommendations of this investigation.

  18. Investigations on detection sensitivity of the NRTA method for different size representing facilities. Pt. 1 and 2

    International Nuclear Information System (INIS)

    Gupta, D.; Bicking, U.; Koutsouvelis, G.

    1985-12-01

    The capability and limitations of the NRTA method (Near-Real-Time Accountancy method) in reprocessing facilities with different throughputs and inventories and measurement uncertainties, were investigated with a detailed computer simulated data base. These investigations have confirmed the earlier findings that the NRTA method could permit under certain operating conditions and for a number of realistic diversion scenarios, a perceptible improvement in the detection capability. Depending on the conditions prevailing, such improvements could be by a factor of 10-20, both for the detectable amounts and the detection time, over the conventional material balance method with annual inventories. The reasons for and the conditions which would permit such improvements have been discussed in detail with numerical examples in the report. (orig.) [de

  19. Trichloroethylene (TCE) in tree cores to complement a subsurface investigation on residential property near a former electroplating facility.

    Science.gov (United States)

    Wilcox, Jeffrey D; Johnson, Kathy M

    2016-10-01

    Tree cores were collected and analyzed for trichloroethylene (TCE) on a private property between a former electroplating facility in Asheville, North Carolina (USA), and a contaminated wetland/spring complex. TCE was detected in 16 of 31 trees, the locations of which were largely consistent with a "plume core" delineated by a more detailed subsurface investigation nearly 2 years later. Concentrations in tree cores and nearby soil borings were not correlated, perhaps due to heterogeneities in both geologic and tree root structure, spatial and temporal variability in transpiration rates, or interferences caused by other contaminants at the site. Several tree cores without TCE provided evidence for significantly lower TCE concentrations in shallow groundwater along the margins of the contaminated spring complex in an area with limited accessibility. This study demonstrates that tree core analyses can complement a more extensive subsurface investigation, particularly in residential or ecologically sensitive areas.

  20. Beam brilliance investigation of high current ion beams at GSI heavy ion accelerator facility.

    Science.gov (United States)

    Adonin, A A; Hollinger, R

    2014-02-01

    In this work the emittance measurements of high current Ta-beam provided by VARIS (Vacuum Arc Ion Source) ion source are presented. Beam brilliance as a function of beam aperture at various extraction conditions is investigated. Influence of electrostatic ion beam compression in post acceleration gap on the beam quality is discussed. Use of different extraction systems (single aperture, 7 holes, and 13 holes) in order to achieve more peaked beam core is considered. The possible ways to increase the beam brilliance are discussed.

  1. Geophysical investigation program Northern Switzerland: Refraction-seismic measurements 84

    International Nuclear Information System (INIS)

    Fromm, G.; Driessen, L.; Lehnen, I.

    1985-01-01

    Acting on instructions from the SGPK/Nagra working group (Baden, Switzerland), PRAKLA-SEISMOS GmbH, Hanover, planned, processed and interpreted seismic refraction measurements in northern Switzerland; CGG, Massy (France) was responsible for carrying out the field work. The aim of the survey was to investigate the shape and depth of a regional, WSW-ENE striking Permocarboniferous trough which underlays the mesozoic sediments of the Tabular Jura. The crystalline basement surface and possibly other geological boundaries were to be identified on the basis of refractor velocities. The recording arrangement included a 36 km spread in the assumed trough axis and four 12 km long spreads perpendicular to the axis (broad side 'T') which covered the trough edges. The resulting good quality data indicated two refractors: horizon H5 which is attributable to the lower Permocarboniferous could only be detected in the western half of the spread with any certainty. Horizon H6 probably represents the crystalline basement surface. If anisotropy is taken into account, the refractor velocity closely corresponds to the Gneiss of the WEIACH- and the Granite 3 of the BOETTSTEIN-borehole. This horizon was clearly discernible on all recordings and allowed the approximate mapping of the trough's shape. The assumed strike direction and depth was largely confirmed. In the WSW section the trough is more than 3300 m deep, it rises to - 3000 m in the ESE section and shows only in the east of the survey area a tendency towards a narrower width and shallower depth (depth data relate to the seismic reference datum at 500 m above MSL). (author)

  2. An update on the LEU target development and conversion program for the MAPLE reactors and new processing facility

    International Nuclear Information System (INIS)

    Malkoske, G.R.; Eng, B.Sc; Eng, P.

    2002-01-01

    Historically, the production of molybdenum-99 in the NRU research reactors at Chalk River, Canada, has been extracted from reactor targets employing highly enriched uranium (HEU). A reliable supply of HEU metal from the United States used in the manufacture of targets for the NRU research reactor has been a key factor to enable MDS Nordion to develop a secure supply of medical isotopes for the international nuclear medicine community. The molybdenum extraction process from HEU targets provides predictable, consistent yields for our high-volume molybdenum production process. Each link of the isotope supply chain, from isotope production to ultimate use by the physician, has been established using this proven and established method of HEU target irradiation and processing to extract molybdenum-99. To ensure a continued reliable and timely supply of medical isotopes, MDS Nordion is completing the construction of two MAPLE reactors and a New Processing Facility. The design of the MAPLE facilities was based on an established process developed by Atomic Energy of Canada Ltd. (AECL)-extraction of isotopes from HEU target material. However, in concert with the global trend to utilize low enriched uranium (LEU) in research reactors, MDS Nordion has launched a three phase LEU Target Development and Conversion Program for the MAPLE facilities. Phase 1, the Initial Feasibility Study, which identified the technical issues to convert the MAPLE reactor targets from HEU to LEU for large scale commercial production was reported on at the RERTR-2000 conference. The second phase of the LEU Target Development and Conversion Program was developed with extensive consultation and involvement of experts knowledgeable in target development, process system design, enriched uranium conversion chemistry and commercial scale reactor operations and molybdenum production. This paper will provide an overview of the Phase 2 Conversion Development Program, report on progress to date, and further

  3. Guest investigator program study: Physics of equatorial plasma bubbles

    Science.gov (United States)

    Tsunoda, Roland T.

    1994-01-01

    -shaped plasma bubbles. The second topic was pursued because the inability to predict the day-to-day occurrence of plasma bubbles indicated inadequate knowledge of the physics of plasma bubbles. An understanding of bubble formation requires an understanding of the roles of the various terms in the linearized growth rate of the collisional Rayleigh-Taylor instability. In our study, we examined electric-field perturbations found in SM-D EFI data and found that the seeding is more likely to be produced in the E region rather than the F region. The results of this investigation are presented in the Appendix of this report and will be submitted for publication in the Journal of Geophysical Research.

  4. Cloud a particle beam facility to investigate the influence of cosmic rays on clouds

    CERN Document Server

    Kirkby, Jasper

    2001-01-01

    Palaeoclimatic data provide extensive evidence for solar forcing of the climate during the Holocene and the last ice age, but the underlying mechanism remains a mystery. However recent observations suggest that cosmic rays may play a key role. Satellite data have revealed a surprising correlation between cosmic ray intensity and the fraction of the Earth covered by low clouds \\cite{svensmark97,marsh}. Since the cosmic ray intensity is modulated by the solar wind, this may be an important clue to the long-sought mechanism for solar-climate variability. In order to test whether cosmic rays and clouds are causally linked and, if so, to understand the microphysical mechanisms, a novel experiment known as CLOUD\\footnotemark\\ has been proposed \\cite{cloud_proposal}--\\cite{cloud_addendum_2}. CLOUD proposes to investigate ion-aerosol-cloud microphysics under controlled laboratory conditions using a beam from a particle accelerator, which provides a precisely adjustable and measurable artificial source of cosmic rays....

  5. Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text. Environmental Restoration Program

    Energy Technology Data Exchange (ETDEWEB)

    Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

    1992-09-01

    This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

  6. Object Oriented Programming Systems (OOPS) and frame representations: An investigation of programming paradigms

    Science.gov (United States)

    Auty, David

    1988-01-01

    The project was initiated to research Object Oriented Programming Systems (OOPS) and frame representation systems, their significance and applicability, and their implementation in or relationship to Ada. Object orientated is currently a very popular conceptual adjective. Object oriented programming, in particular, is promoted as a particularly productive approach to programming; an approach which maximizes opportunities for code reuse and lends itself to the definition of convenient and well-developed units. Such units are thus expected to be usable in a variety of situations, beyond the typical highly specific unit development of other approaches. Frame represenation systems share a common heritage and similar conceptual foundations. Together they represent a quickly emerging alternative approach to programming. The approach is to first define the terms, starting with relevant concepts and using these to put bounds on what is meant by OOPS and Frames. From this the possibilities were pursued to merge OOPS with Ada which will further elucidate the significant characteristics which make up this programming approach. Finally, some of the merits and demerits of OOPS were briefly considered as a way of addressing the applicability of OOPS to various programming tasks.

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

    Energy Technology Data Exchange (ETDEWEB)

    Kolpa, R.; Smith, K.

    1993-07-01

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

  8. RCRA facility investigation for the townsite of Los Alamos, New Mexico

    International Nuclear Information System (INIS)

    Dorries, A.M.; Conrad, R.C.; Nonno, L.M.

    1992-01-01

    During World War II, Los Alamos, New Mexico was established as an ideal location for the secrecy and safety needed for the research and development required to design a nuclear fission bomb. Experiments carried out in the 1940s generated both radioactive and hazardous waste constituents on what is presently part of the Los Alamos townsite. Under the RCRA permit issued to Los alamos national Laboratory in 1990, the Laboratory is scheduled for investigation of its solid waste management units (SWMUs). The existing information on levels of radioactivity on the townsite is principally data from soil samples taken during the last site decontamination in 1976, little information on the presence of hazardous constituents exists today. This paper addresses pathway analysis and a preliminary risk assessment for current residents of the Los Alamos townsite. The estimated dose levels, in mrem per year, show that the previously decontaminated SWMU areas on the Los Alamos townsite will not contribute a radiation dose of any concern to the current residents

  9. Flow field investigations in rotating facilities by means of stationary PIV systems

    International Nuclear Information System (INIS)

    Armellini, A; Mucignat, C; Casarsa, L; Giannattasio, P

    2012-01-01

    The flow field inside rotating test sections can be investigated by means of particle image velocimetry (PIV) operated in the phase-locked mode. With this experimental approach, the measurement system is kept fixed and it is synchronized with the periodical passage of the test section. Therefore, the direct output of the PIV measurements is the absolute velocity field, while the relative one is indirectly obtained from proper data processing that relies on accurate knowledge of the peripheral velocity field. This work provides an uncertainty analysis about the evaluation of the peripheral displacement field in phase-locked PIV measurements. The analysis leads to the detection of the levels of accuracy required in the estimation of both the angular velocity and the position of the center of rotation to ensure correct evaluation of the peripheral displacement field. In this regard, a simple methodology is proposed to evaluate the center of rotation position with an accuracy below 1 px. Finally, a procedure to pre-process the PIV images by subtracting the peripheral displacement is described. The advantages of its implementation are highlighted by the comparison with the performance of a more standard methodology where the peripheral field is subtracted from the absolute velocity field and not directly from the PIV raw data

  10. Physical studies of transmutation scenarios. The Muse program with the Masurca facility: a step towards an hybrid demonstrator?

    International Nuclear Information System (INIS)

    Bouchard, J.; Leconte, Ph.; Doubre, H.; Bhatnagar, V.P.; Carbonnier, J.L.; Chawla, R.; Bernard, H.

    2002-01-01

    The Muse research program, which started in 1995, is a contribution to the development of a dedicated subcritical accelerator driven system (ADS) for the transmutation of minor actinides produced by conventional nuclear power plants. The Muse experiments aim at making a parametric study of different reactor core compositions with different subcritical levels and supplied by different sources in order to demonstrate that the measurement techniques and the calculation charts established for critical FBRs remain valid with an hybrid system. The 4. phase of the Muse program concerns the design, realization and installation of the Genepi (generator of intense pulse neutrons) deutons accelerator at the Masurca facility of Cadarache (France) for the understanding of the neutronic behaviour of an ADS, the definition of a reference calculation scheme, and the development of specific experimental techniques for dynamical measurements. This document brings together the presentations (transparencies) given at the SFEN technical meeting of May 30, 2002 about the Muse program. (J.S.)

  11. Depression among patients attending antiretroviral treatment program in public health facilities in Bahir Dar City, Ethiopia.

    Science.gov (United States)

    Tareke, Minale; Addisu, Fikir; Abate, Andargie

    2018-05-01

    The magnitude of depression is not well investigated among people living with HIV/AIDS. Thus, this research aimed to assess the magnitude of depression and its influencing factors among people living with HIV/AIDS attending government institutions in Bahir Dar City, North West, Ethiopia. institution based-cross-sectional study was done among randomly selected 415 people living with HIV/AIDS attending antiretroviral therapy program in Bahir Dar city, Ethiopia. Socio-demographic data and medical histories for all respondents were collected using interviewer-administered structured questionnaire. We assessed the odds of association of patient characteristics with depression was assessed using multiple logistic regression. The relative effect estimates of the respective factors were presented with odds ratio accompanied by their 95% uncertainty intervals. From 407 people living with HIV/AIDS interviewed, 198(48.6%) of them had depression. Social support, HIV clinical staging, total daily pill burden, treatment regimen and adherence to highly active antiretroviral therapy were significantly associated with depression. The magnitude of depression among people living with HIV/AIDS was found to be high. Early mental health screening should be done for people living with HIV/AIDS. Copyright © 2018 Elsevier B.V. All rights reserved.

  12. Phase I Investigations at the Former CCC/USDA Grain Storage Facility in Montgomery City, Missouri, in 2010-2011

    Energy Technology Data Exchange (ETDEWEB)

    LaFreniere, Lorraine M. [Argonne National Lab. (ANL), Argonne, IL (United States). Environmental Science Division. Applied Geoscience and Environmental Restoration Program

    2012-11-01

    This report presents the technical findings of Phase I of Argonne’s studies. The Phase I field investigation was initiated on October 18, 2010. The work was conducted in accord with (1) the final site-specific Phase I Work Plan for Montgomery City (Argonne 2010; approved by the MDNR [2010]); (2) applicable Missouri regulations; and (3) the standard operating procedures, quality assurance/quality control (QA/QC) measures, and general health and safety policies outlined in the Master Work Plan (Argonne 2002) for operations in Kansas, which was reviewed by the MDNR and accepted for current use. A draft master plan specific to work in Missouri and a set of draft standard operating procedures are in review with the MDNR. The site-specific Work Plan for Montgomery City (Argonne 2010) (1) summarizes the pre-existing knowledge base for the Montgomery City investigation site compiled by Argonne and (2) describes the site-specific technical objectives and the intended scope of work developed for the first phase of the investigation. Three primary technical objectives were identified for the Phase I studies, as follows: 1. Update the presently identified inventory and status of private and public drinking water wells in the immediate vicinity of the former CCC/USDA grain storage facility, and sample the identified wells for volatile organic compounds (VOCs) and geochemical analyses. In conjunction with this effort, determine the present sources(s) of drinking water for all residents in an approximate 0.5-mi radius of the former CCC/USDA facility. 2. Investigate for possible evidence of a soil source of carbon tetrachloride contamination in the unconsolidated sediments beneath the former CCC/USDA facility that might affect the underlying bedrock aquifer units. 3. Obtain preliminary information on the site-specific lithologic and hydrologic characteristics of the unconsolidated sediments overlying bedrock at the former CCC/USDA grain storage location. Section 2 of this report

  13. An Overall Investigation of Direct Vessel Injection Line Break Accidents of the ATLAS Facility

    International Nuclear Information System (INIS)

    Kim, Yeon-Sik; Choi, Ki-Yong; Cho, Seok; Kim, Bok-Deuk

    2015-01-01

    For parametric evaluations of direct vessel injection (DVI) line break scenarios, the pressurizer (PZR) pressure, core collapsed water level, and peak cladding temperature were investigated between the analyses and tests. The PZR pressure was mainly dependent upon the break flow model, e.g., discharge coefficient of the Henry-Fauske critical model. The core collapsed water level and peak cladding temperature were mainly dependent on the counter-current flow limit (CCFL) option of the fuel alignment plate (FAP). The CCFL option of the cross-over leg (COL) affected the PZR pressure owing to the loop seal clearings and seemed to have little effect on the core collapsed water level. Proper C d values and applicable CCFL options were summarized. C d values seemed to be dependent on the sizes of the DVI line break. The PZR pressure was mainly dependent on the break flow model, e.g., the discharge coefficient of the Henry-Fauske critical model. The core collapsed water level and peak cladding temperature were mainly dependent on the CCFL option of the FAP. The CCFL option of the COL affected the PZR pressure owing to loop seal clearings and seemed to have little effect on the core collapsed water level. From parametric evaluations, proper C d values and applicable CCFL options were suggested. The C d values seemed to be dependent on the sizes of the DVI line break. Although there was little difference in the CCFL options of the COL, the Ku-option was the preferred one for COLs' CCFL option. The CCFL options of the FAP appeared sensitive to the core collapsed water level and peak cladding temperature. The Ku-option of the FAP tended to negatively exaggerate the core behavior and showed excessively conservative results, especially on the peak cladding temperature. For smaller breaks, e.g., 25%, NA- and Wa-options would be applicable for the FAP. However, for larger breaks, e.g., 50%, the Wa-option of the FAP was the preferred one. Comparisons between the tests and

  14. 76 FR 34720 - Chemical Facility Anti-Terrorism Standards Personnel Surety Program

    Science.gov (United States)

    2011-06-14

    ... are currently required for employment or access to secure areas of those facilities. Background On... individuals in order to clarify suspected data errors or resolve potential matches (e.g., in situations where...., affirmations or certifications of compliance, extension requests, brief surveys for process improvement, etc...

  15. 75 FR 65282 - Medicare and Medicaid Programs; Requirements for Long Term Care Facilities; Hospice Services

    Science.gov (United States)

    2010-10-22

    .... Palliative care in an LTC facility involves addressing physical, intellectual, emotional, social, and... Disability, Aging and Long-Term Care Policy and the Urban Institute; ``Synthesis and Analysis of Medicare..., mental, social, or emotional status; clinical complications that suggested a need to alter the care plan...

  16. Wind Atlas Analysis and Application Program: WAsP 11 Help Facility

    DEFF Research Database (Denmark)

    2014-01-01

    of specific wind turbines and wind farms. The WAsP Help Facility includes a Quick Start Tutorial, a User's Guide and a Technical Reference. It further includes descriptions of the Observed Wind Climate Wizard, the WAsP Climate Analyst, the WAsP Map Editor tool, the WAsP Turbine Editor tool, the Air Density...

  17. Site selection report basalt waste isolation program near-surface test facility

    International Nuclear Information System (INIS)

    Sharpe, S.D.

    1978-01-01

    A site selection committee was established to review the information gathered on potential sites and to select a site for the Near-Surface Test Facility Phase I. A decision was made to use a site on the north face of Gable Mountain located on the Hanford Site. This site provided convenient access to the Pomona Basalt Flow. This flow was selected for use at this site because it exhibited the characteristics established in the primary criteria. These criteria were: the flows thickness; its dryness; its nearness to the surface; and, its similarities to basalt units which are candidates for the repository. After the selection of the Near-Surface Test Facility Phase I Site, the need arose for an additional facility to demonstrate safe handling, storage techniques, and the physical effects of radioactive materials on an in situ basalt formation. The committee reviewed the sites selected for Phase I and chose the same site for locating Phase II of the Near-Surface Test Facility

  18. 78 FR 17680 - Information Collection Request; Chemical Facility Anti-Terrorism Standards Personnel Surety Program

    Science.gov (United States)

    2013-03-22

    ... Total Burden Cost (Capital/Startup) [cir] Estimating Capital Costs for Option 3--Number and Type of High... Department to take advantage of the vetting for terrorist ties already being conducted on affected... Department anticipates that many high-risk chemical facilities will rely on businesses that provide contract...

  19. 77 FR 55120 - Federal Housing Administration (FHA): Section 232 Healthcare Facility Insurance Program...

    Science.gov (United States)

    2012-09-07

    ... in light of available accounting software systems. HUD agrees that accounting software available... facilities (as opposed to when the regulations were first promulgated in the 1970s), and this important role..., the exemption would eliminate the conflict between the HUD inspection requirements and the State...

  20. Facilitating programming comprehension for novice learners with multimedia approach: A preliminary investigation

    Science.gov (United States)

    Annamalai, Subashini; Salam, Sobihatun Nur Abdul

    2017-10-01

    This research paper presents the preliminary investigation on the use of an interactive multimedia courseware named MAFPro, to facilitate C Programming lessons for novice learners. The courseware utilizes the elements of multimedia that focus on enhancing learners' programming comprehension. Among the aspects that were examined were the students' programming comprehension and their perceived motivation of MAFPro. This study was carried out in a survey design method with the participation of 30 undergraduates who are novice learners. The data analysis indicates that the multimedia courseware, MAFPro that has been used in the C programming classroom has a significant difference on the undergraduates' programming comprehension. The students also perceived MAFPro as motivating and engaging.