WorldWideScience

Sample records for meet interim status

  1. Waste Encapsulation and Storage Facility (WESF) Interim Status Closure Plan

    International Nuclear Information System (INIS)

    SIMMONS, F.M.

    2000-01-01

    This document describes the planned activities and performance standards for closing the Waste Encapsulation and Storage Facility (WESF). WESF is located within the 225B Facility in the 200 East Area on the Hanford Facility. Although this document is prepared based on Title 40 Code of Federal Regulations (CFR), Part 265, Subpart G requirements, closure of the storage unit will comply with Washington Administrative Code (WAC) 173-303-610 regulations pursuant to Section 5.3 of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Action Plan (Ecology et al. 1996). Because the intention is to clean close WESF, postclosure activities are not applicable to this interim status closure plan. To clean close the storage unit, it will be demonstrated that dangerous waste has not been left onsite at levels above the closure performance standard for removal and decontamination. If it is determined that clean closure is not possible or environmentally is impracticable, the interim status closure plan will be modified to address required postclosure activities. WESF stores cesium and strontium encapsulated salts. The encapsulated salts are stored in the pool cells or process cells located within 225B Facility. The dangerous waste is contained within a double containment system to preclude spills to the environment. In the unlikely event that a waste spill does occur outside the capsules, operating methods and administrative controls require that waste spills be cleaned up promptly and completely, and a notation made in the operating record. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

  2. 40 CFR 265.383 - Interim status thermal treatment devices burning particular hazardous waste.

    Science.gov (United States)

    2010-07-01

    ... status thermal treatment devices burning particular hazardous waste. (a) Owners or operators of thermal treatment devices subject to this subpart may burn EPA Hazardous Wastes FO20, FO21, FO22, FO23, FO26, or... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Interim status thermal treatment...

  3. First interim project review meeting on management of water hyacinth

    International Nuclear Information System (INIS)

    1980-01-01

    The first project planning meeting was held in New Delhi during 1978 and the second, a project review meeting, in Papua New Guinea during June 1979, both funded by UNEP. Reports from the regional coordinators for Bangladesh, Malaysia, Sri Lanka, Fiji and India are presented. Also presented are reports from the national coordinators for Malaysia, Bangladesh and India. Two visits (a visit to India, Bangladesh and Sri Lanka to study the feasibility of making a film on the work done with water hyacinth and a visit to the U.S. by the regional project coordinator) are also described

  4. Interim-status groundwater monitoring plan for the 216-B-63 trench

    Energy Technology Data Exchange (ETDEWEB)

    Sweeney, M.D.

    1995-02-09

    This document outlines the groundwater monitoring plan, under RCRA regulations in 40 CFR 265 Subpart F and WAC173-300-400, for the 216-B-63 Trench. This interim status facility is being sampled under detection monitoring criteria and this plan provides current program conditions and requirements.

  5. Status of the Galileo interim radiation electron model

    Science.gov (United States)

    Garrett, H. B.; Jun, I.; Ratliff, J. M.; Evans, R. W.; Clough, G. A.; McEntire, R. W.

    2003-04-01

    Measurements of the high energy, omni-directional electron environment by the Galileo spacecraft Energetic Particle Detector (EPD) were used to develop a new model of Jupiter's trapped electron radiation in the jovian equatorial plane for the range 8 to 16 Jupiter radii (1 jovian radius = 71,400 km). 10-minute averages of these data formed an extensive database of observations of the jovian radiation belts between Jupiter orbit insertion (JOI) in 1995 and 2002. These data were then averaged to provide a differential flux spectrum at 0.174, 0.304, 0.527, 1.5, 2.0, 11.0, and 31 MeV in the jovian equatorial plane as a function of radial distance. This omni-directional, equatorial model was combined with the original Divine model of jovian electron radiation to yield estimates of the out-of-plane radiation environment. That model, referred to here as the Galileo Interim Radiation Electron (or GIRE) model, was then used to calculate the Europa mission dose for an average and a 1-sigma worst-case situation. The prediction of the GIRE model is about a factor of 2 lower than the Divine model estimate over the range of 100 to 1000 mils (2.54 to 25.4 mm) of aluminum shielding, but exceeds the Divine model by about 50% for thicker shielding. The model, the steps leading to its creation, and relevant issues and concerns are discussed. While work remains to be done, the GIRE model clearly represents a significant step forward in the study of the jovian radiation environment, and it is a useful and valuable tool for estimating that environment for future space missions.

  6. Report of the first interim meeting of the Seabed Working Group Engineering Studies Task Group

    International Nuclear Information System (INIS)

    Talbert, D.M.

    1982-02-01

    The first interim meeting of the Engineering Studies Task Group (ESTG) was held at the Delft Soil Mechanics Laboratory, Delft, The Netherlands, on 21-24 September 1981. The main business of the meeting was the development of a network analysis for the ESTG. Significant progress was made; however, substantial further development remains to be accomplished. Other items discussed were (1) progress relevant to engineering studies made in the various national programs since the sixth annual meeting of the Seabed Working Group (SWG) held in Paris, February, 1981; (2) the ESTG Boundary Conditions and Scope of Work as previously defined at the Paris meeting; (3) the Draft II SWG Five-Year Plan; (4) the deep ocean drilling proposal made by the Site Selection Task Group at the Paris meeting and expanded upon at their May, 1981, meeting; and (5) a recent compilation of data from the Nares Abyssal Plain arising from the US Program studies. Finally, consideration was given to a plan for continued work by the ESTG. A brief discussion of the principal items is given. The current state of the network analysis is shown

  7. Interim status of the Texas uranium survey experiment

    International Nuclear Information System (INIS)

    Jupiter, C.; Wollenberg, H.

    1974-01-01

    The objective of the Texas uranium survey experiment is to evaluate an improved method for prospecting for uranium by determining correlations among (a) geologic analysis, (b) soil sample radiochemical analysis, (c) aerial radiometric data, (d) aerial infrared scans, and (e) aerophotographic data. Although aerial radiometric measurements have been used previously in mineral prospecting, the development of useful correlative techniques based on analysis of data from large terrestrial areas employing the five parameters (a through e, above) remains to be evaluated, and could be of significant value to the need for establishing uranium resource pools to meet the nation's energy crisis. The Texas uranium survey field experiment began on June 13, 1973, employing a Martin-404 aircraft to fly gamma-ray recording equipment at a 500-ft altitude over two areas in southeast Texas. The areas surveyed are referred to as the Dubose area (approximately 120 sq. miles) and the Clay West area (approximately 24 sq. miles). This document briefly summarizes the work which has been done, describes the kind and quality of calibrations and data analysis carried out thus far and outlines recommended additional work which would bring the experiment to some degree of completion, providing a basis for evaluating the techniques

  8. Interim status of vertical calciner testing through calendar year 1996

    International Nuclear Information System (INIS)

    Compton, J.A.

    1998-01-01

    A prototype vertical calciner was constructed and tested for use in converting plutonium solutions to dry plutonium dioxide in the Hanford Plutonium Finishing Plant. Six non-radioactive runs were completed in June and July, 1995. Fourteen runs with plutonium nitrate solutions were completed between September, 1995 and August, 1996. Equipment modifications were made following those runs. The test runs with plutonium have converted 62.3 L of feed solution containing 11.1 kg of plutonium into dry plutonium dioxide containing 8.5 kg of plutonium. The decrease in product plutonium content is primarily due to plutonium accumulation within the calciner powder bed from particle compaction. Nine of the eleven product batches have had Losses On Ignition that met the storage criterion of less than 0.5 weight percent at 950 C. The highest Loss On Ignition found was 0.718 weight percent. Initial problems with agitator shaft binding and breakage of bushings have been eliminated. A feed pump control problem has been found and the pump replaced. Improvement in scrubber efficiency is needed. Future runs are planned to confirm that (1) the remainder of product meets the Loss On Ignition criterion, (2) the replacement feedpump works as needed, and (3) the scrubber efficiency improves. The operating staff for the production calciner may also be observing the prototype's runs to gain familiarity with the process and equipment

  9. 75 FR 34537 - Interim Final Rules for Group Health Plans and Health Insurance Coverage Relating to Status as a...

    Science.gov (United States)

    2010-06-17

    ... 45 CFR Part 147 Group Health Plans and Health Insurance Coverage Relating to Status as a... for Group Health Plans and Health Insurance Coverage Relating to Status as a Grandfathered Health Plan... and Insurance Oversight, Department of Health and Human Services. ACTION: Interim final rules with...

  10. Interim restorations.

    Science.gov (United States)

    Gratton, David G; Aquilino, Steven A

    2004-04-01

    Interim restorations are a critical component of fixed prosthodontic treatment, biologically and biomechanically. Interim restoration serves an important diagnostic role as a functional and esthetic try-in and as a blueprint for the design of the definitive prosthesis. When selecting materials for any interim restoration, clinicians must consider physical properties, handling properties, patient acceptance, and material cost. Although no single material meets all the requirements and material classification alone of a given product is not a predictor of clinical performance, bis-acryl materials are typically best suited to single-unit restorations, and poly(methylmethacrylate) interim materials are generally ideal for multi-unit, complex, long-term, interim fixed prostheses. As with most dental procedures, the technique used for fabrication has a greater effect on the final result than the specific material chosen.

  11. 40 CFR 262.212 - Making the hazardous waste determination at an on-site interim status or permitted treatment...

    Science.gov (United States)

    2010-07-01

    ..., storage or disposal facility. If an eligible academic entity makes the hazardous waste determination... hazardous waste permit or interim status as soon as it arrives in the on-site treatment, storage or disposal... permitted treatment, storage or disposal facility. (e) If the unwanted material is a hazardous waste, the...

  12. Interim-status groundwater monitoring plan for the 216-B-63 trench. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Sweeney, M.D.

    1995-06-13

    This document outlines the groundwater monitoring plan for interim-status detection-level monitoring of the 216-B-63 Trench. This is a revision of the initial groundwater monitoring plan prepared for Westinghouse Hanford Company (WHC) by Bjornstad and Dudziak (1989). The 216-B-63 Trench, located at the Hanford Site in south-central Washington State, is an open, unlined, earthern trench approximately 1.2 m (4 ft) wide at the bottom, 427 m (1400 ft) long, and 3 m (10 ft) deep that received wastewater containing hazardous waste and radioactive materials from B Plant, located in the 200 East Area. Liquid effluent discharge to the 216-B-63 Trench began in March 1970 and ceased in February 1992. The trench is now managed by Waste Tank Operations.

  13. Interim-status groundwater monitoring plan for the 216-B-63 trench. Revision 1

    International Nuclear Information System (INIS)

    Sweeney, M.D.

    1995-01-01

    This document outlines the groundwater monitoring plan for interim-status detection-level monitoring of the 216-B-63 Trench. This is a revision of the initial groundwater monitoring plan prepared for Westinghouse Hanford Company (WHC) by Bjornstad and Dudziak (1989). The 216-B-63 Trench, located at the Hanford Site in south-central Washington State, is an open, unlined, earthern trench approximately 1.2 m (4 ft) wide at the bottom, 427 m (1400 ft) long, and 3 m (10 ft) deep that received wastewater containing hazardous waste and radioactive materials from B Plant, located in the 200 East Area. Liquid effluent discharge to the 216-B-63 Trench began in March 1970 and ceased in February 1992. The trench is now managed by Waste Tank Operations

  14. 40 CFR 265 interim-status ground-water monitoring plan for the 2101-M pond

    International Nuclear Information System (INIS)

    Chamness, M.A.; Luttrell, S.P.; Dudziak, S.

    1989-03-01

    This report outlines a ground-water monitoring plan for the 2101-M pond, located in the southwestern part of the 200-East Area on the Hanford Site in south-central Washington State. It has been determined that hazardous materials may have been discharged to the pond. Installation of an interim-status ground-water monitoring system is required under the Resource Conservation and Recovery Act to determine if hazardous chemicals are moving out of the pond. This plan describes the location of new wells for the monitoring system, how the wells are to be completed, the data to be collected, and how those data can be used to determine the source and extent of any ground-water contamination from the 2101-M pond. Four new wells are planned, one upgradient and three downgradient. 35 refs., 12 figs., 9 tabs

  15. Interim Status Closure Plan Open Burning Treatment Unit Technical Area 16-399 Burn Tray

    Energy Technology Data Exchange (ETDEWEB)

    Vigil-Holterman, Luciana R. [Los Alamos National Laboratory

    2012-05-07

    This closure plan describes the activities necessary to close one of the interim status hazardous waste open burning treatment units at Technical Area (TA) 16 at the Los Alamos National Laboratory (LANL or the Facility), hereinafter referred to as the 'TA-16-399 Burn Tray' or 'the unit'. The information provided in this closure plan addresses the closure requirements specified in the Code of Federal Regulations (CFR), Title 40, Part 265, Subparts G and P for the thermal treatment units operated at the Facility under the Resource Conservation and Recovery Act (RCRA) and the New Mexico Hazardous Waste Act. Closure of the open burning treatment unit will be completed in accordance with Section 4.1 of this closure plan.

  16. 76 FR 540 - National Conference on Weights and Measures 2011 Interim Meeting

    Science.gov (United States)

    2011-01-05

    ... and representatives of business, industry, trade associations, and consumer organizations on subjects...'' which contains meeting agendas, registration forms and hotel reservation information at http://www.ncwm... Retail Motor Fuel Dispenser (RMFD) Price Posting and Computer Capability will meet from 1:30 to 4 p.m. on...

  17. Current status of the first interim spent fuel storage facility in Japan

    International Nuclear Information System (INIS)

    Shinbo, Hitoshi; Kondo, Mitsuru

    2008-01-01

    In Japan, storage of spent fuels outside nuclear power plants was enabled as a result of partial amendments to the Nuclear Reactor Regulation Law in June 2000. Five months later, Mutsu City in Aomori Prefecture asked the Tokyo Electric Power Company (TEPCO) to conduct technical surveys on siting of the interim spent fuel storage facility (we call it 'Recyclable-Fuel Storage Center'). In April 2003, TEPCO submitted the report on siting feasibility examination, concluded that no improper engineering data for siting, construction of the facility will be possible from engineering viewpoint. Siting Activities for publicity and public acceptance have been continued since then. After these activities, Aomori Prefecture and Mutsu City approved siting of the Recyclable Fuel Storage Center in October 2005. Aomori Prefecture, Mutsu City, TEPCO and Japan Atomic Power Company (JAPC) signed an agreement on the interim spent fuel storage Facility. A month later, TEPCO and JAPC established Recyclable-Fuel Storage Company (RFS) in Mutsu City through joint capital investment, specialized in the first interim spent fuel storage Facility in Japan. In May 2007, we made an application for establishment permit, following safety review by regulatory authorities. In March 2008, we started the preparatory construction. RFS will safely store of spent fuels of TEPCO and JAPC until they will be reprocessed. Final storage capacity will be 5,000 ton-U. First we will construct the storage building of 3,000 ton-U to be followed by second building. We aim to start operation by 2010. (author)

  18. Present status of yellow fever: Memorandum from a PAHO Meeting

    OpenAIRE

    1986-01-01

    An international seminar on the treatment and laboratory diagnosis of yellow fever, sponsored by the Pan American Health Organization (PAHO) and held in 1984, differed from previous meetings on yellow fever because of its emphasis on the care and management of patients and because the participants included specialists from several branches of medicine, such as hepatology, haematology, cardiology, infectious diseases, pathology and nephrology. The meeting reviewed the current status of yellow ...

  19. FY17 Status Report: Research on Stress Corrosion Cracking of SNF Interim Storage Canisters.

    Energy Technology Data Exchange (ETDEWEB)

    Schindelholz, Eric John [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Bryan, Charles R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Alexander, Christopher L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-09-01

    This progress report describes work done in FY17 at Sandia National Laboratories (SNL) to assess the localized corrosion performance of container/cask materials used in the interim storage of spent nuclear fuel (SNF). Of particular concern is stress corrosion cracking (SCC), by which a through-wall crack could potentially form in a canister outer wall over time intervals that are shorter than possible dry storage times. Work in FY17 refined our understanding of the chemical and physical environment on canister surfaces, and evaluated the relationship between chemical and physical environment and the form and extent of corrosion that occurs. The SNL corrosion work focused predominantly on pitting corrosion, a necessary precursor for SCC, and process of pit-to-crack transition; it has been carried out in collaboration with university partners. SNL is collaborating with several university partners to investigate SCC crack growth experimentally, providing guidance for design and interpretation of experiments.

  20. Status and trends in spent fuel reprocessing. Proceedings of an advisory group meeting

    International Nuclear Information System (INIS)

    1999-08-01

    Spent fuel management has always been an important part of the nuclear fuel cycle and is still one of the most important activities in all countries exploiting the peaceful use of nuclear energy. Continuous attention is being given by the IAEA to the collection, analysis and exchange of information on spent fuel management. Its role in this area is to provide a forum for exchanging information and to coordinate and encourage closer co-operation among Member States in certain research and developing activities that are of common interest. As part of spent fuel management, reprocessing activities have been reviewed from time to time on a low profile level under the terminology 'spent fuel treatment'. However, spent fuel treatment covers, in broad terms, spent fuel storage (short, interim and long term), fuel rod consolidation, reprocessing and, in case the once-through cycle is selected, conditioning of the spent fuel for disposal. Hence the reprocessing activities under the heading 'spent fuel treatment' were somewhat misleading. Several meetings on spent fuel treatment have been organized during the fast decade: an Advisory Group meeting (AGM) in 1992, a Technical Committee meeting in 1995 and recently an Advisory Group meeting from 7 to 10 September 1998. The objectives of the meetings were to review the status and trends of spent fuel reprocessing, to discuss the environmental impact and safety aspects of reprocessing facilities and to define the most important issues in this field. Notwithstanding the fact that the Summary of the report does not include aspects of military reprocessing, some of the national presentations do refer to some relevant aspects (e.g. experience, fissile stockpiles)

  1. Evaluation of tuff as a medium for a nucolear waste repository: interim status report on the properties of tuff

    International Nuclear Information System (INIS)

    Johnstone, J.K.; Wolfsberg, K.

    1980-07-01

    This report is the second in a series of summary briefings to the National Academy of Science's (NAS) Committee on Radioactive Waste Management dealing with feasibility of disposal of heat-producing radioactive waste in silicic tuff. The interim status of studies of tuff properties determined on samples obtained from Yucca Mountain and Rainier Mesa (G-tunnel) located on the Nevada Test Site (NTS) are discussed. In particular, progress is described on resolving issues identified during the first briefing to the NAS which include behavior of water in tuff when heated, the effect of the presence or absence of water and joints on the thermal/physical properties of tuff and the detailed/complex sorptive properties of highly altered and unaltered tuff. Initial correlations of thermal/physical and sorptive properties with the highly variable porosity and mineralogy are described. Three in-situ, at-depth field experiments, one nearly completed and two just getting underway are described. In particular, the current status of mineralogy and petrology, geochemistry, thermal and mechanical, radiation effects and water behavior studies are described. The goals and initial results of a Mine Design Working Group are discussed. Regional factors such as seismicity, volcanism and hydrology are not discussed

  2. Report of the Fourth interim meeting of the Seabed Working Group Engineering Studies Task Group, 3-6 October 1983, at Rijks Geologische Dienst, Haarlem, The Netherlands

    International Nuclear Information System (INIS)

    Talbert, D.M.

    1984-06-01

    This report presents the results of the fourth interim meeting of the Seabed Working Group's (SWG) Engineering Studies Task Group (ESTG). This task group is charged with determining whether the engineering technology exists to emplace waste canisters in deep ocean sediments. The fourth interim meeting, held at Rijks Geologische Dienst, Haarlem, The Netherlands, 3-6 October 1983, reviewed progress made by the various national programs since the ESTG third interim meeting (July 1982) and developed a table of requirements for processing samples for a geotechnical properties data base. Other items addressed were (1) potential methods of instrumenting penetrators to obtain in situ measurements, (2) procedures for evaluating and quantifying the disturbed zone created by an emplaced penetrator, (3) review and modification of the current draft version of the SWG Five-Year Plan, (4) review and extension of the ESTG detailed plan for penetrator tests, and (5) details of the penetrator tests scheduled for March 1984 in the Nares Abyssal Plain using the research vessel M/V TYRO. The review of the national programs indicated significant progress when measured against the integrated ESTG five-year plan which results in a joint evaluation of engineering feasibility of subseabed disposal based upon (1) a demonstration of an emplacement capability, (2) an evaluation of the zone of sediment disturbance created during emplacement, (3) the existence of acceptable emplacement models, and (4) an acceptable engineering data base. A table of geotechnical sample-processing requirements is being developed to provide guidance for the other task groups that may have the opportunity to furnish suitable geotechnical samples to the ESTG as well as to provide some measure of consistency within the ESTG for the development of the engineering data base for the SWG study areas

  3. 40 CFR 265 interim status indicator-evaluation ground-water monitoring plan for the 216-B-63 trench

    International Nuclear Information System (INIS)

    Bjornstad, B.N.; Dudziak, S.

    1989-03-01

    This document outlines a ground-water monitoring plan for the 216-B-63 trench located in the northeast corner of the 200-East Area on the Hanford Site in southeastern Washington State. It has been determined that hazardous materials (corrosives) were disposed of to the trench during past operations. Installation of an interim-status ground-water monitoring system is required to determine whether hazardous chemicals are leaching to the ground water from beneath the trench. This document summarizes the existing data that are available from near the 216-B-63 trench and presents a plan to determine the extent of ground-water contamination, if any, derived from the trench. The plan calls for the installation of four new monitoring wells located near the west end of the trench. These wells will be used to monitor ground-water levels and water quality immediately adjacent to the trench. Two existing RCRA monitoring wells, which are located near the trench and hydraulically upgradient of it, will be used as background wells. 46 refs., 15 figs., 12 tabs

  4. Interim design status and operational report for remote handling fixtures: primary and secondary burners

    International Nuclear Information System (INIS)

    Burgoyne, R.M.

    1976-12-01

    The HTGR reprocessing flowsheet consists of two basic process elements: (1) spent fuel crushing and burning and (2) solvent extraction. Fundamental to these elements is the design and development of specialized process equipment and support facilities. A major consideration of this design and development program is equipment maintenance: specifically, the design and demonstration of selected remote maintenance capabilities and the integration of these into process equipment design. This report documents the current status of the development of remote handling and maintenance fixtures for the primary and secondary burners

  5. Eleventh interim status report: Model 9975 O-Ring fixture long-term leak performance

    Energy Technology Data Exchange (ETDEWEB)

    Daugherty, W. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-08-01

    A series of experiments to monitor the aging performance of Viton® GLT O-rings used in the Model 9975 package has been ongoing since 2004 at the Savannah River National Laboratory. One approach has been to periodically evaluate the leak performance of O-rings being aged in mock-up 9975 Primary Containment Vessels (PCVs) at elevated temperature. Other methods such as compression-stress relaxation (CSR) tests and field surveillance are also on-going to evaluate O-ring behavior. Seventy tests using PCV mock-ups were assembled and heated to temperatures ranging from 200 to 450 ºF. They were leak-tested initially and have been tested periodically to determine if they continue to meet the leak-tightness criterion defined in ANSI standard N14.5-97. Due to material substitution, fourteen additional tests were initiated in 2008 with GLT-S O-rings heated to temperatures ranging from 200 to 400 ºF.

  6. Interim Status Report on the Design of the Gas-Cooled Fast Reactor (GFR)

    International Nuclear Information System (INIS)

    Weaver, K. D.

    2005-01-01

    Current research and development on the Gas-Cooled Fast Reactor (GFR) has focused on the design of safety systems that will remove the decay heat during accident conditions, ion irradiations of candidate ceramic materials, joining studies of oxide dispersion strengthened alloys; and within the Advanced Fuel Cycle Initiative (AFCI) the fabrication of carbide fuels and ceramic fuel matrix materials, development of non-halide precursor low density and high density ceramic coatings, and neutron irradiation of candidate ceramic fuel matrix and metallic materials. The vast majority of this work has focused on the reference design for the GFR: a helium-cooled, direct power conversion system that will operate with on outlet temperature of 850 C at 7 MPa. In addition to the work being performed in the United States, seven international partners under the Generation IV International Forum (GIF) have identified their interest in participating in research related to the development of the GFR. These are Euratom (European Commission), France, Japan, South Africa, South Korea, Switzerland, and the United Kingdom. Of these, Euratom (including the United Kingdom), France, and Japan have active research activities with respect to the GFR. The research includes GFR design and safety, and fuels/in-core materials/fuel cycle projects. This report outlines the current design status of the GFR, and includes work done in the areas mentioned above

  7. Fifth Interim Status Report: Model 9975 PCV O-Ring Fixture Long-Term Leak Performance

    International Nuclear Information System (INIS)

    Daugherty, W.; Hoffman, E.

    2010-01-01

    A series of experiments to monitor the aging performance of Viton reg. GLT O-rings used in the Model 9975 package has been ongoing for six years at the Savannah River National Laboratory. Sixty-seven mock-ups of 9975 Primary Containment Vessels (PCVs) were assembled and heated to temperatures ranging from 200 to 450 F. They were leak-tested initially and have been tested at nominal six month intervals to determine if they meet the criterion of leaktightness defined in ANSI standard N14.5-97. Fourteen additional tests were initiated in 2008 with GLT-S O-rings heated to temperatures ranging from 200 to 400 F. High temperature aging continues for 36 GLT O-ring fixtures at 200--350 F. Room temperature leak test failures have been experienced in 5 of the GLT O-ring fixtures aging at 300 and 350 F, and in all 3 of the GLT O-ring fixtures aging at higher temperatures. No failures have yet been observed in GLT O-ring fixtures aging at 200 F for 30--48 months, which is still bounding to O-ring temperatures during storage in KAMS. High temperature aging continues for 6 GLT-S O-ring fixtures at 200--300 F. Room temperature leak test failures have been experienced in all 8 of the GLT-S O-ring fixtures aging at 350 and 400 F. No failures have yet been observed in GLT-S O-ring fixtures aging at 200 or 300 F for 19 months. For O-ring fixtures that have failed the room temperature leak test and been disassembled, the O-rings displayed a compression set ranging from 51--95%. This is significantly greater than seen to date for packages inspected during KAMS field surveillance (23% average). For GLT O-rings, service life based on the room temperature leak rate criterion is comparable to that predicted by compression stress relaxation (CSR) data at higher temperatures (350--400 F). While there are no comparable failure data yet at aging temperatures below 300 F, extrapolations of the data for GLT O-rings suggests that CSR model predictions provide a conservative prediction of service

  8. Interim overdentures.

    Science.gov (United States)

    Fenton, A H

    1976-07-01

    The construction of an interim overdenture using existing removable partial dentures with natural tooth crowns and artificial teeth can be a simple and economical method of providing patients with dentures while tissues heal and teeth are prepared and restored. A more definite prognosis for both the patient and his remaining dentition can be established before the final overdenture is completed. The procedures necessary to provide three types of interim overdentures have been outlined. Patients tolerate this method of changing their dentitions extremely well.

  9. Addendum to IFMIF-CDA interim report

    Energy Technology Data Exchange (ETDEWEB)

    Maekawa, Hiroshi; Ida, Mizuho [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; eds.

    1996-08-01

    During the second IFMIF-CDA Design Integration Workshop, the conceptual design and contents of `IFMIF-CDA Interim Report` were examined and discussed at both general and group meetings. Based on these discussion, the final IFMIF-CDA Report will be modified from the `Interim Report`. This report describes the outline of these modification. (author)

  10. Addendum to IFMIF-CDA interim report

    International Nuclear Information System (INIS)

    Maekawa, Hiroshi; Ida, Mizuho

    1996-08-01

    During the second IFMIF-CDA Design Integration Workshop, the conceptual design and contents of 'IFMIF-CDA Interim Report' were examined and discussed at both general and group meetings. Based on these discussion, the final IFMIF-CDA Report will be modified from the 'Interim Report'. This report describes the outline of these modification. (author)

  11. Marriage Meets the Joneses: Relative Income, Identity, and Marital Status

    Science.gov (United States)

    Watson, Tara; McLanahan, Sara

    2011-01-01

    This paper investigates the effect of relative income on marriage. Accounting flexibly for absolute income, the ratio between a man's income and a local reference group median is a strong predictor of marital status, but only for low-income men. Relative income affects marriage even among those living with a partner. A 10 percent higher reference…

  12. Resource conversation and recovery act (RCRA) Contingency Plan for interim status or permitted units at the Oak Ridge Y-12 Plant

    International Nuclear Information System (INIS)

    1992-08-01

    The official mission of the Y-12 Plant is to serve as a manufacturing technology center for key processes such that capabilities are maintained for safe, secure, reliable, and survivable nuclear weapons systems and other applications of national importance. The Y-12 RCRA Contingency Plan will be reviewed and revised if necessary if the facility RCRA operating permits are revised, the plan is inadequate in an emergency, the procedures herein can be improved, the facility's operations change in a manner that alters the plan, the emergency coordinator changes, or the emergency equipment list changes. Copies of the Y-12 Emergency Management Plan are available at the Plant Shift Superintendent's Office and the Emergency Preparedness Office. This document serves to supplement the Y-12 Emergency Management Plan to be appropriate for all RCRA hazardous waste interim status or permitted treatment, storage, or disposal facilities. The 90-day storage areas at the Y-12 Plant have a separate contingency supplement as required by RCRA and are separate from this supplement

  13. Status report. Characterization of Weld Residual Stresses on a Full-Diameter SNF Interim Storage Canister Mockup.

    Energy Technology Data Exchange (ETDEWEB)

    Enos, David [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Bryan, Charles R. [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

    2015-08-01

    This report documents the mockup specifications and manufacturing processes; the initial cutting of the mockup into three cylindrical pieces for testing and the measured strain changes that occurred during the cutting process; and the planned weld residual stress characterization activities and the status of those activities.

  14. The Effect of Human-Immunodeficiency Virus Status on Outcomes in Penetrating Abdominal Trauma: An Interim Analysis.

    Science.gov (United States)

    McPherson, Deidre; Neuhaus, Valentin; Dhar, Rohin; Edu, Sorin; Nicol, Andrew J; Navsaria, Pradeep H

    2018-01-31

    The purpose of this study was to determine whether the outcomes of hemodynamically stable patients undergoing exploratory laparotomy for penetrating abdominal trauma differed as a result of their HIV status. This was an observational, prospective study from February 2016 to May 2017. All hemodynamically stable patients with penetrating abdominal trauma requiring a laparotomy were included. The mechanism of injury, the HIV status, age, the penetrating abdominal trauma index (PATI), and the revised trauma score (RTS) were entered into a binary logistic regression model. Outcome parameters were in-hospital death, morbidity, admission to intensive care unit (ICU), relaparotomy within 30 days, and length of stay longer than 30 days. A total of 209 patients, 94% male, with a mean age of 29 ± 10 years were analysed. Twenty-eight patients (13%) were HIV positive. The two groups were comparable. Ten (4.8%) laparotomies were negative. There were two (0.96%) deaths, both in the HIV negative group. The complication rate was 34% (n = 72). Twenty-nine patients (14%) were admitted to the ICU. A higher PATI, older age, and a lower RTS were significant risk factors for ICU admission. After 30 days, 12 patients (5.7%) were still in hospital. Twenty-four patients (11%) underwent a second laparotomy. The PATI score was the single independent predictor for complications, relaparotomy, and hospital stay longer than 30 days. Preliminary results reveal that HIV status does not influence outcomes in patients with penetrating abdominal trauma.

  15. Status of national programmes on fast reactors 1998/99. 32nd annual meeting. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    Over the past 32 years, the IAEA has actively encouraged and advocated international cooperation in fast reactor technology. The present publication contains information on the status of fast reactor development and on worldwide activities in this advanced nuclear power technology during 1998/1999, as reported at the 32. annual meeting of the International Working Group on Fast Reactors. It is intended to provide information regarding the current status of LMFR development in IAEA Member States.

  16. Status of national programmes on fast reactors 1998/99. 32nd annual meeting. Working material

    International Nuclear Information System (INIS)

    1999-01-01

    Over the past 32 years, the IAEA has actively encouraged and advocated international cooperation in fast reactor technology. The present publication contains information on the status of fast reactor development and on worldwide activities in this advanced nuclear power technology during 1998/1999, as reported at the 32. annual meeting of the International Working Group on Fast Reactors. It is intended to provide information regarding the current status of LMFR development in IAEA Member States

  17. Agenda 21 interim balance, 1997

    Energy Technology Data Exchange (ETDEWEB)

    Van Vuuren, D.P.; Bakkes, J.A.

    1997-10-01

    Five years after the `United Nations Conference on Environment and Development (UNCED)`, an interim balance was drawn up to see what was done to meet the ambitious challenges adopted in Agenda 21 during this conference. Such a balance is presented in this report and the complementary brochure, `Developments in Sustainability 1992-1997`, reflecting societal developments and changes in environmental quality, as well as changes in responses to environmental concerns. 24 figs., 12 tabs., 68 refs.

  18. Mission Status for Earth Science Constellation MOWG Meeting at KSC: EOS Aura

    Science.gov (United States)

    Fisher, Dominic

    2017-01-01

    This will be presented at the Earth Science Constellation Mission Operations Working Group (MOWG) meeting at KSC (Kennedy Space Center) in December 2017 to discus EOS (Earth Observing System) Aura status. Reviewed and approved by Eric Moyer, ESMO (Earth Sciences Mission Operations) Deputy Project Manager.

  19. Interim report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1985-06-01

    This Interim Report summarizes the research and development activities of the Superconducting Super Collider project carried out from the completion of the Reference Designs Study (May 1984) to June 1985. It was prepared by the SSC Central Design Group in draft form on the occasion of the DOE Annual Review, June 19--21, 1985. Now largely organized by CDG Divisions, the bulk of each chapter documents the progress and accomplishments to date, while the final section(s) describe plans for future work. Chapter 1, Introduction, provides a basic brief description of the SSC, its physics justification, its origins, and the R&D organization set up to carry out the work. Chapter 2 gives a summary of the main results of the R&D program, the tasks assigned to the four magnet R&D centers, and an overview of the future plans. The reader wishing a quick look at the SSC Phase I effort can skim Chapter 1 and read Chapter 2. Subsequent chapters discuss in more detail the activities on accelerator physics, accelerator systems, magnets and cryostats, injector, detector R&D, conventional facilities, and project planning and management. The magnet chapter (5) documents in text and photographs the impressive progress in successful construction of many model magnets, the development of cryostats with low heat leaks, and the improvement in current-carrying capacity of superconducting strand. Chapter 9 contains the budgets and schedules of the COG Divisions, the overall R&D program, including the laboratories, and also preliminary projections for construction. Appendices provide information on the various panels, task forces and workshops held by the CDG in FY 1985, a bibliography of COG and Laboratory reports on SSC and SSC-related work, and on private industrial involvement in the project.

  20. Status of national programmes on fast breeder reactors. Eighteenth annual meeting, Vienna, Austria, 16-19 April 1985

    International Nuclear Information System (INIS)

    1986-02-01

    The Eighteenth Annual Meeting on the Status of National Programmes in Member States of the IAEA on Fast Breeder Reactors had been held in April 1985. The representatives of the Member States and international organizations reported status and activities in the field of fast breeder reactors development and operation. A separate abstract was prepared for each of the 12 presentations of the meeting

  1. Fall meeting 2004: information conference on engines. Final and interim reports of the research centres; Herbsttagung 2004: Informationstagung Motoren. Abschluss- und Zwischenberichte der Forschungsstellen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    The Proceedings (volume R526, 2004) of the Information Conference on Engines which has been held on the 23rd September 2004 in Pforzheim/Germany, contains ten final and interim reports. The subjects of the contributions presented were as follow: particulate filter with NOx storage coating; cause study on damage-relevant knocking combustion; spray wall interaction; binaural transfer path analysis synthesis; acoustical optimized sealing-systems on engine acoustics; working process caused gas exchange noise; knowledge based diesel engine optimization; frontal press fit assemblies; case hardening and autofrettage; oil condition sensor (orig.)

  2. Do Interim Assessments Reduce the Race and SES Achievement Gaps?

    Science.gov (United States)

    Konstantopoulos, Spyros; Li, Wei; Miller, Shazia R.; van der Ploeg, Arie

    2017-01-01

    The authors examined differential effects of interim assessments on minority and low socioeconomic status students' achievement in Grades K-6. They conducted a large-scale cluster randomized experiment in 2009-2010 to evaluate the impact of Indiana's policy initiative introducing interim assessments statewide. The authors used 2-level models to…

  3. 33 CFR 385.38 - Interim goals.

    Science.gov (United States)

    2010-07-01

    ..., monitoring and assessment; (ii) Be provided to the independent scientific review panel established in.... The interim goals shall be developed through the use of appropriate models and tools and shall provide... to be required to meet long-term hydrological and ecological restoration goals, based on best...

  4. Ch-Ch-Ch-changes: how action phase functional leadership, team human capital, and interim vs. permanent leader status impact post-transition team performance

    OpenAIRE

    Maynard, M. Travis; Resick, Christian J.; Cunningham, Quinn W.; DiRenzo, Marco S.

    2017-01-01

    The article of record as published may be found at http://dx.doi.org/10.1007/s10869-016-9482-5 This study addresses the following: (1) does a team leader change along with the quality of the team’s human capital affect post-change team performance?; (2) is functional leadership of the team’s human capital a driver of post-change team performance?; and (3) should interim vs. permanent leaders manage the team’s human capital differently? We analyzed archival data from Major League Baseba...

  5. Spent fuel management: Current status and prospects 1997. Proceedings of a regular advisory group meeting

    International Nuclear Information System (INIS)

    1998-03-01

    Spent fuel management has always been one of the important stages in the nuclear fuel cycle and it is still most vital problems common to all countries with nuclear reactors. It begins with the discharge of spent fuel from a power or a research reactor and ends with its ultimate disposition. Two options exist - an open, once-through cycle with direct disposal of the spent fuel and a closed cycle with reprocessing of the spent fuel, recycling of reprocessed plutonium and uranium in new mixed oxide fuels and disposal of the radioactive waste. Continuous attention is being given by the IAEA to the collection, analysis and exchange of information on spent fuel management. Its role in this area is to provide a forum for exchanging information and to co-ordinate and to encourage closer co-operation among Member States in certain research and development activities that are of common interest. Spent fuel management is recognized as a high priority IAEA activity. The Regular Advisory Group on Spent Fuel Management was established in 1982. The objective of the Regular Advisory Group is to serve as a means of exchanging information on the current status and progress of national programmes on spent fuel management and to provide advice to the IAEA. The results of the last Regular Advisory Group meeting (9-12 September 1997) are reflected in this report. It gives an overview of the status of spent fuel management programmes in a number of countries, a description of the current status and prospects of activities in this field and recommendations of the participants

  6. Current Status and Open Issues of the 235U Evaluation. Summary Report of an IAEA Consultants’ Meeting

    International Nuclear Information System (INIS)

    Noguere, Gilles; Trkov, Andrej

    2016-08-01

    The objective of this consultancy meeting was to discuss the status of the 235 U neutron cross sections from the thermal to MeV energy ranges, to identify the main difficulties and to propose recommendations for improving the current experimental and evaluation works

  7. Weight status, gender, and race/ethnicity: are there differences in meeting recommended health behavior guidelines for adolescents?

    Science.gov (United States)

    Minges, Karl E; Chao, Ariana; Nam, Soohyun; Grey, Margaret; Whittemore, Robin

    2015-04-01

    Healthy behaviors including limited screen time (ST), high physical activity (PA), and adequate fruits and vegetables consumption (FV) are recommended for adolescents, but it is unclear how gender, race/ethnicity, and weight status relate to these public health guidelines in diverse urban adolescents. Participants (N = 384) were recruited from three public high schools in or near New Haven, Connecticut. Descriptive statistics and logistic regression analyses were conducted. Most adolescents exceeded recommended levels of ST (70.5%) and did not meet guidelines for PA (87.2%) and FV (72.6%). Only 3.5% of the sample met all three guidelines. Boys were more likely to meet guidelines for PA (p differences in meeting ST, PA, or FV guidelines by weight status for the overall sample or when stratified by gender or race/ethnicity. We found alarmingly low levels of healthy behaviors in normal weight and overweight/obese adolescents. © The Author(s) 2014.

  8. Meeting Recommended Levels of Physical Activity in Relation to Preventive Health Behavior and Health Status Among Adults

    Directory of Open Access Journals (Sweden)

    Peter D. Hart

    2017-01-01

    Full Text Available Objectives The purpose of this study was to examine the relationship of meeting the recommended levels of physical activity (PA with health status and preventive health behavior in adults. Methods A total of 5630 adults 18 years of age or older were included in this study. PA was assessed using a series of questions that categorized activities based on their metabolic equivalent values and then categorized individuals based on the reported frequency and duration of such activities. Participants reporting 150 minutes or more of moderate-intensity PA per week were considered to have met the PA guidelines. Multiple logistic regression was used to model the relationships between meeting PA guidelines and health status and preventive health behavior, while controlling for confounding variables. Results Overall, 53.9% (95% confidence interval [CI], 51.9 to 55.9% of adults reported meeting the recommended levels of PA. Among adults with good general health, 56.9% (95% CI, 54.7 to 59.1% reported meeting the recommended levels of PA versus 43.1% (95% CI, 40.9 to 45.3% who did not. Adults who met the PA guidelines were significantly more likely not to report high cholesterol, diabetes, chronic obstructive pulmonary disease, arthritis, asthma, depression, or overweight. Furthermore, adults meeting the PA guidelines were significantly more likely to report having health insurance, consuming fruits daily, consuming vegetables daily, and not being a current cigarette smoker. Conclusions In this study, we found meeting the current guidelines for PA to have a protective relationship with both health status and health behavior in adults. Health promotion programs should focus on strategies that help individuals meet the current guidelines of at least 150 minutes per week of moderate-intensity PA.

  9. Meeting

    Indian Academy of Sciences (India)

    July 1989 No.19 Newsletter of the Indian Academy of Sciences. 55th Annual. Meeting ... in the world, keeping alive atthe same time his research interests, abreast .... theory made a comeback with many new ideas and with the success of the ...

  10. CMM Interim Check (U)

    Energy Technology Data Exchange (ETDEWEB)

    Montano, Joshua Daniel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-03-23

    Coordinate Measuring Machines (CMM) are widely used in industry, throughout the Nuclear Weapons Complex and at Los Alamos National Laboratory (LANL) to verify part conformance to design definition. Calibration cycles for CMMs at LANL are predominantly one year in length. Unfortunately, several nonconformance reports have been generated to document the discovery of a certified machine found out of tolerance during a calibration closeout. In an effort to reduce risk to product quality two solutions were proposed – shorten the calibration cycle which could be costly, or perform an interim check to monitor the machine’s performance between cycles. The CMM interim check discussed makes use of Renishaw’s Machine Checking Gauge. This off-the-shelf product simulates a large sphere within a CMM’s measurement volume and allows for error estimation. Data was gathered, analyzed, and simulated from seven machines in seventeen different configurations to create statistical process control run charts for on-the-floor monitoring.

  11. CAST Status Report to the SPSC for the 119th Meeting

    CERN Document Server

    Karuza, Marin

    2015-01-01

    A status report for the CAST experiment in the year 2015 is presented. It includes the current status of the experiment concerning the detection of solar axions as well as the status of the proposed activities concerning relic axions and chameleons as a candidate particles invented to solve the mystery of the dark energy.

  12. The Nord interim store

    International Nuclear Information System (INIS)

    Leushacke, D.F.; Rittscher, D.

    1996-01-01

    In line with the decision taken in 1990 to shut down and decommission the Greifswald and Rheinsberg Nuclear Power Stations, the waste management concept of the Energiewerke Nord is based on direct and complete decommissioning of the six shut down reactor units within the next fifteen years. One key element of this concept is the construction and use of the Zwischenlager Nord (Nord Interim Store, ZLN) for holding the existing nuclear fuels and for interim and decay storage of the radioactive materials arising in decommissioning and demolition. The owner and operator of the store is Energiewerke Nord GmbH. The interim store has the functions of a processing and Energiewerke Nord GmbH. The interim store has the functions of a processing and treatment station and buffer store for the flows of residues arising. As a radioactive waste management station, it accommodates nuclear fuels, radioactive waste or residues which are not treated any further. It is used as a buffer store to allow the materials accumulating in disassembly to be stored temporarily before or after treatment in order to ensure continuous loading of the treatment plants. When operated as a processing station, the ZLN is able to handle nearly all types of radioactive waste and residues arising, except for nuclear fuels. These installations allow the treatment of radioactive residues to be separated from the demolition work both physically and in time. The possibilities of interium storage and buffer storage of untreated waste and waste packages make for high flexibility in logistics and waste management strategy. (orig.) [de

  13. Gaz de France interim financial report 2007

    International Nuclear Information System (INIS)

    2007-01-01

    This financial report contains the unaudited condensed financial statements of Gaz de France Group for the first half ended June 30, 2007, which were reviewed by the audit committee on August 27, 2007 and by the board of directors at its meeting on August 28, 2007. It includes forward-looking statements concerning the objectives, strategies, financial position, future operating results and the operations of Gaz de France Group. These statements reflect the Group's current perception of its activities and the markets in which it operates, as well as various estimates and assumptions considered to be reasonable. Content: interim management report (highlights of the first half of 2007, revenues and results for the period, financial structure, data on outstanding stock, outlook); interim consolidated financial statements (consolidated statements of income, consolidated balance sheets, consolidated statements of cash flows, recognized income and expenses, statements of changes in shareholders' equity, note to the consolidated financial statements); statement by the person responsible for the interim financial report; statutory auditors' report. (J.S.)

  14. Status of environmental technology; Interim Report to the sector study 'Petroleum and Energy', the integrated management plan for North Sea. Mapping of available environmental technology; Statusrapport for miljoeteknologi

    Energy Technology Data Exchange (ETDEWEB)

    2011-03-15

    The purpose of this report is to provide an overview of the current status of environmental technology that may help to prevent and reduce / prevent environmental pollution. The report is a foundation report to the management plan for the North Sea. The report was prepared based on the NPD's knowledge and with good input from the PSA, and resource persons in the oil companies. The following is given a summary of the various disciplines and the technological challenges the industry has managed to meet and which ones remain. (Author)

  15. Summary of the meeting status of static reactor calculations in Nordic countries

    International Nuclear Information System (INIS)

    Lindahl, S.-Oe.

    1983-02-01

    Some impressions of the material presented at the meeting are given. The covered areas were as follows: in-core fuel management, cross section generation, burnable absorbers nodal models, pin power calculations and benchmarking. (Author)

  16. Interim storage study report

    Energy Technology Data Exchange (ETDEWEB)

    Rawlins, J.K.

    1998-02-01

    High-level radioactive waste (HLW) stored at the Idaho Chemical Processing Plant (ICPP) in the form of calcine and liquid and liquid sodium-bearing waste (SBW) will be processed to provide a stable waste form and prepare the waste to be transported to a permanent repository. Because a permanent repository will not be available when the waste is processed, the waste must be stored at ICPP in an Interim Storage Facility (ISF). This report documents consideration of an ISF for each of the waste processing options under consideration.

  17. Interim storage report

    International Nuclear Information System (INIS)

    Rawlins, J.K.

    1998-02-01

    High-level radioactive waste (HLW) stored at the Idaho Chemical Processing Plant (ICPP) in the form of calcine and liquid and liquid sodium-bearing waste (SBW) will be processed to provide a stable waste form and prepare the waste to be transported to a permanent repository. Because a permanent repository will not be available when the waste is processed, the waste must be stored at ICPP in an Interim Storage Facility (ISF). This report documents consideration of an ISF for each of the waste processing options under consideration

  18. An interim report on the State of Nevada socioeconomic studies

    International Nuclear Information System (INIS)

    1989-06-01

    This Interim Report is a report on work in progress and presents findings from the research to date on the potential consequences of a repository for the citizens of Nevada. The research and findings in the Report have been subjected to rigorous peer review as part of the state's effort to insure independent, objective analysis that meets the highest professional standards. The basic research effort will continue through June 1990 and will enable the state to refine and clarify the findings presented in this Interim Report

  19. Safety evaluation of interim stabilization of non-stabilized single-shell watch list tanks

    Energy Technology Data Exchange (ETDEWEB)

    Stahl, S.M.

    1994-12-30

    The report provides a summation of the status of safety issues associated with interim stabilization of Watch List SSTs (organic, ferrocyanide, and flammable gas), as extracted from recent safety analyses, including the Tank Farms Accelerated Safety Analysis efforts.

  20. Safety evaluation of interim stabilization of non-stabilized single-shell watch list tanks

    International Nuclear Information System (INIS)

    Stahl, S.M.

    1994-01-01

    The report provides a summation of the status of safety issues associated with interim stabilization of Watch List SSTs (organic, ferrocyanide, and flammable gas), as extracted from recent safety analyses, including the Tank Farms Accelerated Safety Analysis efforts

  1. Tumor radiosensitizers - current status of development of various approaches: Report of an International Atomic Energy Agency meeting

    DEFF Research Database (Denmark)

    Horsman, Michael Robert; Bohm, Lothar; Margison, Geoffrey P.

    2006-01-01

    PURPOSE: The International Atomic Energy Agency (IAEA) held a Technical Meeting of Consultants to (1) discuss a selection of relatively new agents, not those well-established in clinical practice, that operated through a variety of mechanisms to sensitize tumors to radiation and (2) to compare...... and contrast their tumor efficacy, normal tissue toxicity, and status of development regarding clinical application. The aim was to advise the IAEA as to which developing agent or class of agents would be worth promoting further, by supporting additional laboratory research or clinical trials...... and for clinical trials that would be suitable for industrialized countries, as well as trials that were considered more appropriate for developing countries.PURPOSE: The International Atomic Energy Agency (IAEA) held a Technical Meeting of Consultants to (1) discuss a selection of relatively new agents, not those...

  2. Spent fuel interim storage

    International Nuclear Information System (INIS)

    Bilegan, Iosif C.

    2003-01-01

    The official inauguration of the spent fuel interim storage took place on Monday July 28, 2003 at Cernavoda NNP. The inaugural event was attended by local and central public authority representatives, a Canadian Government delegation as well as newsmen from local and central mass media and numerous specialists from Cernavoda NPP compound. Mr Andrei Grigorescu, State Secretary with the Economy and Commerce Ministry, underlined in his talk the importance of this objective for the continuous development of nuclear power in Romania as well as for Romania's complying with the EU practice in this field. Also the excellent collaboration between the Canadian contractor AECL and the Romanian partners Nuclear Montaj, CITON, UTI, General Concret in the accomplishment of this unit at the planned terms and costs. On behalf of Canadian delegation, spoke Minister Don Boudria. He underlined the importance which the Canadian Government affords to the cooperation with Romania aiming at specific objectives in the field of nuclear power such as the Cernavoda NPP Unit 2 and spent fuel interim storage. After traditional cutting of the inaugural ribbon by the two Ministers the festivities continued on the Cernavoda NPP Compound with undersigning the documents regarding the project completion and a press conference

  3. EOS Aura Mission Status at Earth Science Constellation MOWG Meeting @ LASP (Boulder, CO) April 13, 2016

    Science.gov (United States)

    Guit, William J.; Fisher, Dominic

    2016-01-01

    Presentation reflects EOS Aura mission status, spacecraft subsystems summary, recent and planned activities, inclination adjust maneuvers, propellant usage, orbit maintenance maneuvers, conjunction assessment events, orbital parameters trends and predictions.

  4. EOS Aqua Mission Status at Earth Science Constellation MOWG Meeting @ LASP April 13, 2016

    Science.gov (United States)

    Guit, William J.

    2016-01-01

    This presentation reflects the EOS Aqua mission status, spacecraft subsystem summary, recent and planned activities, inclination adjust maneuvers, propellant usage and lifetime estimate, orbital maintenance maneuvers, conjunction assessment high interest events, ground track error, spacecraft orbital parameters trends and predictions.

  5. Impact of socio-economic status in meeting the needs of people with mental illness; human rights perspective.

    Science.gov (United States)

    Vijayalakshmi, Poreddi; Ramachandra; Reddemma, Konduru; Math, Suresh Bada

    2014-04-01

    The present descriptive study investigated the impact of socio-economic status in meeting the human rights needs among randomly selected recovered psychiatric patients (n = 100) at a tertiary care center. Data was collected through face to face interview, using structured Needs Assessment Questionnaire. The findings revealed that the participants from below poverty line were deprived of physical needs such as 'electricity facilities' (χ (2) = 6.821, p physical appearance (χ (2) = 8.337, p employment, disability pension, free housing, free treatment and free transportation service for people with mental illness to attend hospital or rehabilitation centres.

  6. Status and prospects for gas cooled reactor fuels. Proceedings of two IAEA meetings held in June 2004 and June 2005

    International Nuclear Information System (INIS)

    2009-04-01

    Recently, efforts to develop high temperature gas cooled reactors with an aim to building futuristic nuclear energy systems with advanced nuclear fuel cycles in the context of the Generation IV International Forum have increased significantly. In addition, several development projects are ongoing, focusing on the burning of weapons grade plutonium, including civil plutonium and other transuranic elements using the 'deep-burn concept', or 'inert matrix fuels', especially in the form of coated particles in gas cooled reactor systems. There is also considerable global interest in developing 'nuclear hydrogen' energy systems using high temperature gas cooled reactors. Apart from these developments, the value of preserving the large technology base developed in Germany, the United Kingdom and the United States of America, as well as information developed in other countries, has also been a subject of interest to the IAEA. At the second annual meeting of the 'technical working group on nuclear fuel cycles options and spent fuel management' (TWG-NFCO), held in Vienna from 28-30 May 2003, it was recommended to hold a technical meeting on Current Status and Future Prospects of Gas Cooled Reactor Fuels. The meeting should cover the technological progress that has been made in the last three years and plan future fabrication and qualification facilities for GCR/HTR fuel. TWG-NFCO considered it timely that this progress should be presented and discussed in the interested community. Recognizing the numerous activities being pursued in many Member States, the IAEA convened the technical meeting on this topic in June 2004 in Vienna. Consequently, an update meeting was held in June 2005, which was hosted by the Kharkov Institute of Physics and Technology of Ukraine to review and integrate the latest developments. This publication combines the results of the technical meeting of June 2004 and the meeting of June 2005. The proceedings presented here contain 25 in depth papers on the

  7. Status of Galileo interim radiation electron model

    Science.gov (United States)

    Garrett, H. B.; Jun, I.; Ratliff, J. M.; Evans, R. W.; Clough, G. A.; McEntire, R. W.

    2003-01-01

    Measurements of the high energy, omni-directional electron environment by the Galileo spacecraft Energetic Particle Detector (EDP) were used to develop a new model of Jupiter's trapped electron radiation in the jovian equatorial plane for the range 8 to 16 Jupiter radii.

  8. NMSBA Leveraged Project Interim Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Ivanov, Sergei A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-10-05

    We have investigated the quality of copper particles available on the market today and determined their complete unsuitability to be used for copper inks, since all of them were significantly oxidized: there was only 50% of metallic copper in each batch and the rest was Cu2O and CuO. To date, we have fully identified the challenges and developed the synthesis for large amounts of the copper ink precursor, namely, copper(I) mesityl. Currently, the amounts of tens of grams of the precursor have been obtained. From this precursor, four small batches of copper nanoparticles (50 mg each) have been synthesized to investigate the possibility of decreasing particle sensitivity to oxygen. These particles have been treated with different surface-stabilizing agents (namely, octylamine, oleylamine, pyridine, benzotriazole, and dodecanethiol) in order to investigate their influence on particle oxygen sensitivity. A batch of copper nanoparticles in the amount of 2 grams has also been synthesized in order to start preparation of test ink batches with different solvents, surfactants, and stabilizers.

  9. ETF interim design review

    International Nuclear Information System (INIS)

    Steiner, D.; Rutherford, P.H.

    1980-01-01

    A three-day ETF Interim Design Review was conducted on July 23-25, 1980, at the Sheraton Potomac Inn in Rockville, Maryland. The intent of the review was to provide a forum for an in-depth assessment and critique of all facets of the ETF design by members of the fusion community. The review began with an opening plenary session at which an overview of the ETF design was presented by D. Steiner, manager of the ETF Design Center, complemented by a physics overview by P.H. Rutherford, chairman of the ETF/INTOR Physics Committee. This was followed by six concurrent review sessions over the next day and a half. The review closed with a plenary session at which the Design Review Board presented its findings. This document consists of the viewgraphs for the opening plenary session and an edited version of the presentations made by Steiner and Rutherford

  10. Interim geotechnical data report

    International Nuclear Information System (INIS)

    1986-01-01

    This issue, the Interim Geotechnical Field Data Report, presents information obtained from the geotechnical activities at the WIPP site underground facilities since the last quarterly report. It also includes cumulative plots which contain all previous data. Finally, it continues the geotechnical analyses and interpretations of the data. The GFDR is organized into two principal parts. The first part, Geotechnical Field Data, presents in graphical form all the data collected since April 1982 from the geomechanical instruments. Presented in the second part, Evaluation and Analyses, are preliminary interpretations and analyses of the data. In this report, continuing geotechnical assessment of all the facility features is presented. Also included in the second part are separate sections on evaluation and interpretation of the instrumentation measurements, and an updated description and evaluation of observed behavior of the underground openings

  11. Federal Interim Storage program

    International Nuclear Information System (INIS)

    Johnson, E.R.; McBride, J.A.

    1984-01-01

    The DOE has developed a program for providing Federal Interim Storage servies for spent nuclear fuel which complies with the requirements of the Nuclear Waste Policy Act of 1982. Although very little constructive activity in providing storage facilities can be undertaken by DOE until fuel has been certified by NRC as eligible for FIS, DOE planning and background information is such as to provide reasonable assurance that its obligations can be fulfilled when the required certifications have been issued. A fee structure providing fuel recovery of all costs associated with the FIS program, as required by the Act, has been developed. It provides for an equitable distribution of costs among users, based on the quantity of fuel requiring storage

  12. Both Mother and Infant Require a Vitamin D Supplement to Ensure That Infants' Vitamin D Status Meets Current Guidelines.

    Science.gov (United States)

    Aghajafari, Fariba; Field, Catherine J; Weinberg, Amy R; Letourneau, Nicole

    2018-03-29

    We examined the association between maternal vitamin D intake during breastfeeding with their infants' vitamin D status in infants who did or did not receive vitamin D supplements to determine whether infant supplementation was sufficient. Using plasma from a subset of breastfed infants in the APrON (Alberta Pregnant Outcomes and Nutrition) cohort, vitamin D status was measured by liquid chromatography-tandem mass spectrometry. Maternal and infants' dietary data were obtained from APrON's dietary questionnaires. The median maternal vitamin D intake was 665 International Units (IU)/day, while 25% reported intakes below the recommended 400 IU/day. Of the 224 infants in the cohort, 72% were exclusively breastfed, and 90% were receiving vitamin D supplements. Infants' median 25(OH)D was 96.0 nmol/L (interquartile ranges (IQR) 77.6-116.2), and 25% had 25(OH)D < 75 nmol/L. An adjusted linear regression model showed that, with a 100 IU increase in maternal vitamin D intake, infants' 25(OH)D increased by 0.9 nmol/L controlling for race, season, mid-pregnancy maternal 25(OH)D, birthweight, and whether the infant received daily vitamin D supplement (β = 0.008, 95% confidence interval (CI) 0.002, 0.13). These results suggest that, to ensure infant optimal vitamin D status, not only do infants require a supplement, but women also need to meet current recommended vitamin D intake during breastfeeding.

  13. Both Mother and Infant Require a Vitamin D Supplement to Ensure That Infants’ Vitamin D Status Meets Current Guidelines

    Directory of Open Access Journals (Sweden)

    Fariba Aghajafari

    2018-03-01

    Full Text Available We examined the association between maternal vitamin D intake during breastfeeding with their infants’ vitamin D status in infants who did or did not receive vitamin D supplements to determine whether infant supplementation was sufficient. Using plasma from a subset of breastfed infants in the APrON (Alberta Pregnant Outcomes and Nutrition cohort, vitamin D status was measured by liquid chromatography-tandem mass spectrometry. Maternal and infants’ dietary data were obtained from APrON’s dietary questionnaires. The median maternal vitamin D intake was 665 International Units (IU/day, while 25% reported intakes below the recommended 400 IU/day. Of the 224 infants in the cohort, 72% were exclusively breastfed, and 90% were receiving vitamin D supplements. Infants’ median 25(OHD was 96.0 nmol/L (interquartile ranges (IQR 77.6–116.2, and 25% had 25(OHD < 75 nmol/L. An adjusted linear regression model showed that, with a 100 IU increase in maternal vitamin D intake, infants’ 25(OHD increased by 0.9 nmol/L controlling for race, season, mid-pregnancy maternal 25(OHD, birthweight, and whether the infant received daily vitamin D supplement (β = 0.008, 95% confidence interval (CI 0.002, 0.13. These results suggest that, to ensure infant optimal vitamin D status, not only do infants require a supplement, but women also need to meet current recommended vitamin D intake during breastfeeding.

  14. Both Mother and Infant Require a Vitamin D Supplement to Ensure That Infants’ Vitamin D Status Meets Current Guidelines

    Science.gov (United States)

    Weinberg, Amy R.; Letourneau, Nicole

    2018-01-01

    We examined the association between maternal vitamin D intake during breastfeeding with their infants’ vitamin D status in infants who did or did not receive vitamin D supplements to determine whether infant supplementation was sufficient. Using plasma from a subset of breastfed infants in the APrON (Alberta Pregnant Outcomes and Nutrition) cohort, vitamin D status was measured by liquid chromatography-tandem mass spectrometry. Maternal and infants’ dietary data were obtained from APrON’s dietary questionnaires. The median maternal vitamin D intake was 665 International Units (IU)/day, while 25% reported intakes below the recommended 400 IU/day. Of the 224 infants in the cohort, 72% were exclusively breastfed, and 90% were receiving vitamin D supplements. Infants’ median 25(OH)D was 96.0 nmol/L (interquartile ranges (IQR) 77.6–116.2), and 25% had 25(OH)D < 75 nmol/L. An adjusted linear regression model showed that, with a 100 IU increase in maternal vitamin D intake, infants’ 25(OH)D increased by 0.9 nmol/L controlling for race, season, mid-pregnancy maternal 25(OH)D, birthweight, and whether the infant received daily vitamin D supplement (β = 0.008, 95% confidence interval (CI) 0.002, 0.13). These results suggest that, to ensure infant optimal vitamin D status, not only do infants require a supplement, but women also need to meet current recommended vitamin D intake during breastfeeding. PMID:29596362

  15. NASA Dryden Status: Aerospace Control and Guidance Sub-Committee Meeting 109

    Science.gov (United States)

    Jacobson, Steven R.

    2012-01-01

    NASA Dryden has been engaging in some exciting work that will enable lighter weight and more fuel efficient vehicles through advanced control and dynamics technologies. The main areas of emphasis are Enabling Light-weight Flexible Structures, real time control surface optimization for fuel efficiency and autonomous formation flight. This presentation provides a description of the current and upcoming work in these areas. Additionally, status is for the Dreamchaser pilot training activity and KQ-X autonomous aerial refueling.

  16. IAEA Technical Meeting on Status of IAEA Fast Reactor Knowledge Preservation Initiative. Presentations

    International Nuclear Information System (INIS)

    2013-01-01

    The objectives of the technical meeting were to: • exchange information between the Member States/International Organizations on national and international initiatives addressing knowledge preservation and data retrieval/collection in the field of fast neutron systems; • present and discuss the Member States’/International Organizations’ policies and conditions for releasing to the IAEA both publicly available and confidential information on fast neutron systems; • collect data on fast neutron systems provided by participating Member States/International Organizations and encourage participants to contribute in data collection; • provide recommendations for further IAEA initiatives in the field of fast reactor knowledge preservation

  17. Project management plan for Reactor 105-C Interim Safe Storage project

    International Nuclear Information System (INIS)

    Plagge, H.A.

    1996-09-01

    Reactor 105-C (located on the Hanford Site in Richland, Washington) will be placed into an interim safe storage condition such that (1) interim inspection can be limited to a 5-year frequency; (2) containment ensures that releases to the environmental are not credible under design basis conditions; and (3) final safe storage configuration shall not preclude or significantly increase the cost for any decommissioning alternatives for the reactor assembly.This project management plan establishes plans, organizational responsibilities, control systems, and procedures for managing the execution of Reactor 105-C interim safe storage activities to meet programmatic requirements within authorized funding and approved schedules

  18. Spent fuel management: Current status and prospects 1995. Proceedings of a regular advisory group meeting

    International Nuclear Information System (INIS)

    1996-08-01

    Spent fuel management has always been one of the important stages in the nuclear fuel cycle and it is still one of the most vital problems common to all countries with nuclear reactors. It begins with the discharge of spent fuel from a power or a research reactor and ends with its ultimate disposition, either by direct disposal or by reprocessing of the spent fuel. Two options exist - an open, once-through cycle with direct disposal of the spent fuel and a closed cycle with reprocessing of the spent fuel and recycling of plutonium and uranium in new mixed oxide fuels. The selection of a spent fuel strategy is a complex procedure in which many factors have to be weighed, including political, economic and safeguards issues as well as protection of the environment. This report gives an overview of the status of spent fuel management programmes in a number of countries, a description of the current status and prospects of activities in this field and recommendations of the participants. Refs, figs, tabs

  19. Interim Design Report

    CERN Document Server

    Choubey, S.; Goswami, S.; Berg, J.S.; Fernow, R.; Gallardo, J.C.; Gupta, R.; Kirk, H.; Simos, N.; Souchlas, N.; Ellis, M.; Kyberd, P.; Benedetto, E.; Fernandez-Martinez, E.; Efthymiopoulos, I.; Garoby, R.; Gilardoni, S.; Martini, M.; Prior, G.; Ballett, P.; Pascoli, S.; Bross, A.; Geer, S.; Johnstone, C.; Kopp, J.; Mokhov, N.; Morfin, J.; Neuffer, D.; Parke, S.; Popovic, M.; Strait, J.; Striganov, S.; Blondel, A.; Dufour, F.; Laing, A.; Soler, F.J.P; Lindner, M.; Schwetz, T.; Alekou, A.; Apollonio, M.; Aslaninejad, M.; Bontoiu, C.; Dornan, P.; Eccleston, R.; Kurup, A.; Long, K.; Pasternak, J.; Pozimski, J.; Bogacz, A.; Morozov, V.; Roblin, Y.; Bhattacharya, S.; Majumdar, D.; Mori, Y.; Planche, T.; Zisman, M.; Cline, D.; Stratakis, D.; Ding, X.; Coloma, P.; Donini, A.; Gavela, B.; Lopez Pavon, J.; Maltoni, M.; Bromberg, C.; Bonesini, M.; Hart, T.; Kudenko, Y.; Mondal, N.; Antusch, S.; Blennow, M.; Ota, T.; Abrams, R.J.; Ankenbrandt, C.M.; Beard, K.B.; Cummings, M.A.C.; Flanagan, G.; Johnson, R.P.; Roberts, T.J.; Yoshikawa, C.Y.; Migliozzi, P.; Palladino, V.; de Gouvea, A.; Graves, V.B.; Kuno, Y.; Peltoniemi, J.; Blackmore, V.; Cobb, J.; Witte, H.; Mezzetto, M.; Rigolin, S.; McDonald, K.T.; Coney, L.; Hanson, G.; Snopok, P.; Tortora, L.; Andreopoulos, C.; Bennett, J.R.J.; Brooks, S.; Caretta, O.; Davenne, T.; Densham, C.; Edgecock, R.; Kelliher, D.; Loveridge, P.; McFarland, A.; Machida, S.; Prior, C.; Rees, G.; Rogers, C.; Thomason, J.W.G.; Booth, C.; Skoro, G.; Karadzhov, Y.; Matev, R.; Tsenov, R.; Samulyak, R.; Mishra, S.R.; Petti, R.; Dracos, M.; Yasuda, O.; Agarwalla, S.K.; Cervera-Villanueva, A.; Gomez-Cadenas, J.J.; Hernandez, P.; Li, T.; Martin-Albo, J.; Huber, P.; Back, J.; Barker, G.; Harrison, P.; Meloni, D.; Tang, J.; Winter, W.

    2011-01-01

    The International Design Study for the Neutrino Factory (the IDS-NF) was established by the community at the ninth "International Workshop on Neutrino Factories, super-beams, and beta- beams" which was held in Okayama in August 2007. The IDS-NF mandate is to deliver the Reference Design Report (RDR) for the facility on the timescale of 2012/13. In addition, the mandate for the study [3] requires an Interim Design Report to be delivered midway through the project as a step on the way to the RDR. This document, the IDR, has two functions: it marks the point in the IDS-NF at which the emphasis turns to the engineering studies required to deliver the RDR and it documents baseline concepts for the accelerator complex, the neutrino detectors, and the instrumentation systems. The IDS-NF is, in essence, a site-independent study. Example sites, CERN, FNAL, and RAL, have been identified to allow site-specific issues to be addressed in the cost analysis that will be presented in the RDR. The choice of example sites shou...

  20. Status of national programmes on fast reactors 1997/98. 31. annual meeting of the International Working Group on Fast Reactors

    International Nuclear Information System (INIS)

    1998-01-01

    The objective of the meeting was to co-ordinate the exchange of information on the status of fast reactor development and operational experience, including experience with experimental types of reactor; to consider meeting arrangements for 1998 and 1999; and to review the IAEA co-ordinated research activities in the field of fast reactor, as well as co-ordination of the International Working Group on Fast Reactors activities with other organizations

  1. Status of industrial scale radiation treatment of wastewater and its future. Proceedings of a consultants meeting

    International Nuclear Information System (INIS)

    2004-09-01

    Providing access to clean water resources is one of the most important objectives of the UN's Millennium Project. Contamination of surface water is a big problem for many, mostly developing countries. The main sources of liquid polluted effluents are municipalities and industry. Effective, mostly biological wastewater technologies for wastewater purification are available nowadays. However, they cannot be applied to solve all existing problems. Destruction of non-biodegradable organic compounds is one problem and biological contamination (caused by viruses, bacteria, parasites, etc.) of sludge is another. Methods of their purification are sought. Ionizing radiation (gamma or X rays, electron beams) is a very effective form of energy, which can destroy organic or biological contaminants. The IAEA promotes and supports research on radiation treatment of liquid effluents. The Coordinated Research Project (CRP) on Remediation of Polluted Waters and Wastewater by Radiation Processing aims to establish optimal treatment methodologies to disinfect and decontaminate actual samples of drinking water and wastewater by using ionizing radiation. Quite a few technical cooperation (TC) projects concerning radiation treatment of wastewater and sludge are under development. In the frame of one of such TC projects pilot plant for electron beam treatment of textile dyeing complex wastewater was constructed in the Republic of Korea. To discuss developments achieved under these projects and results of the pilot plant operation, the IAEA organized a consultants meeting in Daejon, Republic of Korea, 13-16 October 2003. These proceedings will be of value to research groups working in the field of radiation technology development. Developing Member States with radiation technology programmes will benefit from research in this area. The meeting dealt with advanced radiation processing of wastewater and its technical and economical aspects. It informed about high power accelerators ELV-12

  2. CAST Status Report to the SPSC for the 123rd Meeting

    CERN Document Server

    Desch, K

    2016-01-01

    After the successful 2015 data taking with Micromegas detectors, targeting solar axion search, and with an InGrid detector, targeting solar chameleon search, CAST has started on its new 2016-2018 program which has been presented to SPSC at the 119th meeting in October 2015. This program extends the physics goals of CAST towards the search for solar chameleons using a force sensor (KWISP) and towards the search for relic axions using a microwave cavity inserted into the CAST magnet (CAST-CAPP). The search for solar chameleons and other axion-like particles was continued with a significantly upgraded InGrid detector. The new experiments make use different elements of the unique CAST infrastructure (KWISP: Abrixas XRT and sun pointing capability of CAST, CAST-CAPP: high magnetic dipole field), while the InGrid detector exploits all of CAST´s features (Abrixas XRT, high magnetic dipole field, sun pointing). All three experiments within CAST have made significant progress in exploring these new approaches in 2016...

  3. AGR-1 Data Qualification Interim Report

    International Nuclear Information System (INIS)

    Abbott, Machael

    2009-01-01

    Projects for the very-high-temperature reactor (VHTR) program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR Program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are (1) qualified for use, (2) stored in a readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the data streams associated with the first Advanced Gas Reactor (AGR-1) experiment, the processing of these data within NDMAS, and reports the interim FY09 qualification status of the AGR-1 data to date. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category, which is assigned by the data generator, and include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing, to confirm that the data are an accurate representation of the system or object being measured, and (3) documentation that the data were collected under an NQA-1 or equivalent QA program. The interim qualification status of the following four data streams is reported in this document: (1) fuel fabrication data, (2) fuel irradiation data, (3) fission product monitoring system (FPMS) data, and (4) Advanced Test Reactor (ATR) operating conditions data. A final report giving the NDMAS qualification status of all AGR-1 data (including cycle 145A) is planned for February 2010

  4. 24 CFR 35.1330 - Interim controls.

    Science.gov (United States)

    2010-04-01

    ... Lead-Paint Hazard Evaluation and Hazard Reduction Activities § 35.1330 Interim controls. Interim..., cleanable covering or coating, such as metal coil stock, plastic, polyurethane, or linoleum. (3) Surfaces...

  5. Radioactive waste interim storage in Germany

    International Nuclear Information System (INIS)

    2015-12-01

    The short summary on the radioactive waste interim storage in Germany covers the following issues: importance of interim storage in the frame of radioactive waste management, responsibilities and regulations, waste forms, storage containers, transport of vitrified high-level radioactive wastes from the reprocessing plants, central interim storage facilities (Gorleben, Ahaus, Nord/Lubmin), local interim storage facilities at nuclear power plant sites, federal state collecting facilities, safety, radiation exposure in Germany.

  6. IAEA Technical Meeting on Status of IAEA Fast Reactor Knowledge Preservation Initiative. Working Material

    International Nuclear Information System (INIS)

    2013-01-01

    In response to needs expressed by Member States and within a broader IAEA-wide effort in nuclear knowledge preservation, the IAEA has been carrying out a dedicated initiative on Fast Reactor Data Knowledge Preservation (FRKP). The main objectives of the FRKP initiative are to: • Halt the on-going loss of information related to Fast Reactors (FR); • Collect, retrieve, preserve and make accessible already existing data and information on FR. These objectives require the implementation of activities supporting digital document archival, exchange, search and retrieval and facilitating, by developing and using suitable standards and IT tools, the knowledge preservation over the next decades. To this purpose the IAEA has developed the Fast Reactor Knowledge Organization System (FRKOS), a web-based application employing IAEA methodology and approach for categorization of FR knowledge domain, which allows creating a comprehensive and well-structured international inventory of fast reactor data and information provided by different Member States. The resulting Web Portal is established and maintained by the IAEA. The IAEA knowledge preservation initiatives and tools in the field of fast neutron systems - which were presented and very well received during the recent IAEA Fast Reactor and Related Fuel Cycles Conference (FR13) - are supposed to be of interest for national nuclear authorities, regulators, scientific and research organizations, commercial companies and all other stakeholders involved in fast reactor activities at national or international level. The objectives of the technical meeting were to: • Exchange information between the member states/international organizations on national and international initiatives addressing knowledge preservation and data retrieval/collection in the field of fast neutron systems; • Present and discuss the member states’/international organizations’ policies and conditions for releasing to the IAEA both publicly

  7. 7 CFR 1735.75 - Interim financing.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 11 2010-01-01 2010-01-01 false Interim financing. 1735.75 Section 1735.75... Involving Loan Funds § 1735.75 Interim financing. (a) A borrower may submit a written request for RUS approval of interim financing if it is necessary to close an acquisition before the loan to finance the...

  8. 7 CFR 1738.21 - Interim financing.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 11 2010-01-01 2010-01-01 false Interim financing. 1738.21 Section 1738.21... Interim financing. (a) Upon notification by RUS that an applicant's application is considered complete, the applicant may enter into an interim financing agreement with a lender other than RUS or use its...

  9. Status of liquid metal fast reactor development. Proceedings of the 27. meeting of the International Working Group on Fast Reactors held in Vienna, 17-19 May 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-03-01

    These proceedings contain updated and new information on the status of fast reactor development and on activities in the field of advanced nuclear power technology during 1993, as reported at the 27th meeting of the IWGFR held in Vienna, from 17 to 19 May 1994. Refs, figs and tabs.

  10. Status of liquid metal fast reactor development. Proceedings of the 27. meeting of the International Working Group on Fast Reactors held in Vienna, 17-19 May 1994

    International Nuclear Information System (INIS)

    1995-03-01

    These proceedings contain updated and new information on the status of fast reactor development and on activities in the field of advanced nuclear power technology during 1993, as reported at the 27th meeting of the IWGFR held in Vienna, from 17 to 19 May 1994. Refs, figs and tabs

  11. EOS Aqua: Mission Status at the Earth Science Constellation (ESC) Mission Operations Working Group (MOWG) Meeting at the Kennedy Space Center (KSC)

    Science.gov (United States)

    Guit, Bill

    2017-01-01

    This presentation at the Earth Science Constellation Mission Operations Working Group meeting at KSC in December 2017 to discuss EOS (Earth Observing System) Aqua Earth Science Constellation status. Reviewed and approved by Eric Moyer, ESMO (Earth Science Mission Operations) Deputy Project Manager.

  12. Terrestrial gravity data analysis for interim gravity model improvement

    Science.gov (United States)

    1987-01-01

    This is the first status report for the Interim Gravity Model research effort that was started on June 30, 1986. The basic theme of this study is to develop appropriate models and adjustment procedures for estimating potential coefficients from terrestrial gravity data. The plan is to use the latest gravity data sets to produce coefficient estimates as well as to provide normal equations to NASA for use in the TOPEX/POSEIDON gravity field modeling program.

  13. Tumor radiosensitizers-current status of development of various approaches: Report of an International Atomic Energy Agency meeting

    International Nuclear Information System (INIS)

    Horsman, Michael R.; Bohm, Lothar; Margison, Geoffrey P.; Milas, Luka; Rosier, Jean-Francois; Safrany, Geza; Selzer, Edgar; Verheij, Marcel; Hendry, Jolyon H.

    2006-01-01

    Purpose: The International Atomic Energy Agency (IAEA) held a Technical Meeting of Consultants to (1) discuss a selection of relatively new agents, not those well-established in clinical practice, that operated through a variety of mechanisms to sensitize tumors to radiation and (2) to compare and contrast their tumor efficacy, normal tissue toxicity, and status of development regarding clinical application. The aim was to advise the IAEA as to which developing agent or class of agents would be worth promoting further, by supporting additional laboratory research or clinical trials, with the eventual goal of improving cancer control rates using radiotherapy, in developing countries in particular. Results: The agents under discussion included a wide, but not complete, range of different types of drugs, and antibodies that interfered with molecules in cell signaling pathways. These were contrasted with new molecular antisense and gene therapy strategies. All the drugs discussed have previously been shown to act as tumor cell radiosensitizers or to kill hypoxic cells present in tumors. Conclusion: Specific recommendations were made for more preclinical studies with certain of the agents and for clinical trials that would be suitable for industrialized countries, as well as trials that were considered more appropriate for developing countries

  14. Remedial design report and remedial action work plan for the 100-HR-3 and 100-KR-4 groundwater operable units' interim action

    International Nuclear Information System (INIS)

    1996-09-01

    This document is a combination remedial design report and remedial action work plan for the 100-HR-3 and 100-KR-4 Operable Units (located on the Hanford Site in Richland, Washington) interim action. The interim actions described in this document represent the first of an ongoing program to address groundwater contamination in each operable unit. This document describes the design basis, provides a description of the interim action, and identifies how they will meet the requirements set forth in the interim action Record of Decision

  15. Status and risk assessment of the use of transgenic arthropods in plant protection. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2006-03-01

    New developments in the modern biotechnology have opened up the possibility of introducing genes into the germline of many insect species, including those of agricultural importance. This technology offers the potential to improve current pest control strategies that incorporate the Sterile Insect Technique (SIT). Potential improvements include the development of strains that (1) produce only male insects for sterilization and release and (2) carry a marker that distinguishes them from wild insects. There are many institutions involved in the development of transgenic insect technology both for studies on basic gene regulation and for the creation of transgenic strains for use in a wide range of insect control programmes. It has been realized that the release into the environment of transgenic insects will not be an easy process considering the current public sensitivities in this area. The fact that insects are mobile and that once released cannot be recalled creates much concern. If fertile transgenic insects were to be released in any type of control programme, then the transgene would enter the wild population through mating. This strategy is fraught with, as yet, unknown risks and it is inconceivable that regulatory approval will be given for such a release in the near future. However, when transgenic strains are integrated into a sterile insect release then the concerns about transmission of the transgene to the wild population disappear as the matings between the released and the wild insects are sterile. This scenario is likely to be the first type of transgenic release. Insects that are currently released in SIT programmes experience no significant regulatory problems, but this will not be the case if the insects that are released are transgenic, even if they are sterile. The meeting Status and Risk Assessment of the Use of Transgenic Arthropods in Plant Protection held in FAO Headquarters, Rome, in April 2002 was the first effort to bring together

  16. Status of nuclear data needed for radiation therapy and existing data development activities in Member States. Summary report of a consultants' meeting

    International Nuclear Information System (INIS)

    Kocherov, N.P.

    1997-01-01

    The present report contains the summary of the IAEA Consultants' Meeting on the ''Status of nuclear data needed for radiation therapy and existing data development activities in Member States'' held at the IAEA Headquarters, Vienna, 9-11 December 1996. The present activities on nuclear data for radiotherapy are summarized in Member States, the present status of nuclear data for photon, neutron and proton therapy is reviewed and topics which are not presently covered by other institutions are identified. (author). 4 refs, 2 figs

  17. ITER Conceptual design: Interim report

    International Nuclear Information System (INIS)

    1990-01-01

    This interim report describes the results of the International Thermonuclear Experimental Reactor (ITER) Conceptual Design Activities after the first year of design following the selection of the ITER concept in the autumn of 1988. Using the concept definition as the basis for conceptual design, the Design Phase has been underway since October 1988, and will be completed at the end of 1990, at which time a final report will be issued. This interim report includes an executive summary of ITER activities, a description of the ITER device and facility, an operation and research program summary, and a description of the physics and engineering design bases. Included are preliminary cost estimates and schedule for completion of the project

  18. Burn site groundwater interim measures work plan.

    Energy Technology Data Exchange (ETDEWEB)

    Witt, Jonathan L. (North Wind, Inc., Idaho Falls, ID); Hall, Kevin A. (North Wind, Inc., Idaho Falls, ID)

    2005-05-01

    This Work Plan identifies and outlines interim measures to address nitrate contamination in groundwater at the Burn Site, Sandia National Laboratories/New Mexico. The New Mexico Environment Department has required implementation of interim measures for nitrate-contaminated groundwater at the Burn Site. The purpose of interim measures is to prevent human or environmental exposure to nitrate-contaminated groundwater originating from the Burn Site. This Work Plan details a summary of current information about the Burn Site, interim measures activities for stabilization, and project management responsibilities to accomplish this purpose.

  19. Commentary: Interim leadership of academic departments at U.S. medical schools.

    Science.gov (United States)

    Grigsby, R Kevin; Aber, Robert C; Quillen, David A

    2009-10-01

    Medical schools and teaching hospitals are experiencing more frequent turnover of department chairs. Loss of a department chair creates instability in the department and may have a negative effect on the organization at large. Interim leadership of academic departments is common, and interim chairs are expected to immediately demonstrate skills and leadership abilities. However, little is known about how persons are prepared to assume the interim chair role. Newer competencies for effective leadership include an understanding of the business of medicine, interpersonal and communication skills, the ability to deal with conflict and solve adaptive challenges, and the ability to build and work on teams. Medical schools and teaching hospitals need assistance to meet the unique training and support needs of persons serving as interim leaders. For example, the Association of American Medical Colleges and individual chair societies can develop programs to allow current chairs to reflect on their present positions and plan for the future. Formal leadership training, mentorship opportunities, and conscientious succession planning are good first steps in preparing to meet the needs of academic departments during transitions in leadership. Also, interim leadership experience may be useful as a means for "opening the door" to underrepresented persons, including women, and increasing the diversity of the leadership team.

  20. Hanford low-level tank waste interim performance assessment

    International Nuclear Information System (INIS)

    Mann, F.M.

    1997-01-01

    The Hanford Low-Level Tank Waste Interim Performance Assessment examines the long-term environmental and human health effects associated with the disposal of the low-level fraction of the Hanford single and double-shell tank waste in the Hanford Site 200 East Area. This report was prepared as a good management practice to provide needed information about the relationship between the disposal system design and performance early in the disposal system project cycle. The calculations in this performance assessment show that the disposal of the low-level fraction can meet environmental and health performance objectives

  1. A randomized controlled trial of interim methadone maintenance.

    Science.gov (United States)

    Schwartz, Robert P; Highfield, David A; Jaffe, Jerome H; Brady, Joseph V; Butler, Carol B; Rouse, Charles O; Callaman, Jason M; O'Grady, Kevin E; Battjes, Robert J

    2006-01-01

    Effective alternatives to long waiting lists for entry into methadone hydrochloride maintenance treatment are needed to reduce the complications of continuing heroin dependence and to increase methadone treatment entry. To compare the effectiveness of interim methadone maintenance with that of the usual waiting list condition in facilitating methadone treatment entry and reducing heroin and cocaine use and criminal behavior. Randomized, controlled, clinical trial using 2 conditions, with treatment assignment on a 3:2 basis to interim maintenance-waiting list control. A methadone treatment program in Baltimore. A total of 319 individuals meeting the criteria for current heroin dependence and methadone maintenance treatment. Participants were randomly assigned to either interim methadone maintenance, consisting of an individually determined methadone dose and emergency counseling only for up to 120 days, or referral to community-based methadone treatment programs. Entry into comprehensive methadone maintenance therapy at 4 months from baseline; self-reported days of heroin use, cocaine use, and criminal behavior; and number of urine drug test results positive for heroin and cocaine at the follow-up interview conducted at time of entry into comprehensive methadone treatment (or at 4 months from baseline for participants who did not enter regular treatment). Significantly more participants assigned to the interim methadone maintenance condition entered comprehensive methadone maintenance treatment by the 120th day from baseline (75.9%) than those assigned to the waiting list control condition (20.8%) (Pmethadone maintenance results in a substantial increase in the likelihood of entry into comprehensive treatment, and is an effective means of reducing heroin use and criminal behavior among opioid-dependent individuals awaiting entry into a comprehensive methadone treatment program.

  2. Maternity leave duration and full-time/part-time work status are associated with US mothers’ ability to meet breastfeeding intentions

    Science.gov (United States)

    Mirkovic, Kelsey R.; Perrine, Cria G.; Scanlon, Kelley S.; Grummer-Strawn, Laurence M.

    2015-01-01

    Background Breastfeeding provides numerous health benefits for infants and mothers; however, many infants are not breastfed as long as recommended or desired by mothers. Maternal employment is frequently cited as a barrier to breastfeeding. Objectives To assess whether maternity leave duration and return-status (full-time [FT], part-time [PT]) were associated with not meeting a mother’s intention to breastfeed at least 3 months. Methods We used data from the Infant Feeding Practices Study II, a cohort study. Analyses were limited to women employed prenatally who intended to breastfeed 3 months or longer (n=1172). Multivariable logistic regression was used to assess the relationship between maternity leave duration and return to work-status (<6 weeks/FT, <6 weeks/PT, 6 weeks – 3 months/FT, 6 weeks – 3 months/PT, not working by 3 months) and meeting a mother’s intention to breastfeed at least 3 months. Results Overall, 28.8% of mothers did not meet their intention to breastfeed at least 3 months. Odds of not meeting intention to breastfeed at least 3 months were higher among mothers who returned to work FT before 3 months (<6 weeks/FT: aOR = 2.25, 95% CI: 1.23 – 4.12; 6 weeks – 3 months/FT: aOR = 1.82, 95% CI: 1.30 – 2.56), compared with mothers not working at 3 months. Conclusions Returning to work full-time before 3 months may reduce a mother’s ability to meet her intention to breastfeed at least 3 months. Employer support for flexible work scheduling may help more women achieve their breastfeeding goals. PMID:25034868

  3. Maternity leave duration and full-time/part-time work status are associated with US mothers' ability to meet breastfeeding intentions.

    Science.gov (United States)

    Mirkovic, Kelsey R; Perrine, Cria G; Scanlon, Kelley S; Grummer-Strawn, Laurence M

    2014-11-01

    Breastfeeding provides numerous health benefits for infants and mothers; however, many infants are not breastfed as long as recommended or desired by mothers. Maternal employment is frequently cited as a barrier to breastfeeding. This study aimed to assess whether maternity leave duration and return status (full-time [FT], part-time [PT]) were associated with not meeting a mother's intention to breastfeed at least 3 months. We used data from the Infant Feeding Practices Study II, a cohort study. Analyses were limited to women employed prenatally who intended to breastfeed 3 months or longer (n = 1172). Multivariable logistic regression was used to assess the relationship between maternity leave duration and return-to-work status (< 6 weeks/FT, < 6 weeks/PT, 6 weeks-3 months/FT, 6 weeks-3 months/PT, not working by 3 months) and meeting a mother's intention to breastfeed at least 3 months. Overall, 28.8% of mothers did not meet their intention to breastfeed at least 3 months. Odds of not meeting intention to breastfeed at least 3 months were higher among mothers who returned to work FT before 3 months (< 6 weeks/FT: adjusted odds ratio = 2.25, 95% confidence interval, 1.23-4.12; 6 weeks-3 months/FT: adjusted odds ratio = 1.82, 95% confidence interval, 1.30-2.56), compared with mothers not working at 3 months. Returning to work full-time before 3 months may reduce a mother's ability to meet her intention to breastfeed at least 3 months. Employer support for flexible work scheduling may help more women achieve their breastfeeding goals. © International Lactation Consultant Association 2014.

  4. 76 FR 58790 - Notice of Interim Approval

    Science.gov (United States)

    2011-09-22

    ... to the customers. Rate Scenario 3--Original Cumberland Marketing Policy The third rate alternative... an interim basis to the customers. Rate Scenario 3--Original Cumberland Marketing Policy The third... allocated on an interim basis to the customers. Rate Scenario 3--Original Cumberland Marketing Policy The...

  5. Fusion Breeder Program interim report

    International Nuclear Information System (INIS)

    Moir, R.; Lee, J.D.; Neef, W.

    1982-01-01

    This interim report for the FY82 Fusion Breeder Program covers work performed during the scoping phase of the study, December, 1981-February 1982. The goals for the FY82 study are the identification and development of a reference blanket concept using the fission suppression concept and the definition of a development plan to further the fusion breeder application. The context of the study is the tandem mirror reactor, but emphasis is placed upon blanket engineering. A tokamak driver and blanket concept will be selected and studied in more detail during FY83

  6. Solid waste burial grounds interim safety analysis

    International Nuclear Information System (INIS)

    Saito, G.H.

    1994-01-01

    This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment

  7. Solid waste burial grounds interim safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Saito, G.H.

    1994-10-01

    This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment.

  8. Interim report on the scientific investigations in the Animas River watershed, Colorado to facilitate remediation decisions by the U.S. Bureau of Land Management and the U.S. Forest Service, March 29, 2000 meeting, Denver, Colorado

    Science.gov (United States)

    ,

    2000-01-01

    INTRODUCTION The joint U.S. Department of the Interior and U.S. Department of Agriculture Abandoned Mine Lands Initiative (AMLI) was developed as a collaborative effort between the Federal land management agencies (FLMA, that is the U.S. Bureau of Land Management and the U.S. Forest Service) and the U.S. Geological Survey (USGS) in 1996. The stated goal of the AML Initiative was to develop a strategy for gathering and communicating the scientific information needed to develop effective and cost-efficient remediation of abandoned mines within the framework of a watershed. Four primary objectives of the AMLI are to: 1. Provide the scientific information needed (in the short-term) by the FLMAs to make decisions related to the design and implementation of cleanup actions, 2. Develop a multi-disciplined, multi-division approach that integrates geologic, hydrologic, geochemical and ecological information into a knowledge base for sound decision making, 3. Transfer technologies developed within the scientific programs of the USGS to the field and demonstrate their suitability to solve real, practical problems, and 4. Establish working relationships among involved members of land management and regulatory agencies within the framework of a watershed approach to the cleanup of abandoned mines. Long-term process-based research, including development of analytical tools, is recognized as being critical to the long-term success in remediating watersheds impacted by historical mining activities (AML 5-year plan, http://amli.usgs.gov/amli). In a meeting of Federal agencies (U.S. Bureau of Land Management [BLM], U.S. Bureau of Reclamation [BOR], U.S. National Park Service [NPS], U.S. Forest Service [USFS], the U.S. Environmental Protection Agency [EPA], the U.S. Fish and Wildlife Service [F&WS]), and State agencies (Colorado Division of Public Health and Environment, Colorado Division of Mines and Geology), several watersheds were examined within the state whose water quality was

  9. Interim and final storage casks

    International Nuclear Information System (INIS)

    Stumpfrock, L.; Kockelmann, H.

    2012-01-01

    The disposal of radioactive waste is a huge social challenge in Germany and all over the world. As is well known the search for a site for a final repository for high-level waste in Germany is not complete. Therefore, interim storage facilities for radioactive waste were built at plant sites in Germany. The waste is stored in these storage facilities in appropriate storage and transport casks until the transport in a final repository can be carried out. Licensing of the storage and transport casks aimed for use in the public space is done according to the traffic laws and for handling in the storage facility according to nuclear law. Taking into account the activity of the waste to be stored, different containers are in use, so that experience is available from the licensing and operation in interim storage facilities. The large volume of radioactive waste to be disposed of after the shut-down of power generation in nuclear power stations makes it necessary for large quantities of licensed storage and transport casks to be provided soon.

  10. Glass packages in interim storage

    International Nuclear Information System (INIS)

    Jacquet-Francillon, N.

    1994-10-01

    This report summarize the current state of knowledge concerning the behavior of type C waste packages consisting of vitrified high-level solutions produced by reprocessing spent fuel. The composition and the physical and chemical properties of the feed solutions are reviewed, and the vitrification process is described. Sodium alumino-borosilicate glass compositions are generally employed - the glass used at la Hague for LWR fuel solutions, for example, contains 45 % SiO 2 . The major physical, chemical, mechanical and thermal properties of the glass are reviewed. In order to allow their thermal power to diminish, the 3630 glass packages produced (as of January 1993) in the vitrification facilities at Marcoule and La Hague are placed in interim storage for several decades. The actual interim storage period has not been defined, as it is closely related to the concept and organization selected for the final destination of the packages: a geological repository. The glass behavior under irradiation is described. Considerable basic and applied research has been conducted to assess the aqueous leaching behavior of nuclear containment glass. The effects of various repository parameters (temperature, flow rate, nature of the environmental materials) have been investigated. The experimental findings have been used to specify a model describing the kinetics of aqueous corrosion of the glass. More generally all the ''source term'' models developed in France by the CEA or by ANDRA are summarized. (author). 152 refs., 33 figs

  11. Comparisons of Cooperative and Non-Cooperative Students: An Analysis of Student Accounting System Data. Interim Report, June, 1981.

    Science.gov (United States)

    Frazier, Don

    The major purpose of this study was to identify unique effects of cooperative vocational education. This interim report is of results of the analyses of existing data bases. Comparisons of cooperative and non-cooperative vocational programs are made on the following variables: enrollments by age, sex and race, school status, work status,…

  12. 13 CFR 120.890 - Source of interim financing.

    Science.gov (United States)

    2010-01-01

    ... 13 Business Credit and Assistance 1 2010-01-01 2010-01-01 false Source of interim financing. 120... Development Company Loan Program (504) Interim Financing § 120.890 Source of interim financing. A Project may use interim financing for all Project costs except the Borrower's contribution. Any source (including...

  13. Austenitic stainless steels, status of the properties database and design rule development

    Energy Technology Data Exchange (ETDEWEB)

    Tavassoli, A.-A. [Commissariat a l`Energie Atomique, CEA-Saclay, Gif-sur Yvette (France). CEREM; Touboul, F. [DMT, Commissariat a l`Energie Atomique, CEA Saclay, Gif-sur-Yvette (France)

    1996-10-01

    In parallel with the new tasks initiated to substantiate the existing database for the reference structural material (type 316LN-IG) of ITER, interim design criteria are being developed to guide subsequent design stages. The French RCC-MR codes for fast breeder reactors, incorporating rules from other ITER partner codes and those needed to meet specific fusion requirements, are used for this purpose. This paper presents the current status of materials data and design rules for type 316LN-IG steel and describes how the irradiation effects are taken into account. (orig.).

  14. Interim reliability evaluation program (IREP)

    International Nuclear Information System (INIS)

    Carlson, D.D.; Murphy, J.A.

    1981-01-01

    The Interim Reliability Evaluation Program (IREP), sponsored by the Office of Nuclear Regulatory Research of the US Nuclear Regulatory Commission, is currently applying probabilistic risk analysis techniques to two PWR and two BWR type power plants. Emphasis was placed on the systems analysis portion of the risk assessment, as opposed to accident phenomenology or consequence analysis, since the identification of risk significant plant features was of primary interest. Traditional event tree/fault tree modeling was used for the analysis. However, the study involved a more thorough investigation of transient initiators and of support system faults than studies in the past and substantially improved techniques were used to quantify accident sequence frequencies. This study also attempted to quantify the potential for operator recovery actions in the course of each significant accident

  15. DOE UST interim subsurface barrier technologies workshop

    International Nuclear Information System (INIS)

    1992-09-01

    This document contains information which was presented at a workshop regarding interim subsurface barrier technologies that could be used for underground storage tanks, particularly the tank 241-C-106 at the Hanford Reservation

  16. Clinical Neuropathology practice news 1-2014: Pyrosequencing meets clinical and analytical performance criteria for routine testing of MGMT promoter methylation status in glioblastoma

    Science.gov (United States)

    Preusser, Matthias; Berghoff, Anna S.; Manzl, Claudia; Filipits, Martin; Weinhäusel, Andreas; Pulverer, Walter; Dieckmann, Karin; Widhalm, Georg; Wöhrer, Adelheid; Knosp, Engelbert; Marosi, Christine; Hainfellner, Johannes A.

    2014-01-01

    Testing of the MGMT promoter methylation status in glioblastoma is relevant for clinical decision making and research applications. Two recent and independent phase III therapy trials confirmed a prognostic and predictive value of the MGMT promoter methylation status in elderly glioblastoma patients. Several methods for MGMT promoter methylation testing have been proposed, but seem to be of limited test reliability. Therefore, and also due to feasibility reasons, translation of MGMT methylation testing into routine use has been protracted so far. Pyrosequencing after prior DNA bisulfite modification has emerged as a reliable, accurate, fast and easy-to-use method for MGMT promoter methylation testing in tumor tissues (including formalin-fixed and paraffin-embedded samples). We performed an intra- and inter-laboratory ring trial which demonstrates a high analytical performance of this technique. Thus, pyrosequencing-based assessment of MGMT promoter methylation status in glioblastoma meets the criteria of high analytical test performance and can be recommended for clinical application, provided that strict quality control is performed. Our article summarizes clinical indications, practical instructions and open issues for MGMT promoter methylation testing in glioblastoma using pyrosequencing. PMID:24359605

  17. Current status of food irradiation in overseas (2013). From the meeting report of RCA food irradiation project

    International Nuclear Information System (INIS)

    Todoriki, Setsuko

    2013-01-01

    The report introduces the activity of RCA (Regional Cooperative Agreement for Research Development and Training Related to Nuclear Science and Technology for Asia and Pacific) food irradiation project (RAS/5/057) and information obtained at the two workshops on current status of Asia and Pacific areas together with EU, USA and Japan. Also current trends of RAS/5/057 Implementing Best Practices for food irradiation for plant sanitary and phytosanitary purposes are described. Amount of food irradiation products of RCA member countries, minimum adopted doses for quarantine harmful insects (70 to 232 Gy) and import amount of fruits of USA (79 to 5500 tons) are tabulated. Finally current status of Japan is explained. (S. Ohno)

  18. Subsurface Interim Measures/Interim Remedial Action Plan and Decision Document for the 903 Pad, Mound, and East Trenches Areas (Operable Unit No. 2)

    International Nuclear Information System (INIS)

    1992-01-01

    The Department of Energy (DOE) is pursuing an Interim Measure/Interim Remedial Action (IM/IRA) at the 903 Pad, Mound, and East Trenches Areas (Operable Unit No. 2) at the Rocky Flats Plant (RFP). This MIRA is to be conducted to provide information that will aid in the selection and design of final remedial actions at OU2 that will address removal of suspected free-phase volatile organic compound (VOC) contamination. The Plan involves investigating the removal of residual free-phase VOCs by in situ vacuum-enhanced vapor extraction technology at 3 suspected VOC source areas within OU2. VOC-contaminated vapors extracted from the subsurface would be treated by granular activated carbon (GAC) adsorption and discharged. The Plan also includes water table depression, when applicable at the test sites, to investigate the performance of vapor extraction technology in the saturated zone. The Plan provides for treatment of any contaminated ground water recovered during the IM/IRA at existing RFP treatment facilities. The proposed MVIRA Plan is presented in the document entitled ''Proposed Subsurface Interim Measures/Interim Remedial Action Plan/Environmental Assessment and Decision Document, 903 Pad, Mound, and East Trenches Areas, Operable Unit No. 2, '' dated 20 March 1992. Information concerning the proposed Subsurface IM/IRA was presented during a DOE Quarterly Review meeting held on 07 April 1992 and a public meeting held on 07 May 1992, at the Marriott Hotel in Golden, Colorado. The Responsiveness Summary presents DOE's response to all comments received at the public meeting, as well as those mailed to date to DOE during the public comment period

  19. High Temperature Materials Interim Data Qualification Report

    International Nuclear Information System (INIS)

    Lybeck, Nancy

    2010-01-01

    Projects for the very high temperature reactor (VHTR) Technology Development Office provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are qualified for use, stored in a readily accessible electronic form, and analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the High Temperature Materials characterization data stream, the processing of these data within NDMAS, and reports the interim FY2010 qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. The High Temperature Materials data are being collected under NQA-1 guidelines, and will be qualified data. For NQA-1 qualified data, the qualification activities include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing to confirm that the data are an accurate representation of the system or object being measured, and (3) documenting that the data were collected under an NQA-1 or equivalent Quality Assurance program. Currently, data from two test series within the High Temperature Materials data stream have been entered into the NDMAS vault: (1) Tensile Tests for Sm (i.e., Allowable Stress) Confirmatory Testing - 1,403,994 records have been inserted into the NDMAS database. Capture testing is in process. (2) Creep-Fatigue Testing to Support Determination of Creep-Fatigue Interaction Diagram - 918,854 records have been processed and inserted into the NDMAS database. Capture testing is in process.

  20. Methods Data Qualification Interim Report

    International Nuclear Information System (INIS)

    Alessi, R. Sam; Grimmett, Tami; Vang, Leng; McGrath, Dave

    2010-01-01

    The overall goal of the Next Generation Nuclear Plant (NGNP) Data Management and Analysis System (NDMAS) is to maintain data provenance for all NGNP data including the Methods component of NGNP data. Multiple means are available to access data stored in NDMAS. A web portal environment allows users to access data, view the results of qualification tests and view graphs and charts of various attributes of the data. NDMAS also has methods for the management of the data output from VHTR simulation models and data generated from experiments designed to verify and validate the simulation codes. These simulation models represent the outcome of mathematical representation of VHTR components and systems. The methods data management approaches described herein will handle data that arise from experiment, simulation, and external sources for the main purpose of facilitating parameter estimation and model verification and validation (V and V). A model integration environment entitled ModelCenter is used to automate the storing of data from simulation model runs to the NDMAS repository. This approach does not adversely change the why computational scientists conduct their work. The method is to be used mainly to store the results of model runs that need to be preserved for auditing purposes or for display to the NDMAS web portal. This interim report demonstrates the currently development of NDMAS for Methods data and discusses data and its qualification that is currently part of NDMAS.

  1. Interim Hanford Waste Management Plan

    International Nuclear Information System (INIS)

    1985-09-01

    The September 1985 Interim Hanford Waste Management Plan (HWMP) is the third revision of this document. In the future, the HWMP will be updated on an annual basis or as major changes in disposal planning at Hanford Site require. The most significant changes in the program since the last release of this document in December 1984 include: (1) Based on studies done in support of the Hanford Defense Waste Environmental Impact Statement (HDW-EIS), the size of the protective barriers covering contaminated soil sites, solid waste burial sites, and single-shell tanks has been increased to provide a barrier that extends 30 m beyond the waste zone. (2) As a result of extensive laboratory development and plant testing, removal of transuranic (TRU) elements from PUREX cladding removal waste (CRW) has been initiated in PUREX. (3) The level of capital support in years beyond those for which specific budget projections have been prepared (i.e., fiscal year 1992 and later) has been increased to maintain Hanford Site capability to support potential future missions, such as the extension of N Reactor/PUREX operations. The costs for disposal of Hanford Site defense wastes are identified in four major areas in the HWMP: waste storage and surveillance, technology development, disposal operations, and capital expenditures

  2. Methods Data Qualification Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    R. Sam Alessi; Tami Grimmett; Leng Vang; Dave McGrath

    2010-09-01

    The overall goal of the Next Generation Nuclear Plant (NGNP) Data Management and Analysis System (NDMAS) is to maintain data provenance for all NGNP data including the Methods component of NGNP data. Multiple means are available to access data stored in NDMAS. A web portal environment allows users to access data, view the results of qualification tests and view graphs and charts of various attributes of the data. NDMAS also has methods for the management of the data output from VHTR simulation models and data generated from experiments designed to verify and validate the simulation codes. These simulation models represent the outcome of mathematical representation of VHTR components and systems. The methods data management approaches described herein will handle data that arise from experiment, simulation, and external sources for the main purpose of facilitating parameter estimation and model verification and validation (V&V). A model integration environment entitled ModelCenter is used to automate the storing of data from simulation model runs to the NDMAS repository. This approach does not adversely change the why computational scientists conduct their work. The method is to be used mainly to store the results of model runs that need to be preserved for auditing purposes or for display to the NDMAS web portal. This interim report demonstrates the currently development of NDMAS for Methods data and discusses data and its qualification that is currently part of NDMAS.

  3. Present Status of the JENDL Project (May, 2013). WPEC Meeting, Paris, France, 23-24 May, 2013

    International Nuclear Information System (INIS)

    Fukahori, Tokio; Iwamoto, Osamu; Ishikawa, Makoto

    2013-01-01

    This paper briefly presents the present status of the Japanese JENDL Project: organization of Japanese Nuclear Data Committee (JNDC), a research committee for JAEA research activities; Nuclear Data Evaluation (JENDL-4.0 Updated Files and JENDL-4.0 Plus, benchmarking for fission reactor applications (criticality for thermal systems, adjusted library for fast systems), new evaluations, covariances, evaluation tools, fission products decay data file); other activities such as the 2012 Symposium on Nuclear Data at Kyoto University Research Reactor Institute, the initiation of conversation on Covariance Data with users, the celebration of the Golden Jubilee (since 1963) of JNDC

  4. ISOE EG-SAM interim report - Report on behalf of the Sub expert Group

    International Nuclear Information System (INIS)

    Harris, Willie; Miller, David W.; Djeffal, Salah; Anderson, Ellen; Couasnon, Olivier; Hagemeyer, Derek; Sovijarvi, Jukka; Amaral, Marcos A.; Tarzia, J.P.; Schmidt, Claudia; Fritioff, Karin; Kaulard, Joerg; Lance, Benoit; Fritioff, Karin; Schieber, Caroline; Hayashida, Yoshihisa; Doty, Rick

    2014-01-01

    During its November 2012 meeting, the expert group decided to develop an interim (preliminary) report before the end of 2013 (with a general perspective and discussion of specific severe accident management worker dose issues), and to finalize the report by organizing the international workshop of 2014 to address national experiences, which will be incorporated to the report. The work of the EG-SAM focuses on radiation protection management and organization, radiation protection training and exercises related to severe accident management, facility configuration and readiness, worker protection, radioactive materials, contamination controls and logistics and key lessons learned especially from the TMI, Chernobyl and Fukushima Dai-ichi accidents. This interim report was completed through intensive work of all Group members nominated by the ISOE, and was accomplished during EG-SAM meetings through 2012-2013. This document gathers the different presentations given by the sub expert groups in charge of each chapter of the report

  5. A study of the usage of LPAs by the North Carolina Division of Motor Vehicles : interim report - phase I.

    Science.gov (United States)

    2014-02-27

    This interim report was prepared to assist NCDMV in meeting the requirements of S.B. 402, Sec. 34.17, which mandates that NCDOT in collaboration with NCDMV shall evaluate current contractual models and compensation for license plate agency (LPA...

  6. Seismic Safety Margins Research Program. Phase I. Interim definition of terms

    International Nuclear Information System (INIS)

    Smith, P.D.; Dong, R.G.

    1980-01-01

    This report documents interim definitions of terms in the Seismic Safety Margins Research Program (SSMRP). Intent is to establish a common-based terminology integral to the probabilistic methods that predict more realistically the behavior of nuclear power plants during an earthquake. These definitions are a response to a request by the Nuclear Regulatory Commission Advisory Committee on Reactor Safeguards at its meeting held November 15-16, 1979

  7. EMCS Retrofit Analysis - Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    Diamond, R.C.; Salsbury, T.I.; Bell, G.C.; Huang, Y.J.; Sezgen, A.O.; Mazzucchi, R.; Romberger, J.

    1999-03-01

    This report presents the interim results of analyses carried out in the Phillip Burton Federal Building in San Francisco from 1996 to 1998. The building is the site of a major demonstration of the BACnet communication protocol. The energy management and control systems (EMCS) in the building were retrofitted with BACnet compatible controllers in order to integrate certain existing systems on one common network. In this respect, the project has been a success. Interoperability of control equipment from different manufacturers has been demonstrated in a real world environment. Besides demonstrating interoperability, the retrofits carried out in the building were also intended to enhance control strategies and capabilities, and to produce energy savings. This report presents analyses of the energy usage of HVAC systems in the building, control performance, and the reaction of the building operators. The report does not present an evaluation of the performance capabilities of the BACnet protocol. A monitoring system was installed in the building that parallels many of the EMCS sensors and data were archived over a three-year period. The authors defined pre-retrofit and post-retrofit periods and analyzed the corresponding data to establish the changes in building performance resulting from the retrofit activities. The authors also used whole-building energy simulation (DOE-2) as a tool for evaluating the effect of the retrofit changes. The results of the simulation were compared with the monitored data. Changes in operator behavior were assessed qualitatively with questionnaires. The report summarizes the findings of the analyses and makes several recommendations as to how to achieve better performance. They maintain that the full potential of the EMCS and associated systems is not being realized. The reasons for this are discussed along with possible ways of addressing this problem. They also describe a number of new technologies that could benefit systems of the type

  8. Advanced nuclear reactor public opinion project. Interim report

    Energy Technology Data Exchange (ETDEWEB)

    Benson, B.

    1991-07-25

    This Interim Report summarizes the findings of our first twenty in-depth interviews in the Advanced Nuclear Reactor Public Opinion Project. We interviewed 6 industry trade association officials, 3 industry attorneys, 6 environmentalists/nuclear critics, 3 state officials, and 3 independent analysts. In addition, we have had numerous shorter discussions with various individuals concerned about nuclear power. The report is organized into the four categories proposed at our April, 1991, Advisory Group meeting: safety, cost-benefit analysis, science education, and communications. Within each category, some change of focus from that of the Advisory Group has been required, to reflect the findings of our interviews. This report limits itself to describing our findings. An accompanying memo draws some tentative conclusions.

  9. Integrated system of safety features for spent fuel interim storage

    International Nuclear Information System (INIS)

    Pantazi, Doina; Stanciu, Marcela; Mateescu, Silvia; Marin, Ion

    1999-01-01

    The design of the spent fuel interim storage facility (SFISF) must meet the applicable safety requirements in order to ensure radiological protection of the personnel, public and environment during all phases of the facility. To elaborate the safety documentation necessary for licensing, we were trying to chose the most appropriate approach related to safety features for SFISF, based on national and international regulations, standards and recommendations, as well as on the experience of other countries with similar facilities and finally, on our own experience in designing other nuclear objectives in Romania. The paper presents the issues that we consider important for the safety evaluation and are developed as a detailed diagram. The diagram contains in a logical succession the following issues: - fundamental principles of radioprotection; - fundamental safety principles of radioactive waste management; - safety objectives of SFISF; - safety criteria for SFISF; - safety requirements for SFISF; - siting criteria for SFISF; - siting requirements for SFISF. (authors)

  10. Modernization and refurbishment of the Central Interim Storage

    International Nuclear Information System (INIS)

    Mele, I.; Zeleznik, N.

    2002-01-01

    The Central Interim Storage for radioactive waste in Brinje, being put into operation in 1986, needs refurbishment and modernization in order to meet the up-to-date operational and safety requirements and to ensure the normal and undisturbed acceptance of radioactive waste from small producers in the future. Because of the waste, being already stored in the storage, the lack of reprocessing capacities and the lack of auxiliary room, the refurbishment and modernization is a complex problem, which needs to be addressed with care. The plan of refurbishment and modernization requires an integral approach, covering all different aspects of renewal and reconstruction. The implementation plan, however, must be based on the actual state of the storage and real conditions for the implementations: from technical to financial. In this paper the project for refurbishment and modernization of the storage, and some activities that have already been implemented, are presented.(author)

  11. Interim storage is not long-term disposal

    International Nuclear Information System (INIS)

    Vincenti, J.R.

    1994-01-01

    Starting in June 30, 1994 South Carolina enforced an embargo on regular shipments of low-level radioactive waste to the Barnwell repository. The failure of 31 states and their respective compacts to provide access to a long-term disposal facility as stipulated by the low-level radioactive Waste Policy Act of 1980 promotes waste disposal gridlock and anticipates another waste disposal crisis. This article discusses the problem using the following topics: Appalachian Compact Users of Radioactive Isotopes (ACURI) Association's interest; the problem of denial of access to Barnwell; pro and contra interim storage; vital services and benefits at risk; issues at the ACURI meeting; nobel Prize winners use radioactive materials; if perception is reality, politics is prevalent

  12. Developing new transportable storage casks for interim dry storage

    International Nuclear Information System (INIS)

    Hayashi, K.; Iwasa, K.; Araki, K.; Asano, R.

    2004-01-01

    Transportable storage metal casks are to be consistently used during transport and storage for AFR interim dry storage facilities planning in Japan. The casks are required to comply with the technical standards of regulations for both transport (hereinafter called ''transport regulation'') and storage (hereafter called ''storage regulation'') to maintain safety functions (heat transfer, containment, shielding and sub-critical control). In addition to these requirements, it is not planned in normal state to change the seal materials during storage at the storage facility, therefore it is requested to use same seal materials when the casks are transported after storage period. The dry transportable storage metal casks that satisfy the requirements have been developed to meet the needs of the dry storage facilities. The basic policy of this development is to utilize proven technology achieved from our design and fabrication experience, to carry out necessary verification for new designs and to realize a safe and rational design with higher capacity and efficient fabrication

  13. Surface Water Interim Measures/Interim Remedial Action Plan/Environmental Assessment and Decision Document for South Walnut Creek Basin (Operable Unit No. 2)

    International Nuclear Information System (INIS)

    1991-01-01

    The Department of Energy (DOE) is pursuing an Interim Measure/Interim Remedial Action (IM/IRA) at the 903 Pad, Mound, and East Trenches Areas (Operable Unit No. 2) at the Rocky Flats Plant (RFP). This IM/IRA is to be conducted to minimize the release from these areas of hazardous substances that pose a potential threat to the public health and environment. The Plan involved the collection of contaminated surface water at specific locations, treatment by chemical precipitation, cross-flow membrane filtration and granular activated carbon (GAC) adsorption, and surface discharge of treated water. Information for the initial configuration of the Plan is presented in the document entitled ''Proposed Interim Measures/Interim Remedial Action Plan and Decision Document, 903 Pad, Mound, and East Trenches Areas, Operable Unit No. 2'' (IM/IRAP) dated 26 September 1990. Information concerning the proposed Surface Water IM/IRA was presented during a public meeting held from 7 to 10 p.m., Tuesday, 23 October 1990, at the Westminster City Park Recreation Center in Westminster, Colorado. This Responsiveness Summary presents DOE's response to all comments received at the public meeting, as well as those mailed to DOE during the public comment period which ended 24 November 1990. There were a number of technical comments on the plan that DOE has addressed herein. It is noted that several major issues were raised by the comments. Regardless of the estimated low risk to the public from construction and water transport activities, the popular sentiment of the public, based on comments received, is strong concern over worker and public health risks from these activities. In the light of public and municipal concerns, DOE proposes to eliminate from this IM/IRA the interbasin transfer of Woman Creek seepage to the South Walnut Creek drainage and to address collection and treatment of contaminated South Walnut Creek and Woman Creek surface water under two separate IM/IRAs

  14. Design review report FFTF interim storage cask

    International Nuclear Information System (INIS)

    Scott, P.L.

    1995-01-01

    Final Design Review Report for the FFTF Interim Storage Cask. The Interim Storage Cask (ISC) will be used for long term above ground dry storage of FFTF irradiated fuel in Core Component Containers (CCC)s. The CCC has been designed and will house assemblies that have been sodium washed in the IEM Cell. The Solid Waste Cask (SWC) will transfer a full CCC from the IEM Cell to the RSB Cask Loading Station where the ISC will be located to receive it. Once the loaded ISC has been sealed at the RSB Cask Loading Station, it will be transferred by facility crane to the DSWC Transporter. After the ISC has been transferred to the Interim Storage Area (ISA), which is yet to be designed, a mobile crane will be used to place the ISC in its final storage location

  15. CMM Interim Check Design of Experiments (U)

    Energy Technology Data Exchange (ETDEWEB)

    Montano, Joshua Daniel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-07-29

    Coordinate Measuring Machines (CMM) are widely used in industry, throughout the Nuclear Weapons Complex and at Los Alamos National Laboratory (LANL) to verify part conformance to design definition. Calibration cycles for CMMs at LANL are predominantly one year in length and include a weekly interim check to reduce risk. The CMM interim check makes use of Renishaw’s Machine Checking Gauge which is an off-the-shelf product simulates a large sphere within a CMM’s measurement volume and allows for error estimation. As verification on the interim check process a design of experiments investigation was proposed to test a couple of key factors (location and inspector). The results from the two-factor factorial experiment proved that location influenced results more than the inspector or interaction.

  16. Choosing a spent fuel interim storage system

    International Nuclear Information System (INIS)

    Roland, V.; Hunter, I.

    2001-01-01

    The Transnucleaire Group has developed different modular solutions to address spent fuel interim storage needs of NPP. These solutions, that are present in Europe, USA and Asia are metal casks (dual purpose or storage only) of the TN 24 family and the NUHOMS canister based system. It is not always simple for an operator to sort out relevant choice criteria. After explaining the basic designs involved on the examples of the TN 120 WWER dual purpose cask and the NUHOMS 56 WWER for WWER 440 spent fuel, we shall discuss the criteria that govern the choice of a given spent fuel interim storage system from the stand point of the operator. In conclusion, choosing and implementing an interim storage system is a complex process, whose implications can be far reaching for the long-term success of a spent fuel management policy. (author)

  17. Interim FDG-PET Scan in Hodgkin's Lymphoma: Hopes and Caveats

    Directory of Open Access Journals (Sweden)

    M. André

    2011-01-01

    Full Text Available FDG-PET has recently emerged as an important tool for the management of Hodgkins lymphoma. Although its use for initial staging and response evaluation at the end of treatment is well established, the place of interim PET for response assessment and subsequent treatment tailoring is still quite controversial. The use of interim PET after a few cycles of chemotherapy may allow treatment reduction for good responders, leading to lesser treatment toxicities as well as early treatment adaptation for bad responders with a potential higher chance for cure. Interpretation of interim PET is a rapidly moving field. Actually, visual interpretation is preferred over quantitative interpretation in this situation. The notion of minimal residual uptake emerged for faint persisting FDG uptake, but has evolved during the recent years. Guidelines using mediastinum and liver as references have been proposed at the expert meeting in Deauville 2009. Actually, several trials are ongoing both for localised and advanced disease to evaluate the FDG-PET potential for early treatment monitoring and tailoring. Until the results of these prospective randomized trials become available, treatment changes according to the interim PET results should remain inappropriate and limited to well-conducted clinical trials.

  18. Used Fuel Logistics: Decades of Experience with transportation and Interim storage solutions

    Energy Technology Data Exchange (ETDEWEB)

    Orban, G.; Shelton, C.

    2015-07-01

    Used fuel inventories are growing worldwide. While some countries have opted for a closed cycle with recycling, numerous countries must expand their interim storage solutions as implementation of permanent repositories is taking more time than foreseen. In both cases transportation capabilities will have to be developed. AREVA TN has an unparalleled expertise with transportation of used fuel. For more than 50 years AREVA TN has safely shipped more than 7,000 used fuel transport casks. The transportation model that was initially developed in the 1970s has been adapted and enhanced over the years to meet more restrictive regulatory requirements and evolving customer needs, and to address public concerns. The numerous “lessons learned” have offered data and guidance that have allowed for also efficient and consistent improvement over the decades. AREVA TN has also an extensive experience with interim dry storage solutions in many countries on-site but also is working with partners to developed consolidated interim storage facility. Both expertise with storage and transportation contribute to safe, secure and smooth continuity of the operations. This paper will describe decades of experience with a very successful transportation program as well as interim storage solutions. (Author)

  19. Interim Administrators in Higher Education: A National Study

    Science.gov (United States)

    Huff, Marie Thielke; Neubrander, Judy

    2015-01-01

    The focus of this paper is on the roles and experiences of interim administrators in higher education. A survey was given to current and recent interim administrators in four-year public universities and colleges across the United States. The goals were to identify the advantages and disadvantages of using and serving as interims, and to solicit…

  20. An Approach for Evaluating the Technical Quality of Interim Assessments

    Science.gov (United States)

    Li, Ying; Marion, Scott; Perie, Marianne; Gong, Brian

    2010-01-01

    Increasing numbers of schools and districts have expressed interest in interim assessment systems to prepare for summative assessments and to improve teaching and learning. However, with so many commercial interim assessments available, schools and districts are struggling to determine which interim assessment is most appropriate to their needs.…

  1. Lessons for outsourcing and interim management relationships.

    Science.gov (United States)

    Macko, W; Kostyack, P T

    1999-01-01

    Few decisions can affect an organization more than the selection of an outsourcing or interim management partner. More and more health care organizations face such decisions in today's competitive market in order to face new business needs. Making these relationships successful can be important for health care organizations seeking competitive advantages or seeking immediately accessible management support. These relationships, however, require careful partner selection and development. Success in outsourcing and interim management relationships is contingent upon a thorough selection process, a strong contract that has clearly and explicitly detailed responsibilities and a culture-sensitive business rapport between the client and selected partner.

  2. 216-T-4 interim stabilization final report

    International Nuclear Information System (INIS)

    Smith, D.L.

    1996-01-01

    This report provides a general description of the activities performed for the interim stabilization of the 216-T-4-1 ditch, 216-T-4-2 ditch, and 216-T-4-2 pond. Interim stabilization was required to reduce the amount of surface-contaminated acres and to minimize the migration of radioactive contamination. Work associated with the 216-T4-1 ditch and 216-T-4-2 pond was performed by the Radiation Area Remedial Action (RARA) Project. Work associated with the 216-T-4-2 ditch was done concurrently but was funded by Westinghouse Hanford Company (WHC) Tank Waste Remediation Systems (TWRS)

  3. Low-level waste forum meeting reports

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-12-31

    This paper provides highlights from the October 1990 meeting of the Low Level Radioactive Waste Forum. Topics of discussion included: a special session on liability and financial assurance needs; proposal to dispose of mixed waste at federal facilities; state plans for interim storage; and hazardous materials legislation.

  4. Effectiveness of interim remedial actions at a radioactive waste facility

    International Nuclear Information System (INIS)

    Devgun, J.S.; Beskid, N.J.; Peterson, J.M.; Seay, W.M.; McNamee, E.

    1989-01-01

    Over the past eight years, several interim remedial actions have been taken at the Niagara Falls Storage Site (NFSS), primarily to reduce radon and gamma radiation exposures and to consolidate radioactive waste into a waste containment facility. Interim remedial actions have included capping of vents, sealing of pipes, relocation of the perimeter fence (to limit radon risk), transfer and consolidation of waste, upgrading of storage buildings, construction of a clay cutoff wall (to limit the potential groundwater transport of contaminants), treatment and release of contaminated water, interim use of a synthetic liner, and emplacement of an interim clay cap. An interim waste containment facility was completed in 1986. 6 refs., 3 figs

  5. 2006 Annual Operations Report for INTEC Operable Unit 3-13, Group 1, Tank Farm Interim Action

    International Nuclear Information System (INIS)

    D. E. Shanklin

    2007-01-01

    This annual operations report describes the requirements followed and activities conducted to inspect, monitor, and maintain the items installed during performance of the Waste Area Group 3, Operable Unit 3-13, Group 1, Tank Farm Interim Action, at the Idaho Nuclear Technology and Engineering Center. This report covers the time period from January 1 through December 31, 2006, and describes inspection and monitoring activities for the surface-sealed areas within the tank farm, concrete-lined ditches and culverts in and around the tank farm, the lift station, and the lined evaporation pond. These activities are intended to assure that the interim action is functioning adequately to meet the objectives stated in the Operable Unit 3-13, Record of Decision for the Group 1, Tank Farm Interim Action (DOE/ID-10660) as described in the Group 1 Remedial Design/Remedial Action Work Plan (DOE/ID-10772)

  6. 2005 Annual Operations Report for INTEC Operable Unit 3-13, Group 1, Tank Farm Interim Action

    International Nuclear Information System (INIS)

    D. Shanklin

    2006-01-01

    This annual operations report describes the requirements followed and activities conducted to inspect, monitor, and maintain the items installed during performance of the Waste Area Group 3, Operable Unit 3-13, Group 1, Tank Farm Interim Action, at the Idaho Nuclear Technology and Engineering Center. This report describes inspection and monitoring activities for the surface-sealed areas within the tank farm, concrete-lined ditches and culverts in and around the tank farm, the lift station, and the lined evaporation pond. These activities are intended to assure that the interim action is functioning adequately to meet the objectives stated in the Operable Unit 3-13, Record of Decision for the Group 1, Tank Farm Interim Action, (DOE/ID-10660) and as amended by the agreement to resolve dispute, which was effective in February 2003

  7. Interim storage of radioactive waste packages

    International Nuclear Information System (INIS)

    1998-01-01

    This report covers all the principal aspects of production and interim storage of radioactive waste packages. The latest design solutions of waste storage facilities and the operational experiences of developed countries are described and evaluated in order to assist developing Member States in decision making and design and construction of their own storage facilities. This report is applicable to any category of radioactive waste package prepared for interim storage, including conditioned spent fuel, high level waste and sealed radiation sources. This report addresses the following issues: safety principles and requirements for storage of waste packages; treatment and conditioning methods for the main categories of radioactive waste; examples of existing interim storage facilities for LILW, spent fuel and high level waste; operational experience of Member States in waste storage operations including control of storage conditions, surveillance of waste packages and observation of the behaviour of waste packages during storage; retrieval of waste packages from storage facilities; technical and administrative measures that will ensure optimal performance of waste packages subject to various periods of interim storage

  8. Disposal facility data for the interim performance

    International Nuclear Information System (INIS)

    Eiholzer, C.R.

    1995-01-01

    The purpose of this report is to identify and provide information on the waste package and disposal facility concepts to be used for the low-level waste tank interim performance assessment. Current concepts for the low-level waste form, canister, and the disposal facility will be used for the interim performance assessment. The concept for the waste form consists of vitrified glass cullet in a sulfur polymer cement matrix material. The waste form will be contained in a 2 x 2 x 8 meter carbon steel container. Two disposal facility concepts will be used for the interim performance assessment. These facility concepts are based on a preliminary disposal facility concept developed for estimating costs for a disposal options configuration study. These disposal concepts are based on vault type structures. None of the concepts given in this report have been approved by a Tank Waste Remediation Systems (TWRS) decision board. These concepts will only be used in th interim performance assessment. Future performance assessments will be based on approved designs

  9. Interim Storage Facility decommissioning. Final report

    International Nuclear Information System (INIS)

    Johnson, R.P.; Speed, D.L.

    1985-01-01

    Decontamination and decommissioning of the Interim Storage Facility were completed. Activities included performing a detailed radiation survey of the facility, removing surface and imbedded contamination, excavating and removing the fuel storage cells, restoring the site to natural conditions, and shipping waste to Hanford, Washington, for burial. The project was accomplished on schedule and 30% under budget with no measurable exposure to decommissioning personnel

  10. 19 CFR 354.8 - Interim sanctions.

    Science.gov (United States)

    2010-04-01

    ... reconsider imposition of interim sanctions on the basis of new and material evidence or other good cause... Secretary may petition a presiding official to impose such sanctions. (b) The presiding official may impose... person to return material previously provided by the Department and all other materials containing the...

  11. Automotive Mechanics Occupational Performance Survey. Interim Report.

    Science.gov (United States)

    Borcher, Sidney D.; Leiter, Paul B.

    The purpose of this federally-funded interim report is to present the results of a task inventory analysis survey of automotive mechanics completed by project staff within the Instructional Systems Design Program at the Center for Vocational and Technical Education. Intended for use in curriculum development for vocational education programs in…

  12. A Non-Traditional Interim Project.

    Science.gov (United States)

    Brown, Diane; Ward, Dorothy

    1980-01-01

    Describes a project initiated by the Foreign Language Department of Birmingham-Southern College for their Interim term and discusses an interdisciplinary course focusing on Medieval Europe. The course included presentations on German and French language and literature, as well as lectures on the arts, philosophy, and family life of the period.…

  13. 340 waste handling facility interim safety basis

    Energy Technology Data Exchange (ETDEWEB)

    VAIL, T.S.

    1999-04-01

    This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people.

  14. ITER interim design report package documents

    International Nuclear Information System (INIS)

    1996-01-01

    This publication contains the Excerpt from the ITER Council (IC-8), the ITER Interim Design Report, Cost Review and Safety Analysis, ITER Site Requirements and ITER Site Design Assumptions and the Excerpt from the ITER Council (IC-9). 8 figs, 2 tabs

  15. LANDFILL BIOREACTOR PERFORMANCE, SECOND INTERIM REPORT

    Science.gov (United States)

    A bioreactor landfill is a landfill that is operated in a manner that is expected to increase the rate and extent of waste decomposition, gas generation, and settlement compared to a traditional landfill. This Second Interim Report was prepared to provide an interpretation of fie...

  16. 340 waste handling facility interim safety basis

    International Nuclear Information System (INIS)

    VAIL, T.S.

    1999-01-01

    This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people

  17. Transitioning aluminum clad spent fuels from wet to interim dry storage

    International Nuclear Information System (INIS)

    Louthan, M.R. Jr.; Iyer, N.C.; Sindelar, R.L.; Peacock, H.B. Jr.

    1994-01-01

    The United States Department of Energy (DOE) currently owns several hundred metric tons of aluminum clad, spent nuclear fuel and target assemblies. The vast majority of these irradiated assemblies are currently stored in water basins that were designed and operated for short term fuel cooling prior to fuel reprocessing. Recent DOE decisions to severely limit the reprocessing option have significantly lengthened the time of storage, thus increasing the tendency for corrosion induced degradation of the fuel cladding and the underlying core material. The portent of continued corrosion, coupled with the age of existing wet storage facilities and the cost of continuing basin operations, including necessary upgrades to meet current facility standards, may force the DOE to transition these wet stored, aluminum clad spent fuels to interim dry storage. The facilities for interim dry storage have not been developed, partially because fuel storage requirements and specifications for acceptable fuel forms are lacking. In spite of the lack of both facilities and specifications, current plans are to dry store fuels for approximately 40 to 60 years or until firm decisions are developed for final fuel disposition. The transition of the aluminum clad fuels from wet to interim dry storage will require a sequence of drying and canning operations which will include selected fuel preparations such as vacuum drying and conditioning of the storage atmosphere. Laboratory experiments and review of the available literature have demonstrated that successful interim dry storage may also require the use of fuel and canister cleaning or rinsing techniques that preclude, or at least minimize, the potential for the accumulation of chloride and other potentially deleterious ions in the dry storage environment. This paper summarizes an evaluation of the impact of fuel transitioning techniques on the potential for corrosion induced degradation of fuel forms during interim dry storage

  18. 300 area solvent evaporator interim status closure plan: Revision 2

    International Nuclear Information System (INIS)

    1989-02-01

    This document describes activities for the closure of a hazardous waste tank treatment facility operated by the US Department of Energy-Richland Operations Office (DOE-RL) and co-operated by the Westinghouse Hanford Company (WHC). This treatment facility was a solvent evaporator located in the 300 Area of the Hanford Site, from 1975 to 1985 on behalf of DOE-RL. The 300 Area Solvent Evaporator (300 ASE) was a modified load lugger (dumpster) in which solvent wastes were evaporated. Some of the solvents were radioactively contaminated because they came from a degreaser which processed bare uranium metal billets from the N Reactor Fuel Manufacturing Facility. The waste was composed of perchloroethylene, trichloroethylene, 1,1,1-trichloroethane, ethyl acetate/bromine solution, paint shop solvents and possibly some used oil. Also, small amounts of uranium, copper, zirconium and possibly beryllium were present in the degreaser solvents as particulates. Radioactive and non-radioactive solvents were not segregated in the 300 ASE, and the entire mixture was regarded as mixed waste

  19. Interim Status Report for Risk Management for SFRs

    International Nuclear Information System (INIS)

    Jankovsky, Zachary Kyle; Denman, Matthew R.; Groth, Katrina; Wheeler, Timothy A.

    2015-01-01

    Accident management is an important component to maintaining risk at acceptable levels for all complex systems, such as nuclear power plants. With the introduction of passive, or inherently safe, reactor designs the focus has shifted from management by operators to allowing the system's design to take advantage of natural phenomena to manage the accident. Inherently and passively safe designs are laudable, but nonetheless extreme boundary conditions can interfere with the design attributes which facilitate inherent safety, thus resulting in unanticipated and undesirable end states. This report examines an inherently safe and small sodium fast reactor experiencing a variety of beyond design basis events with the intent of exploring the utility of a Dynamic Bayesian Network to infer the state of the reactor to inform the operator's corrective actions. These inferences also serve to identify the instruments most critical to informing an operator's actions as candidates for hardening against radiation and other extreme environmental conditions that may exist in an accident. This reduction in uncertainty serves to inform ongoing discussions of how small sodium reactors would be licensed and may serve to reduce regulatory risk and cost for such reactors.

  20. 40 CFR 266.103 - Interim status standards for burners.

    Science.gov (United States)

    2010-07-01

    ...) Minimum scrubber blowdown from the system or maximum suspended solids content of scrubber water; and (C) Minimum pH level of the scrubber water; (x) For systems using venturi scrubbers, the minimum differential...) For systems using wet scrubbers, including wet ionizing scrubbers (unless complying with the Tier I or...

  1. Interim status report of the TMI personnel-dosimetry project

    International Nuclear Information System (INIS)

    Rich, B.L.; Alvarez, J.L.; Adams, S.R.

    1981-06-01

    The current 2-chip TLD personnel dosimeter in use at Three Mile Island (TMI) has been shown inadequate for the anticipated high beta/gamma fields during TMI recovery operations in some areas. This project surveyed the available dosimeter systems, set up an Idaho National Engineering Laboratory (INEL) prototype system, and compared this system with those commercial systems that could be made immediately available for comparison. Of the systems tested, the new INEL personnel dosimeter was found to produce the most accurate results for use in recovery operations at TMI-2. The other multiple-chip or multiple-filter systems were found less desirable at present. The most prominent deficiencies in the INEL dosimeter stem from the fact that it lacks a completely automated reader and its x-ray and thermal neutron responses require additional development. A automated prototype reader system may be in operation by the end of CY-1981. Three alternatives for operational dosimetry are discussed. A combination of a modified version of the presently used Harshaw 2-chip dosimeter and the INEL dosimeter is recommended

  2. Interim Status Report for Risk Management for SFRs

    Energy Technology Data Exchange (ETDEWEB)

    Jankovsky, Zachary Kyle [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Denman, Matthew R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Groth, Katrina [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Wheeler, Timothy A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-10-01

    Accident management is an important component to maintaining risk at acceptable levels for all complex systems, such as nuclear power plants. With the introduction of passive, or inherently safe, reactor designs the focus has shifted from management by operators to allowing the system's design to take advantage of natural phenomena to manage the accident. Inherently and passively safe designs are laudable, but nonetheless extreme boundary conditions can interfere with the design attributes which facilitate inherent safety, thus resulting in unanticipated and undesirable end states. This report examines an inherently safe and small sodium fast reactor experiencing a variety of beyond design basis events with the intent of exploring the utility of a Dynamic Bayesian Network to infer the state of the reactor to inform the operator's corrective actions. These inferences also serve to identify the instruments most critical to informing an operator's actions as candidates for hardening against radiation and other extreme environmental conditions that may exist in an accident. This reduction in uncertainty serves to inform ongoing discussions of how small sodium reactors would be licensed and may serve to reduce regulatory risk and cost for such reactors.

  3. Interim report on the meteorological database

    International Nuclear Information System (INIS)

    Stage, S.A.; Ramsdell, J.V.; Simonen, C.A.; Burk, K.W.

    1993-01-01

    The Hanford Environmental Dose Reconstruction (HEDR) Project is estimating radiation doses that individuals may have received from operations at Hanford from 1944 to the present. An independent Technical Steering Panel (TSP) directs the project, which is being conducted by the Battelle, Pacific Northwest Laboratories in Richland, Washington. The goals of HEDR, as approved by the TSP, include dose estimates and determination of confidence ranges for these estimates. This letter report describes the current status of the meteorological database. The report defines the meteorological data available for use in climate model calculations, describes the data collection procedures and the preparation and control of the meteorological database. This report also provides an initial assessment of the data quality. The available meteorological data are adequate for atmospheric calculations. Initial checks of the data indicate the data entry accuracy meets the data quality objectives

  4. Department of Energy Plutonium ES ampersand H Vulnerability Assessment Savannah River Site interim compensatory measures

    International Nuclear Information System (INIS)

    Bickford, W.E.

    1994-01-01

    The Savannah River Site (SRS) has recently completed a self-assessment of potential vulnerabilities associated with plutonium and other transuranic materials stored at the site. An independent Working Group Assessment Team (WGAT) appointed by DOE/ES ampersand H also performed an independent assessment, and reviewed and validated the site self-assessment. The purpose of this report is to provide a status of interim compensatory measures at SRS to address hazards in advance of any corrective actions. ES ampersand H has requested this status for all vulnerabilities ranked medium or higher with respect to potential consequences to workers, environment, and the public

  5. 75 FR 56608 - Agency Meeting

    Science.gov (United States)

    2010-09-16

    ... SECURITIES AND EXCHANGE COMMISSION Agency Meeting Federal Register Citation of Previous Announcement: [To be published] Status: Open Meeting. Place: 100 F. Street, NE., Washington, DC. Date and Time of Previously Announced Meeting: September 15, 2010. Change In the Meeting: Room Change. The Joint...

  6. 78 FR 73190 - Sunshine Act Meeting

    Science.gov (United States)

    2013-12-05

    ... FEDERAL RESERVE SYSTEM Sunshine Act Meeting Agency Holding the Meeting: Board of Governors of the...., Washington, DC 20551. STATUS: Open. On the day of the meeting, you will be able to view the meeting via... webcast of the meeting. A link to the meeting documentation will also be available approximately 20...

  7. ITER management advisory committee meeting in NAKA

    International Nuclear Information System (INIS)

    Yoshikawa, M.

    1999-01-01

    The ITER Management Advisory Committee (MAC) Meeting was held on 17 December 1999 in Naka, Japan. The main topics were the ITER EDA Status, Task Status Summary and Work Program and a schedule of ITER meetings

  8. Spent fuel interim management: 1995 update

    International Nuclear Information System (INIS)

    Anderson, C.K.

    1995-01-01

    The problems of interim away-from-reactor spent fuel storage and storage in spent fuel pools at the reactor site are discussed. An overview of the state-of-the-art in the USA, Europe, and Japan is presented. The technical facilities for away-from-reactor storage are briefly described, including wet storage pools, interactive concrete systems, metallic containers, and passive concrete systems. Reprocessing technologies are mostly at the design stage only. It is predicted that during the 20 years to come, about 50 000 tonnes of spent fuel will be stored at reactor sites regardless of the advance of spent fuel reprocessing or interim storage projects. (J.B.). 4 tabs., 2 figs

  9. Pathways to deep decarbonization - Interim 2014 Report

    International Nuclear Information System (INIS)

    2014-01-01

    The interim 2014 report by the Deep Decarbonization Pathways Project (DDPP), coordinated and published by IDDRI and the Sustainable Development Solutions Network (SDSN), presents preliminary findings of the pathways developed by the DDPP Country Research Teams with the objective of achieving emission reductions consistent with limiting global warming to less than 2 deg. C. The DDPP is a knowledge network comprising 15 Country Research Teams and several Partner Organizations who develop and share methods, assumptions, and findings related to deep decarbonization. Each DDPP Country Research Team has developed an illustrative road-map for the transition to a low-carbon economy, with the intent of taking into account national socio-economic conditions, development aspirations, infrastructure stocks, resource endowments, and other relevant factors. The interim 2014 report focuses on technically feasible pathways to deep decarbonization

  10. SLIGHTLY IRRADIATED FUEL (SIF) INTERIM DISPOSITION PROJECT

    International Nuclear Information System (INIS)

    Norton, S.H.

    2010-01-01

    CH2M HILL Plateau Remediation Company (CH2M HILL PRC) is proud to submit the Slightly Irradiated Fuel (SIF) Interim Disposition Project for consideration by the Project Management Institute as Project of the Year for 2010. The SIF Project was a set of six interrelated sub-projects that delivered unique stand-alone outcomes, which, when integrated, provided a comprehensive and compliant system for storing high risk special nuclear materials. The scope of the six sub-projects included the design, construction, testing, and turnover of the facilities and equipment, which would provide safe, secure, and compliant Special Nuclear Material (SNM) storage capabilities for the SIF material. The project encompassed a broad range of activities, including the following: Five buildings/structures removed, relocated, or built; Two buildings renovated; Structural barriers, fencing, and heavy gates installed; New roadways and parking lots built; Multiple detection and assessment systems installed; New and expanded communication systems developed; Multimedia recording devices added; and A new control room to monitor all materials and systems built. Project challenges were numerous and included the following: An aggressive 17-month schedule to support the high-profile Plutonium Finishing Plant (PFP) decommissioning; Company/contractor changeovers that affected each and every project team member; Project requirements that continually evolved during design and construction due to the performance- and outcome-based nature ofthe security objectives; and Restrictions imposed on all communications due to the sensitive nature of the projects In spite of the significant challenges, the project was delivered on schedule and $2 million under budget, which became a special source of pride that bonded the team. For years, the SIF had been stored at the central Hanford PFP. Because of the weapons-grade piutonium produced and stored there, the PFP had some of the tightest security on the Hanford

  11. SLIGHTLY IRRADIATED FUEL (SIF) INTERIM DISPOSITION PROJECT

    Energy Technology Data Exchange (ETDEWEB)

    NORTON SH

    2010-02-23

    CH2M HILL Plateau Remediation Company (CH2M HILL PRC) is proud to submit the Slightly Irradiated Fuel (SIF) Interim Disposition Project for consideration by the Project Management Institute as Project of the Year for 2010. The SIF Project was a set of six interrelated sub-projects that delivered unique stand-alone outcomes, which, when integrated, provided a comprehensive and compliant system for storing high risk special nuclear materials. The scope of the six sub-projects included the design, construction, testing, and turnover of the facilities and equipment, which would provide safe, secure, and compliant Special Nuclear Material (SNM) storage capabilities for the SIF material. The project encompassed a broad range of activities, including the following: Five buildings/structures removed, relocated, or built; Two buildings renovated; Structural barriers, fencing, and heavy gates installed; New roadways and parking lots built; Multiple detection and assessment systems installed; New and expanded communication systems developed; Multimedia recording devices added; and A new control room to monitor all materials and systems built. Project challenges were numerous and included the following: An aggressive 17-month schedule to support the high-profile Plutonium Finishing Plant (PFP) decommissioning; Company/contractor changeovers that affected each and every project team member; Project requirements that continually evolved during design and construction due to the performance- and outcome-based nature ofthe security objectives; and Restrictions imposed on all communications due to the sensitive nature of the projects In spite of the significant challenges, the project was delivered on schedule and $2 million under budget, which became a special source of pride that bonded the team. For years, the SIF had been stored at the central Hanford PFP. Because of the weapons-grade piutonium produced and stored there, the PFP had some of the tightest security on the Hanford

  12. Tribal child welfare. Interim final rule.

    Science.gov (United States)

    2012-01-06

    The Administration for Children and Families (ACF) is issuing this interim final rule to implement statutory provisions related to the Tribal title IV-E program. Effective October 1, 2009, section 479B(b) of the Social Security Act (the Act) authorizes direct Federal funding of Indian Tribes, Tribal organizations, and Tribal consortia that choose to operate a foster care, adoption assistance and, at Tribal option, a kinship guardianship assistance program under title IV-E of the Act. The Fostering Connections to Success and Increasing Adoptions Act of 2008 requires that ACF issue interim final regulations which address procedures to ensure that a transfer of responsibility for the placement and care of a child under a State title IV-E plan to a Tribal title IV-E plan occurs in a manner that does not affect the child's eligibility for title IV-E benefits or medical assistance under title XIX of the Act (Medicaid) and such services or payments; in-kind expenditures from third-party sources for the Tribal share of administration and training expenditures under title IV-E; and other provisions to carry out the Tribal-related amendments to title IV-E. This interim final rule includes these provisions and technical amendments necessary to implement a Tribal title IV-E program.

  13. The Interim Financial Statements: The Case of Greece

    OpenAIRE

    Rogdaki, E.I.; Kazantzis, Ch.

    1999-01-01

    The following paper refers to the accounting and auditing issues which emerge in the preparation of the interim financial statements of the companies: Firstly, the interim financial statements are defined as being the financial statements that provide useful information about the financial position and the financial results of a company which are realized and accrued during the fiscal year. The interim financial statements can be prepared on a monthly basis, on a quarterly basis or covering a...

  14. Compilation of interim technical research memoranda. Volume I

    International Nuclear Information System (INIS)

    Shanahan, W.R.

    1984-04-01

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

  15. Staff meeting

    CERN Multimedia

    2007-01-01

    Dear Colleagues, 2007 is a very special year for CERN. I would like to review the status of our activities with you, and I invite you to a presentation on Wednesday 27 June 2007 at 3:00 p.m. Main Auditorium (bldg. 500) Closed-circuit transmission of the meeting will be available in the Council Chamber and in the AB Auditorium (Meyrin), the AB Auditorium (Prévessin), the IT Auditorium (bldg. 31) and the AT Auditorium (bldg. 30). Simultaneous translation into English will be available in the Main Auditorium. Robert AYMAR

  16. Safety of interim storage solutions of used nuclear fuel during extended term

    Energy Technology Data Exchange (ETDEWEB)

    Shelton, C.; Bader, S.; Issard, H.; Arslan, M. [AREVA, 7135 Minstrel Way, Suite 300 Columbia, MD 21045 (United States)

    2013-07-01

    In 2013, the total amount of stored used nuclear fuel (UNF) in the world will reach 225,000 T HM. The UNF inventory in wet storage will take up over 80% of the available total spent fuel pool (SFP) capacity. Interim storage solutions are needed. They give flexibility to the nuclear operators and ensure that nuclear reactors continue to operate. However, we need to keep in mind that they are also an easy way to differ final decision and implementation of a UNF management approach (recycling or final disposal). In term of public perception, they can have a negative impact overtime as it may appear that nuclear industry may have significant issues to resolve. In countries lacking an integrated UNF management approach, the UNF are being discharged from the SFPs to interim storage (mostly to dry storage) at the same rate as UNF is being discharged from reactors, as the SFPs at the reactor sites are becoming full. This is now the case in USA, Taiwan, Switzerland, Spain, South Africa and Germany. For interim storage, AREVA has developed different solutions in order to allow the continued operation of reactors while meeting the current requirements of Safety Authorities: -) Dry storage canisters on pads, -) Dual-purpose casks (dry storage and transportation), -) Vault dry storage, and -) Centralized pool storage.

  17. Reliability Centered Maintenance for Savannah River Site`s interim waste management facilities. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Hauer, K.A. [Westinghouse Savannah River Co., Aiken, SC (United States); Wilson, J.F. [PRC, Inc. (US)

    1992-06-01

    The application of Reliability Centered Maintenance (RCM) has been shown to be an effective means to optimize maintenance programs or to establish new programs. The key to success of any RCM program is to customize the methodology to meet the specific needs of the implementing organization. This paper discusses how RCM is being used to establish the preventive maintenance program and how the resulting system data is being used to support the Technical Baseline reconstitution effort for the interim Waste Management Division of Westinghouse Savannah River Company (WSRC).

  18. Reliability Centered Maintenance for Savannah River Site's interim waste management facilities

    Energy Technology Data Exchange (ETDEWEB)

    Hauer, K.A. (Westinghouse Savannah River Co., Aiken, SC (United States)); Wilson, J.F. (PRC, Inc. (US))

    1992-01-01

    The application of Reliability Centered Maintenance (RCM) has been shown to be an effective means to optimize maintenance programs or to establish new programs. The key to success of any RCM program is to customize the methodology to meet the specific needs of the implementing organization. This paper discusses how RCM is being used to establish the preventive maintenance program and how the resulting system data is being used to support the Technical Baseline reconstitution effort for the interim Waste Management Division of Westinghouse Savannah River Company (WSRC).

  19. Reliability Centered Maintenance for Savannah River Site's interim waste management facilities

    International Nuclear Information System (INIS)

    Hauer, K.A.; Wilson, J.F.

    1992-01-01

    The application of Reliability Centered Maintenance (RCM) has been shown to be an effective means to optimize maintenance programs or to establish new programs. The key to success of any RCM program is to customize the methodology to meet the specific needs of the implementing organization. This paper discusses how RCM is being used to establish the preventive maintenance program and how the resulting system data is being used to support the Technical Baseline reconstitution effort for the interim Waste Management Division of Westinghouse Savannah River Company (WSRC)

  20. Status of national programmes on fast breeder reactors. Twenty-fifth annual meeting of the International Working Group on Fast Reactors. Summary report. Working material

    International Nuclear Information System (INIS)

    1992-01-01

    'burning' of the associated extremely long-life transuranic waste, particularly actinides, thus reducing the required isolation time for high level waste from tens of thousands of years to hundreds of years for fission products only. This additional important mission for the LMFBR is gaining worldwide interest. In the framework of disarmament of nuclear weapons and the utilization of the nuclear material for peaceful purposes a role for fast reactors can be also considered. Over the past 25 years, the IAEA has actively encouraged and advocated international cooperation in Fast Breeder Reactor Technology. At the present time the Working Group on Fast Reactors is the oldest and one of the most active groups in the Division of Nuclear Power. The present document contains information on the status of fast breeder reactor development and on worldwide activities in this advanced nuclear power technology during 1991, as reported at the 25th jubilee Annual Meeting of the IWGFR in Vienna, 27-30 April 1992. The publication is intended to provide information regarding the current status of LMFBR development in IAEA Member States and CEC

  1. Status of national programmes on fast breeder reactors. Twenty-fifth annual meeting of the International Working Group on Fast Reactors. Summary report. Working material

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-07-01

    'burning' of the associated extremely long-life transuranic waste, particularly actinides, thus reducing the required isolation time for high level waste from tens of thousands of years to hundreds of years for fission products only. This additional important mission for the LMFBR is gaining worldwide interest. In the framework of disarmament of nuclear weapons and the utilization of the nuclear material for peaceful purposes a role for fast reactors can be also considered. Over the past 25 years, the IAEA has actively encouraged and advocated international cooperation in Fast Breeder Reactor Technology. At the present time the Working Group on Fast Reactors is the oldest and one of the most active groups in the Division of Nuclear Power. The present document contains information on the status of fast breeder reactor development and on worldwide activities in this advanced nuclear power technology during 1991, as reported at the 25th jubilee Annual Meeting of the IWGFR in Vienna, 27-30 April 1992. The publication is intended to provide information regarding the current status of LMFBR development in IAEA Member States and CEC.

  2. The Homestake Interim Laboratory and Homestake DUSEL

    Science.gov (United States)

    Lesko, Kevin T.

    2011-12-01

    The former Homestake gold mine in Lead South Dakota is proposed for the National Science Foundation's Deep Underground Science and Engineering Laboratory (DUSEL). The gold mine provides expedient access to depths in excess of 8000 feet below the surface (>7000 mwe). Homestake's long history of promoting scientific endeavours includes the Davis Solar Neutrino Experiment, a chlorine-based experiment that was hosted at the 4850 Level for more than 30 years. As DUSEL, Homestake would be uncompromised by competition with mining interests or other shared uses. The facility's 600-km of drifts would be available for conversion for scientific and educational uses. The State of South Dakota, under Governor Rounds' leadership, has demonstrated exceptionally strong support for Homestake and the creation of DUSEL. The State has provided funding totalling $46M for the preservation of the site for DUSEL and for the conversion and operation of the Homestake Interim Laboratory. Motivated by the strong educational and outreach potential of Homestake, the State contracted a Conversion Plan by world-recognized mine-engineering contractor to define the process of rehabilitating the facility, establishing the appropriate safety program, and regaining access to the facility. The State of South Dakota has established the South Dakota Science and Technology Authority to oversee the transfer of the Homestake property to the State and the rehabilitation and preservation of the facility. The Homestake Scientific Collaboration and the State of South Dakota's Science and Technology Authority has called for Letters of Interest from scientific, educational and engineering collaborations and institutions that are interested in hosting experiments and uses in the Homestake Interim Facility in advance of the NSF's DUSEL, to define experiments starting as early as 2007. The Homestake Program Advisory Committee has reviewed these Letters and their initial report has been released. Options for

  3. The Homestake Interim Laboratory and Homestake DUSEL

    International Nuclear Information System (INIS)

    Lesko, Kevin T.

    2011-01-01

    The former Homestake gold mine in Lead South Dakota is proposed for the National Science Foundation's Deep Underground Science and Engineering Laboratory (DUSEL). The gold mine provides expedient access to depths in excess of 8000 feet below the surface (>7000 mwe). Homestake's long history of promoting scientific endeavours includes the Davis Solar Neutrino Experiment, a chlorine-based experiment that was hosted at the 4850 Level for more than 30 years. As DUSEL, Homestake would be uncompromised by competition with mining interests or other shared uses. The facility's 600-km of drifts would be available for conversion for scientific and educational uses. The State of South Dakota, under Governor Rounds' leadership, has demonstrated exceptionally strong support for Homestake and the creation of DUSEL. The State has provided funding totalling $46M for the preservation of the site for DUSEL and for the conversion and operation of the Homestake Interim Laboratory. Motivated by the strong educational and outreach potential of Homestake, the State contracted a Conversion Plan by world-recognized mine-engineering contractor to define the process of rehabilitating the facility, establishing the appropriate safety program, and regaining access to the facility. The State of South Dakota has established the South Dakota Science and Technology Authority to oversee the transfer of the Homestake property to the State and the rehabilitation and preservation of the facility. The Homestake Scientific Collaboration and the State of South Dakota's Science and Technology Authority has called for Letters of Interest from scientific, educational and engineering collaborations and institutions that are interested in hosting experiments and uses in the Homestake Interim Facility in advance of the NSF's DUSEL, to define experiments starting as early as 2007. The Homestake Program Advisory Committee has reviewed these Letters and their initial report has been released. Options for

  4. Status of National Programmes on Fast Breeder Reactors. International Working Group on Fast Reactors, Twentieth Annual Meeting, Vienna, 24-27 March 1987

    International Nuclear Information System (INIS)

    1987-07-01

    The Agenda of the meeting was as follows: 1. Approval of the Agenda. 2. Approval of the minutes of the 19th meeting of the IWGFR. 3. Report of the Scientific Secretary regarding the WD activities of the Working Group. 4. Presentations and discussions on national programmes on fast breeder reactors. 5. Consideration of conferences on fast breeder reactors. a. ANS-ENS International Conference on Fast Breeder Systems Experience Gained and Path to Economical Power Generation, Richland, Washington, USA, 13-17 September 1987. b. International Conference on Liquid Metal Engineering and Technology, Avignon, France, 17-20 October 1988. c. Other meetings of interest to IWGFR members. 6. Consideration of major recommendations of some of the WD IWGFR Specialists' Meetings. 7. Consideration of arrangements for Specialists' Meetings in 1987. a. Specialists' Meeting on Fission and Corrosion Products Behaviour in Primary Circuits of LMFBRs, Karlsruhe, Fed. Rep. of Germany, May 1987. b. Specialists' Meeting on LMFBR Reactor Block Antiseismic Design and Verification, Bologna, Italy, October 1987. 8. Selection of topics for Specialists' Meetings to be held in 1988 and suggestions of the IWGFR on other Specialists' Meetings and their justifications. 9. Consideration of joint research activities: a. Coordinated Research Programme on a Comparative Assessment of Processing Techniques for Analysis of Sodium Boiling Noise Detection Data. b. Coordinated Research Programme on Intercomparison of LMFBR Core Mechanics Codes. c. New Topics of CRP. d. Other Activities. 10. Updating of ''LMFBR Plant Parameters''. 11. Informal discussion on ''Safety Criteria for Fast Reactors in IWGFR Countries''. 12. The date and place of the 21th Annual Meeting of the IWGFR

  5. ACCU MEETING

    CERN Document Server

    Chris Onions

    2007-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 13 June 2007 at 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Dosimetry at CERN Status of collaborative tools at CERN Reports from ACCU representatives on other committees Users' Office newss Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria Czech Republic P. Závada (75877) Denmark J.B. Hansen (75941) Finland K. Lassila-Perini (7935...

  6. ACCU MEETING

    CERN Multimedia

    2007-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 13 June 2007 at 9:15 a.m. in room 60-6-002 1.\tChairman’s remarks 6.\tDosimetry at CERN 2.\tAdoption of the agenda 7.\tStatus of collaborative tools at CERN 3.\tMinutes of the previous meeting 8.\tReports from ACCU representatives on other committees 4.\tMatters arising 9.\tUsers’ Office newss 5.\tNews from the CERN Management 10.\tAny Other Business 11.\tAgenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Norway G. Løvhøiden (73176) Belgium G. Wilquet (74664) Poland M. Witek (78967) Bulgaria Portugal...

  7. 40 CFR 80.141 - Interim detergent gasoline program.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 16 2010-07-01 2010-07-01 false Interim detergent gasoline program. 80... (CONTINUED) REGULATION OF FUELS AND FUEL ADDITIVES Detergent Gasoline § 80.141 Interim detergent gasoline... apply to: (i) All gasoline sold or transferred to a party who sells or transfers gasoline to the...

  8. 50 CFR 660.720 - Interim protection for sea turtles.

    Science.gov (United States)

    2010-10-01

    ... 50 Wildlife and Fisheries 9 2010-10-01 2010-10-01 false Interim protection for sea turtles. 660.720 Section 660.720 Wildlife and Fisheries FISHERY CONSERVATION AND MANAGEMENT, NATIONAL OCEANIC AND... Migratory Fisheries § 660.720 Interim protection for sea turtles. (a) Until the effective date of §§ 660.707...

  9. 12 CFR 541.18 - Interim Federal savings association.

    Science.gov (United States)

    2010-01-01

    ... an existing savings and loan holding company or to facilitate any other transaction the Office may... 12 Banks and Banking 5 2010-01-01 2010-01-01 false Interim Federal savings association. 541.18... REGULATIONS AFFECTING FEDERAL SAVINGS ASSOCIATIONS § 541.18 Interim Federal savings association. The term...

  10. Transuranic waste storage and assay facility (TRUSAF) interim safety basis

    International Nuclear Information System (INIS)

    Gibson, K.D.

    1995-09-01

    The TRUSAF ISB is based upon current facility configuration and procedures. The purpose of the document is to provide the basis for interim operation or restrictions on interim operations and the authorization basis for the TRUSAF at the Hanford Site. The previous safety analysis document TRUSAF hazards Identification and Evaluation (WHC 1977) is superseded by this document

  11. Presidential Transition: The Experience of Two Community College Interim Presidents

    Science.gov (United States)

    Thompson, Matthew D.

    2010-01-01

    The purpose of this qualitative case study was to understand the experiences of two community college interim presidents, their characteristics, and how they led institutions following an abrupt presidential departure. There were two fundamental questions framing this research study, 1. How do two interim community college presidents lead…

  12. Decision on performing interim analysis for comparative clinical trials.

    Science.gov (United States)

    Pak, Kyongsun; Jacobus, Susanna; Uno, Hajime

    2017-09-01

    In randomized-controlled trials, interim analyses are often planned for possible early trial termination to claim superiority or futility of a new therapy. While unblinding is necessary to conduct the formal interim analysis in blinded studies, blinded data also have information about the potential treatment difference between the groups. We developed a blinded data monitoring tool that enables investigators to predict whether they observe such an unblinded interim analysis results that supports early termination of the trial. Investigators may skip some of the planned interim analyses if an early termination is unlikely. We specifically focused on blinded, randomized-controlled studies to compare binary endpoints of a new treatment with a control. Assuming one interim analysis is planned for early termination for superiority or futility, we conducted extensive simulation studies to assess the impact of the implementation of our tool on the size, power, expected number of interim analyses, and bias in the treatment effect. The numerical study showed the proposed monitoring tool does not affect size or power, but dramatically reduces the expected number of interim analyses when the effect of the treatment difference is small. The tool serves as a useful reference when interpreting the summary of the blinded data throughout the course of the trial, without losing integrity of the study. This tool could potentially save the study resources and budget by avoiding unnecessary interim analyses.

  13. General certification procedure of enterprises and interim job enterprises

    CERN Document Server

    Int. At. Energy Agency, Wien

    2002-01-01

    This procedure defines the certification global process of enterprises employing workers of A or B category for nuclear facilities and interim job enterprises proposing workers of A or B category for nuclear facilities. This certification proves the enterprises ability to satisfy the specification ''E'' of the CEFRI and the interim job enterprises to satisfy the specification ''I'' of the CEFRI. (A.L.B.)

  14. 47 CFR 51.715 - Interim transport and termination pricing.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 3 2010-10-01 2010-10-01 false Interim transport and termination pricing. 51.715 Section 51.715 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER... Telecommunications Traffic § 51.715 Interim transport and termination pricing. (a) Upon request from a...

  15. 78 FR 49782 - Interim Staff Guidance on Changes During Construction

    Science.gov (United States)

    2013-08-15

    ... Construction AGENCY: Nuclear Regulatory Commission. ACTION: Draft interim staff guidance; request for comment... During Construction.'' This ISG provides guidance to the NRC staff on the Preliminary Amendment Request...-ISG-025 ``Interim Staff Guidance on Changes during Construction under 10 CFR Part 52'' is available...

  16. Central waste complex interim safety basis

    International Nuclear Information System (INIS)

    Cain, F.G.

    1995-01-01

    This interim safety basis provides the necessary information to conclude that hazards at the Central Waste Complex are controlled and that current and planned activities at the CWC can be conducted safely. CWC is a multi-facility complex within the Solid Waste Management Complex that receives and stores most of the solid wastes generated and received at the Hanford Site. The solid wastes that will be handled at CWC include both currently stored and newly generated low-level waste, low-level mixed waste, contact-handled transuranic, and contact-handled TRU mixed waste

  17. Interim supply in the electricity industry

    Energy Technology Data Exchange (ETDEWEB)

    Strassburg, W

    1977-06-01

    The interim supply or the so-called 'condition without a contract' can occur within the framework of energy supply in the relationship between 1) public utility and tariff customer, 2) public utility and the special last-in-line consumer, 3) supplying and distributing public utility, 4) public utility and territorial administrative body. The present contribution deals with the cases named under (3) and (4). Cases (1) and (2) were dealt with in a previous article. Relevant contract clauses and laws and their effects on contracting partners are discussed.

  18. Interim supply in the electricity industry

    Energy Technology Data Exchange (ETDEWEB)

    Strassburg, W

    1977-05-01

    The interim supply or the so-called 'condition without a contract' can occur within the framework of energy supply in the relationship between: 1) public utility and tariff customer, 2) public utility and the special last-in-line consumer, 3) supplying and distributing public utility, 4) public utility and territorial administrative body. The contribution at hand deals with the cases under 1) and 2); cases 3) and 4) are dealt with in an article to be published. Relevant contract clauses and laws and their effects on contracting partners are discussed. 41 references.

  19. Interim Reliability Evaluation Program procedures guide

    International Nuclear Information System (INIS)

    Carlson, D.D.; Gallup, D.R.; Kolaczkowski, A.M.; Kolb, G.J.; Stack, D.W.; Lofgren, E.; Horton, W.H.; Lobner, P.R.

    1983-01-01

    This document presents procedures for conducting analyses of a scope similar to those performed in Phase II of the Interim Reliability Evaluation Program (IREP). It documents the current state of the art in performing the plant systems analysis portion of a probabilistic risk assessment. Insights gained into managing such an analysis are discussed. Step-by-step procedures and methodological guidance constitute the major portion of the document. While not to be viewed as a cookbook, the procedures set forth the principal steps in performing an IREP analysis. Guidance for resolving the problems encountered in previous analyses is offered. Numerous examples and representative products from previous analyses clarify the discussion

  20. National NIF Diagnostic Program Interim Management Plan

    International Nuclear Information System (INIS)

    Warner, B

    2002-01-01

    The National Ignition Facility (NIF) has the mission of supporting Stockpile Stewardship and Basic Science research in high-energy-density plasmas. To execute those missions, the facility must provide diagnostic instrumentation capable of observing and resolving in time events and radiation emissions characteristic of the plasmas of interest. The diagnostic instrumentation must conform to high standards of operability and reliability within the NIF environment. These exacting standards, together with the facility mission of supporting a diverse user base, has led to the need for a central organization charged with delivering diagnostic capability to the NIF. The National NIF Diagnostics Program (NNDP) has been set up under the aegis of the NIF Director to provide that organization authority and accountability to the wide user community for NIF. The funds necessary to perform the work of developing diagnostics for NIF will be allocated from the National NIF Diagnostics Program to the participating laboratories and organizations. The participating laboratories and organizations will design, build, and commission the diagnostics for NIF. Restricted availability of funding has had an adverse impact, unforeseen at the time of the original decision to projectize NIF Core Diagnostics Systems and Cryogenic Target Handing Systems, on the planning and initiation of these efforts. The purpose of this document is to provide an interim project management plan describing the organizational structure and management processes currently in place for NIF Core Diagnostics Systems. Preparation of a Program Execution Plan for NIF Core Diagnostics Systems has been initiated and a current draft is provided as Attachment 1 to this document. The National NIF Diagnostics Program Interim Management Plan provides a summary of primary design criteria and functional requirements, current organizational structure, tracking and reporting procedures, and current planning estimates of project scope

  1. Developing new transportable storage casks for interim dry storage

    Energy Technology Data Exchange (ETDEWEB)

    Hayashi, K.; Iwasa, K.; Araki, K.; Asano, R. [Hitachi Zosen Diesel and Engineering Co., Ltd., Tokyo (Japan)

    2004-07-01

    Transportable storage metal casks are to be consistently used during transport and storage for AFR interim dry storage facilities planning in Japan. The casks are required to comply with the technical standards of regulations for both transport (hereinafter called ''transport regulation'') and storage (hereafter called ''storage regulation'') to maintain safety functions (heat transfer, containment, shielding and sub-critical control). In addition to these requirements, it is not planned in normal state to change the seal materials during storage at the storage facility, therefore it is requested to use same seal materials when the casks are transported after storage period. The dry transportable storage metal casks that satisfy the requirements have been developed to meet the needs of the dry storage facilities. The basic policy of this development is to utilize proven technology achieved from our design and fabrication experience, to carry out necessary verification for new designs and to realize a safe and rational design with higher capacity and efficient fabrication.

  2. Kennedy Space Center Press Site (SWMU 074) Interim Measure Report

    Science.gov (United States)

    Applegate, Joseph L.

    2015-01-01

    This report summarizes the Interim Measure (IM) activities conducted at the Kennedy Space Center (KSC) Press Site ("the Press Site"). This facility has been designated as Solid Waste Management Unit 074 under KSC's Resource Conservation and Recovery Act Corrective Action program. The activities were completed as part of the Vehicle Assembly Building (VAB) Area Land Use Controls Implementation Plan (LUCIP) Elimination Project. The purpose of the VAB Area LUCIP Elimination Project was to delineate and remove soil affected with constituents of concern (COCs) that historically resulted in Land Use Controls (LUCs). The goal of the project was to eliminate the LUCs on soil. LUCs for groundwater were not addressed as part of the project and are not discussed in this report. This report is intended to meet the Florida Department of Environmental Protection (FDEP) Corrective Action Management Plan requirement as part of the KSC Hazardous and Solid Waste Amendments permit and the U.S. Environmental Protection Agency's (USEPA's) Toxic Substance Control Act (TSCA) self-implementing polychlorinated biphenyl (PCB) cleanup requirements of 40 Code of Federal Regulations (CFR) 761.61(a).

  3. Interim report of working group of Nuclear Fusion Committee

    International Nuclear Information System (INIS)

    Takuma, Hiroshi

    1986-01-01

    The conclusion of the working group was presented as an interim report to the general meeting of Nuclear Fusion Committee, which became the base for deciding the future plan. The report was the result of the hard work for about a half year by five Committee experts and 23 researchers, and has the rich contents. At present, the supply of petroleum relaxed, and the trend that a large amount of investment for a long period for nuclear fusion research is problematical has become strong. Of course, the importance of the nuclear fusion research never changes. The research projects of Heliotron E, Gekko 12, Gamma 10 and so on have advanced, and the base for synthetically promoting the research has been completed. It is indispensable to decide the most effective plan for the next stage. The working group discussed on the five year plan, especially on the research based on a large project. The policy of the works and problems, the progress of the works of respective subgroups, and the summarization are reported. The researches on nuclear burning simulation, no current plasma using an external conductor system and making an axisymmetrical high-beta torus steady were proposed. (Kako, I.)

  4. 76 FR 64071 - Annual Meeting

    Science.gov (United States)

    2011-10-17

    ... APPALACHIAN STATES LOW-LEVEL RADIOACTIVE WASTE COMMISSION Annual Meeting Time and Date: 10 a.m.-12..., PA 17101. Status: The meeting will be open to the public. Matters to be Considered: Portions Open to the Public: The primary purpose of this meeting is to (1) Review the independent auditors' report of...

  5. 75 FR 65297 - Annual Meeting

    Science.gov (United States)

    2010-10-22

    ... APPALACHIAN STATES LOW-LEVEL RADIOACTIVE WASTE COMMISSION Annual Meeting Time And Date: 10 a.m.-12..., PA 17101. Status: The meeting will be open to the public. Matters To Be Considered Portions Open to the Public: The primary purpose of this meeting is to (1) Review the independent auditors' report of...

  6. 78 FR 64472 - Annual Meeting

    Science.gov (United States)

    2013-10-29

    ... APPALACHIAN STATES LOW-LEVEL RADIOACTIVE WASTE COMMISSION Annual Meeting Time and Date: 10 a.m.-12... 17101. Status: The meeting will be open to the public. Matters To Be Considered: Portions Open To The Public: The primary purpose of this meeting is to (1) Review the independent auditors' report of...

  7. 77 FR 61737 - Annual Meeting

    Science.gov (United States)

    2012-10-11

    ... APPALACHIAN STATES LOW-LEVEL RADIOACTIVE WASTE COMMISSION Annual Meeting Time and Date: 10 a.m.-12... 17101. Status: The meeting will be open to the public. Matters To Be Considered Portions Open to the Public: The primary purpose of this meeting is to (1) Review the independent auditors' report of...

  8. Status of ERDA TRU waste packaging study

    International Nuclear Information System (INIS)

    Doty, J.W. Jr.

    1977-01-01

    This paper discusses the status of Task 3 of the TRU Waste Cyclone Drum Incinerator and Treatment System program. This task covers acceptable TRU packaging for interim storage and terminal isolation. The kind of TRU wastes generated by contractors and its transport are discussed. Both drum and box systems are desirable

  9. The status of graphite development for gas cooled reactors. Proceedings of a specialists` meeting held in Tokai, Japan, 9-12 September 1991

    Energy Technology Data Exchange (ETDEWEB)

    1993-02-01

    The meeting was convened by the IAEA on the recommendation of the International Working Group on Gas Cooled Reactors. It was attended by 61 participants from 6 countries. The meeting covered the following subjects: overview of national programs; design criteria, fracture mechanisms and component test; materials development and properties; non-destructive examination, inspection and surveillance. The participants presented 33 papers on behalf of their countries. A separate abstract was prepared for each of these papers. Refs, figs, tabs, photos and diagrams.

  10. National Ignition Facility Cryogenic Target Systems Interim Management Plan

    International Nuclear Information System (INIS)

    Warner, B

    2002-01-01

    Restricted availability of funding has had an adverse impact, unforeseen at the time of the original decision to projectize the National Ignition Facility (NIF) Cryogenic Target Handling Systems (NCTS) Program, on the planning and initiation of these efforts. The purpose of this document is to provide an interim project management plan describing the organizational structure and management processes currently in place for NCTS. Preparation of a Program Execution Plan (PEP) for NCTS has been initiated, and a current draft is provided as Attachment 1 to this document. The National Ignition Facility is a multi-megajoule laser facility being constructed at Lawrence Livermore National Laboratory (LLNL) by the National Nuclear Security Administration (NNSA) in the Department of Energy (DOE). Its primary mission is to support the Stockpile Stewardship Program (SSP) by performing experiments studying weapons physics, including fusion ignition. NIF also supports the missions of weapons effects, inertial fusion energy, and basic science in high-energy-density physics. NIF will be operated by LLNL under contract to the University of California (UC) as a national user facility. NIF is a low-hazard, radiological facility, and its operation will meet all applicable federal, state, and local Environmental Safety and Health (ES and H) requirements. The NCTS Interim Management Plan provides a summary of primary design criteria and functional requirements, current organizational structure, tracking and reporting procedures, and current planning estimates of project scope, cost, and schedule. The NIF Director controls the NIF Cryogenic Target Systems Interim Management Plan. Overall scope content and execution schedules for the High Energy Density Physics Campaign (SSP Campaign 10) are currently undergoing rebaselining and will be brought into alignment with resources expected to be available throughout the NNSA Future Years National Security Plan (FYNSP). The revised schedule for

  11. COMPLETION OF THE FIRST INTEGRATED SPENT NUCLEAR FUEL TRANSSHIPMENT/INTERIM STORAGE FACILITY IN NW RUSSIA

    International Nuclear Information System (INIS)

    Dyer, R.S.; Barnes, E.; Snipes, R.L.; Hoeibraaten, S.; Gran, H.C.; Foshaug, E.; Godunov, V.

    2003-01-01

    Northwest and Far East Russia contain large quantities of unsecured spent nuclear fuel (SNF) from decommissioned submarines that potentially threaten the fragile environments of the surrounding Arctic and North Pacific regions. The majority of the SNF from the Russian Navy, including that from decommissioned nuclear submarines, is currently stored in on-shore and floating storage facilities. Some of the SNF is damaged and stored in an unstable condition. Existing Russian transport infrastructure and reprocessing facilities cannot meet the requirements for moving and reprocessing this amount of fuel. Additional interim storage capacity is required. Most of the existing storage facilities being used in Northwest Russia do not meet health and safety, and physical security requirements. The United States and Norway are currently providing assistance to the Russian Federation (RF) in developing systems for managing these wastes. If these wastes are not properly managed, they could release significant concentrations of radioactivity to these sensitive environments and could become serious global environmental and physical security issues. There are currently three closely-linked trilateral cooperative projects: development of a prototype dual-purpose transport and storage cask for SNF, a cask transshipment interim storage facility, and a fuel drying and cask de-watering system. The prototype cask has been fabricated, successfully tested, and certified. Serial production is now underway in Russia. In addition, the U.S. and Russia are working together to improve the management strategy for nuclear submarine reactor compartments after SNF removal

  12. Radiation shielding and dose rate evaluation at the interim storage facility for spent fuel from Cernavoda NPP

    International Nuclear Information System (INIS)

    Stanciu, Marcela; Mateescu, Silvia; Pantazi, Doina; Penescu, Maria

    2000-01-01

    At present studies necessary to license the Interim Storage Facility for the Spent Fuel (CANDU type) from Cernavoda NPP are developed in our country.The spent fuel from Cernavoda NPP is discharged into Spent Fuel Bay in Service Building of the plant, where it remains several years for cooling. After this period, the bundles of spent fuel are to be transferred to the Interim Storage Facility.The dry interim storage solution seems to be the most appropriate variant for Cernavoda NPP.The design of the Spent Fuel Interim Storage Facility must meet the applicable safety requirements in order to ensure radiological protection of the personnel, public and environment during all phases of the facility achievement. In this paper we intend to present the calculation of radiation shielding at the spent fuel interim storage facility for two technical solutions: - Concrete Monolithic Module and Concrete Storage Cask. In order to quantify the fuel composition after irradiation, the isotope generation and depletion code ORIGEN 2.1 has been used, taking into account a cooling time of 7 years and 9 years, respectively, for these two variants. The shielding calculations have been performed using the computer codes QAD-5K and MICROSHIELD-4. The evaluations refer only to gamma radiation because the resulting neutron source (from (α,n) reactions and spontaneous fission) is insignificant as compared to the gamma source. The final results consist in the minimum thickness of the shielding and the corresponding external dose rates, ensuring a design average dose rate based on national and international regulations. (authors)

  13. Sustainable Solutions for Nuclear used Fuels Interim Storage

    International Nuclear Information System (INIS)

    Arslan, Marc; Favet, Dominique; Issard, Herve; Le Jemtel, Amaury; Drevon, Caroline

    2014-01-01

    AREVA has a unique experience in providing sustainable solutions for used fuel management, fitted with the needs of different customers in the world and with regulation in different countries. These solutions entail both recycling and interim storage technologies. In a first part, we will describe the various types of solutions for Interim Storage of UNF that have been implemented around the world for interim storage at reactor or centralized Pad solution in canisters dry storage, vault type storages for dry storage, dry storage of transportation casks (dual purpose) pools for wet storage, The experience for all these different families of interim storages in which AREVA is involved is extensive and will be discussed with respect to the new challenges: increase of the duration of the interim storage (long term interim storage) increase of burn up of the fuels In a second part of the presentation, special recycling features will be presented. In that case, interim storage of the used fuels is ensured in pools. This provides in the long term good conditions for the behaviour of the fuel and its retrievability. With recycling, the final waste (Universal Canister of vitrified fission products and compacted hulls and end pieces): is stable and licensed in many countries for the final disposal (France, UK, Belgium, NL, Switzerland, Germany, Japan, upcoming: Spain, Australia, Italy). Presents neither safety criticality risks nor proliferation risks (AREVA conditioned HLW and LL-ILW are free of IAEA safeguard constraints thanks to AREVA process high recovery and purification yields). It can therefore be safely stored in interim storage for more than 100 years before final disposal. Some economic considerations will also be discussed. In particular, in the case of long term interim storage of used fuels, there are growing uncertainties regarding the future needs of repackaging and transportation, which can result in future cost overruns. Meanwhile, in the recycling policy

  14. Retention of long-term interim restorations with sodium fluoride enriched interim cement

    Science.gov (United States)

    Strash, Carolyn

    Purpose: Interim fixed dental prostheses, or "provisional restorations", are fabricated to restore teeth when definitive prostheses are made indirectly. Patients undergoing extensive prosthodontic treatment frequently require provisionalization for several months or years. The ideal interim cement would retain the restoration for as long as needed and still allow for ease of removal. It would also avoid recurrent caries by preventing demineralization of tooth structure. This study aims to determine if adding sodium fluoride varnish to interim cement may assist in the retention of interim restorations. Materials and methods: stainless steel dies representing a crown preparation were fabricated. Provisional crowns were milled for the dies using CAD/CAM technology. Crowns were provisionally cemented onto the dies using TempBond NE and NexTemp provisional cements as well as a mixture of TempBond NE and Duraphat fluoride varnish. Samples were stored for 24h then tested or thermocycled for 2500 or 5000 cycles before being tested. Retentive strength of each cement was recorded using a universal testing machine. Results: TempBond NE and NexTemp cements performed similarly when tested after 24h. The addition of Duraphat significantly decreased the retention when added to TempBond NE. NexTemp cement had high variability in retention over all tested time periods. Thermocycling for 2500 and 5000 cycles significantly decreased the retention of all cements. Conclusions: The addition of Duraphat fluoride varnish significantly decreased the retention of TempBond NE and is therefore not recommended for clinical use. Thermocycling significantly reduced the retention of TempBond NE and NexTemp. This may suggest that use of these cements for three months, as simulated in this study, is not recommended.

  15. Status of National Programmes on Fast Breeder Reactors. International Working Group on Fast Reactors Twenty-First Annual Meeting, Seattle, USA, 9-12 May 1988

    International Nuclear Information System (INIS)

    1988-11-01

    The following papers on the status of national programmes on fast breeder reactors are presented in this report: Fast breeder reactor development in France during 1987; Status of fast breeder reactor development in the Federal Republic of Germany, Belgium and the Netherlands; A review of the Indian fast reactor programme; A review of the Italian fast reactor programme; A review of the fast reactor programme in Japan; Status of fast reactor activities in the USSR; A review of the United Kingdom fast reactor programme; Status of liquid metal reactor development in the United States of America; Review of activities of the Commission of European Communities relating to fast reactors in 1987; European co-operation in the field of fast reactor research and development — 1987 progress report; A review of fast reactor activities in Switzerland

  16. Mobile Launch Platform Vehicle Assembly Area (SWMU 056) Biosparge Expansion Interim Measures Work Plan

    Science.gov (United States)

    Burcham, Michael S.; Daprato, Rebecca C.

    2016-01-01

    This document presents the design details for an Interim Measure (IM) Work Plan (IMWP) for the Mobile Launch Platform/Vehicle Assembly Building (MLPV) Area, located at the John F. Kennedy Space Center (KSC), Florida. The MLPV Area has been designated Solid Waste Management Unit Number 056 (SWMU 056) under KSC's Resource Conservation and Recovery Act (RCRA) Corrective Action Program. This report was prepared by Geosyntec Consultants (Geosyntec) for the National Aeronautics and Space Administration (NASA) under contract number NNK09CA02B and NNK12CA13B, project control number ENV1642. The Advanced Data Package (ADP) presentation covering the elements of this IMWP report received KSC Remediation Team (KSCRT) approval at the December 2015 Team Meeting; the meeting minutes are included in Appendix A.

  17. PROJECT W-551 INTERIM PRETREATMENT SYSTEM PRECONCEPTUAL CANDIDATE TECHNOLOGY DESCRIPTIONS

    Energy Technology Data Exchange (ETDEWEB)

    MAY TH

    2008-08-12

    The Office of River Protection (ORP) has authorized a study to recommend and select options for interim pretreatment of tank waste and support Waste Treatment Plant (WTP) low activity waste (LAW) operations prior to startup of all the WTP facilities. The Interim Pretreatment System (IPS) is to be a moderately sized system which separates entrained solids and 137Cs from tank waste for an interim time period while WTP high level waste vitrification and pretreatment facilities are completed. This study's objective is to prepare pre-conceptual technology descriptions that expand the technical detail for selected solid and cesium separation technologies. This revision includes information on additional feed tanks.

  18. 77 FR 43064 - Defense Science Board; Notice of Advisory Committee Meetings

    Science.gov (United States)

    2012-07-23

    ... Science Board 2012 Summer Study on Technology and Innovation Enablers for Superiority in 2030 will meet in closed session August 20-24, 2012, from 8:00 a.m. to 5:00 p.m. at the Charles Stark Draper Laboratory... meeting, the Board will discuss interim finding and recommendations resulting from ongoing Task Force...

  19. Hierarchies of belief and interim rationalizability

    Directory of Open Access Journals (Sweden)

    Jeffrey C. Ely

    2006-03-01

    Full Text Available In games with incomplete information, conventional hierarchies of belief are incomplete as descriptions of the players' information for the purposes of determining a player's behavior. We show by example that this is true for a variety of solution concepts. We then investigate what is essential about a player's information to identify behavior. We specialize to two player games and the solution concept of interim rationalizability. We construct the universal type space for rationalizability and characterize the types in terms of their beliefs. Infinite hierarchies of beliefs over conditional beliefs, which we call Delta-hierarchies, are what turn out to matter. We show that any two types in any two type spaces have the same rationalizable sets in all games if and only if they have the same Delta-hierarchies.

  20. Interim report and accounts 1993/94

    International Nuclear Information System (INIS)

    1993-01-01

    An interim set of accounts and reports is presented here for 1993/1994 for the health science company Amersham International. The company's research programs focus on developments in life science research, nuclear medicine and industrial quality and safety assurance, with particular expertise in the application of radioactivity to labelling and detection at the molecular level. This report which covers the half-year to 30 September 1993 shows promising financial results, with turnover, operating profits and earnings per share all having risen. All life science markets report growth although difficult trading conditions are being reported in Europe. Two products in the Healthcare business have achieved progress, a pain palliation agent for bone metastases has been launched in the United States, and European approval has been gained for a new technetium based heart imaging agent. Further growth is expected for the company. (UK)

  1. Safety regulations for radioisotopes, etc. (interim report)

    International Nuclear Information System (INIS)

    1980-01-01

    An (interim) report by an ad hoc expert committee to the Nuclear Safety Commission, on the safety regulations for radioisotopes, etc., was presented. For the utilization of radioisotopes, etc., there is the Law Concerning Prevention of Radiation Injury Due to Radioisotopes, etc. with the advances in this field and the improvement in international standards, the regulations by the law have been examined. After explaining the basic ideas of the regulations, the problems and countermeasures in the current regulations are described: legal system, rationalization in permission procedures and others, inspection on RI management, the system of the persons in charge of radiation handling, RI transport, low-level radioactive wastes, consumer goods, definitions of RIs, radiation and sealed sources, regulations by group partitioning, RI facilities, system of personnel exposure registration, entrusting of inspection, etc. to private firms, and reduction in the works for permission among governmental offices. (author)

  2. Interim Hanford Waste Management Technology Plan

    International Nuclear Information System (INIS)

    1985-09-01

    The Interim Hanford Waste Management Technology Plan (HWMTP) is a companion document to the Interim Hanford Waste Management Plan (HWMP). A reference plan for management and disposal of all existing and certain projected future radioactive Hanford Site Defense Wastes (HSDW) is described and discussed in the HWMP. Implementation of the reference plan requires that various open technical issues be satisfactorily resolved. The principal purpose of the HWMTP is to present detailed descriptions of the technology which must be developed to close each of the technical issues associated with the reference plan identified in the HWMP. If alternative plans are followed, however, technology development efforts including costs and schedules must be changed accordingly. Technical issues addressed in the HWMTP and HWMP are those which relate to disposal of single-shell tank wastes, contaminated soil sites, solid waste burial sites, double-shell tank wastes, encapsulated 137 CsCl and 90 SrF 2 , stored and new solid transuranic (TRU) wastes, and miscellaneous wastes such as contaminated sodium metal. Among the high priority issues to be resolved are characterization of various wastes including early determination of the TRU content of future cladding removal wastes; completion of development of vitrification (Hanford Waste Vitrification Plant) and grout technology; control of subsidence in buried waste sites; and development of criteria and standards including performance assessments of systems proposed for disposal of HSDW. Estimates of the technology costs shown in this report are made on the basis that all identified tasks for all issues associated with the reference disposal plan must be performed. Elimination of, consolidation of, or reduction in the scope of individual tasks will, of course, be reflected in corresponding reduction of overall technology costs

  3. The incorporation of boron in fissile transport packages for the transport and interim storage of irradiated light water reactor fuels

    International Nuclear Information System (INIS)

    Hunter, I.J.

    1998-01-01

    Boron is widely used in the nuclear industry for capturing neutrons and it is particularly useful in the criticality control of packages for the transport and interim storage of irradiated light water reactor fuels. Such fuels are typically located in an internal frame of stainless steel or aluminium, referred to as a basket, which locates the fuel assemblies in channels. Transnucleaire has designed and supplied more than 100 baskets of varying types during the past 30 years. Boron has been incorporated in many forms. Early designs of baskets used boron in specific zones to contribute to the control of criticality. Later developments in new materials dispersed boron throughout the basket and gave designers more options for the basic forms which make up the channels. New basket concepts have been developed by Transnucleaire to meet the changing market needs for transport and interim storage and boron continues to play an important role as an efficient thermal neutron absorber. (author)

  4. Strategic Review of Medical Training and Career Structure Interim Report

    OpenAIRE

    Department of Health (Ireland)

    2013-01-01

    Click here to download Strategic Review of Medical Training and Career Structure Interim Report PDF 44kb Click here to download Strategic Review of Medical Training and Career Structure Terms of Reference PDF 59KB

  5. Fuel Supply Shutdown Facility Interim Operational Safety Requirements

    International Nuclear Information System (INIS)

    BENECKE, M.W.

    2000-01-01

    The Interim Operational Safety Requirements for the Fuel Supply Shutdown (FSS) Facility define acceptable conditions, safe boundaries, bases thereof, and management of administrative controls to ensure safe operation of the facility

  6. Fire Hazards Analysis for the 200 Area Interim Storage Area

    International Nuclear Information System (INIS)

    JOHNSON, D.M.

    2000-01-01

    This documents the Fire Hazards Analysis (FHA) for the 200 Area Interim Storage Area. The Interim Storage Cask, Rad-Vault, and NAC-1 Cask are analyzed for fire hazards and the 200 Area Interim Storage Area is assessed according to HNF-PRO-350 and the objectives of DOE Order 5480 7A. This FHA addresses the potential fire hazards associated with the Interim Storage Area (ISA) facility in accordance with the requirements of DOE Order 5480 7A. It is intended to assess the risk from fire to ensure there are no undue fire hazards to site personnel and the public and to ensure property damage potential from fire is within acceptable limits. This FHA will be in the form of a graded approach commensurate with the complexity of the structure or area and the associated fire hazards

  7. Tank Farm Interim Surface Barrier Materials And Runoff Alternatives Study

    International Nuclear Information System (INIS)

    Holm, M.J.

    2009-01-01

    This report identifies candidate materials and concepts for interim surface barriers in the single-shell tank farms. An analysis of these materials for application to the TY tank farm is also provided.

  8. Interim research assessment 2003-2005 - Computer Science

    NARCIS (Netherlands)

    Mouthaan, A.J.; Hartel, Pieter H.

    This report primarily serves as a source of information for the 2007 Interim Research Assessment Committee for Computer Science at the three technical universities in the Netherlands. The report also provides information for others interested in our research activities.

  9. Interim Feed The Future Population Based Assessment of Cambodia

    Data.gov (United States)

    US Agency for International Development — This is the interim population based survey of Feed the Future in Cambodia for 2015. The data is split into survey modules. Modules A through C includes location...

  10. EPA's Revised Interim Financial Assistance Conflict of Interest Policy

    Science.gov (United States)

    EPA has established the following revised interim policy governing disclosure of actual and potential conflicts of interest (COI Policy) by applicants for, and recipients of, federal financial assistance awards from EPA.

  11. Interim report on long range plan for nuclear physics

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    The interim report on the updated NSAC Long Range Plan for Nuclear Physics will be presented to the community for discussion and comment before submission to the funding agencies. The presentation will be coordinated by E. Moniz chair of NSAC

  12. Evaluation of Hose in Hose Transfer Line Service Life for Hanfords Interim Stabilization Program

    International Nuclear Information System (INIS)

    TORRES, T.D.

    2001-01-01

    RPP-6153, Engineering Task Plan for Hose-in-Hose Transfer System for the Interim Stabilization Program (Torres, 2000a), defines the programmatic goals, functional requirements, and technical criteria for the development and subsequent installation of waste transfer line equipment to support Hanford's Interim Stabilization Program. RPP-6028, Specification for Hose in Hose Transfer Lines for Hanford's Interim Stabilization Program (Torres, 2000b), has been issued to define the specific requirements for the design, manufacture, and verification of transfer line assemblies for specific waste transfer applications associated with Interim Stabilization. Included in RPP-6028 are tables defining the chemical constituents of concern to which transfer lines will be exposed. Current Interim Stabilization Program planning forecasts that the at-grade transfer lines will be required to convey pumpable waste for as much as three years after commissioning, RPP-6028 Section 3.2.7. Performance Incentive Number ORP-05 requires that all the Single Shell Tanks be Interim Stabilized by September 30, 2003. The Tri-Party Agreement (TPA) milestone M-41-00, enforced by a federal consent decree, requires all the Single Shell Tanks to be Interim stabilized by September 30, 2004. By meeting the Performance Incentive the TPA milestone is met. Prudent engineering dictates that the equipment used to transfer waste have a life in excess of the forecasted operational time period, with some margin to allow for future adjustments to the planned schedule. This document evaluates the effective service life of the Hose-in-Hose Transfer Lines, based on information submitted by the manufacturer, published literature and calculations. The effective service life of transfer line assemblies is a function of several factors. Foremost among these are the hose material's resistance to the harmful effects of process fluid characteristics, ambient environmental conditions, exposure to ionizing radiation and the

  13. TWRS HLW interim storage facility search and evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Calmus, R.B., Westinghouse Hanford

    1996-05-16

    The purpose of this study was to identify and provide an evaluation of interim storage facilities and potential facility locations for the vitrified high-level waste (HLW) from the Phase I demonstration plant and Phase II production plant. In addition, interim storage facilities for solidified separated radionuclides (Cesium and Technetium) generated during pretreatment of Phase I Low-Level Waste Vitrification Plant feed was evaluated.

  14. K basins interim remedial action health and safety plan

    Energy Technology Data Exchange (ETDEWEB)

    DAY, P.T.

    1999-09-14

    The K Basins Interim Remedial Action Health and Safety Plan addresses the requirements of the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), as they apply to the CERCLA work that will take place at the K East and K West Basins. The provisions of this plan become effective on the date the US Environmental Protection Agency issues the Record of Decision for the K Basins Interim Remedial Action, currently planned in late August 1999.

  15. Interim Report by Asia International Grid Connection Study Group

    Science.gov (United States)

    Omatsu, Ryo

    2018-01-01

    The Asia International Grid Connection Study Group Interim Report examines the feasibility of developing an international grid connection in Japan. The Group has investigated different cases of grid connections in Europe and conducted research on electricity markets in Northeast Asia, and identifies the barriers and challenges for developing an international grid network including Japan. This presentation introduces basic contents of the interim report by the Study Group.

  16. ITER interim design report package and relevant documents

    International Nuclear Information System (INIS)

    1996-01-01

    This publication documents the technical basis which underlay the Interim Design Report, Cost Review and Safety Analysis submitted to the ITER Councils (IC-8 and IC-9) Records of decisions and the ''ITER Interim Design Report Package''. This publication contains ITER Site Requirements and ITER Site Design Assumptions, TAC-8 Report, SRG Report, CP's Report on Tentative Sequence of Events and Parties' Views on the IDR Package and Parties' Technical Comments on the IDR Package. Figs, tabs

  17. Materials behavior in interim storage of spent fuel

    International Nuclear Information System (INIS)

    Johnson, A.B. Jr.; Bailey, W.J.; Gilbert, E.R.; Inman, S.C.

    1982-01-01

    Interim storage has emerged as the only current spent-fuel management method in the US and is essential in all countries with nuclear reactors. Materials behavior is a key aspect in licensing interim-storage facilities for several decades of spent-fuel storage. This paper reviews materials behavior in wet storage, which is licensed for light-water reactor (LWR) fuel, and dry storage, for which a licensing position for LWR fuel is developing

  18. Interim Safety Basis for Fuel Supply Shutdown Facility

    International Nuclear Information System (INIS)

    BENECKE, M.W.

    2000-01-01

    This ISB, in conjunction with the IOSR, provides the required basis for interim operation or restrictions on interim operations and administrative controls for the facility until a SAR is prepared in accordance with the new requirements or the facility is shut down. It is concluded that the risks associated with tha current and anticipated mode of the facility, uranium disposition, clean up, and transition activities required for permanent closure, are within risk guidelines

  19. Interim report of the task force on energy policy

    International Nuclear Information System (INIS)

    2001-01-01

    A Task Force was established by the Premier of British Columbia in August 2001 to draft an energy policy framework for the province. Based on best practices worldwide, and keeping in mind the specific energy needs of British Columbia, this framework aims at fostering energy development in British Columbia, in accordance with exemplary environmental practices. This interim report comprises the preliminary findings of the Task Force, and public input is sought before the final report is finalized and presented to government. The energy sector of British Columbia comprises hydroelectric power, oil, gas and coal resources. In addition, green energy and alternative energy technologies are being developed, such as wind, solar, and wave power, and hydrogen fuel cells. Industry and individual consumers are well served by the highly developed transmission and distribution systems for energy. Several strategic directions were identified by the Task Force for inclusion in the energy policy of British Columbia, to meet its full potential. They are: growth to ensure safe, reliable energy and take advantage of economic opportunities; diversification; competitiveness; industry restructuring and expansion; environmental imperative; government leadership; and community and First Nations' involvement. Some changes are also required for the continuing success of the energy sector in British Columbia: a move to fully competitive markets in the electricity system, the development of natural gas storage capacity in the Lower Mainland, additional considerations for coal use, and the development of alternative energy sources. It is expected that private capital and more energy supply will result from a fully competitive energy market, which in turn would lower energy costs. Jobs and income would increase as a result of the growth in the sector. Diversification makes good economic and environmental sense. tabs., figs

  20. 78 FR 8203 - Sunshine Act Meetings

    Science.gov (United States)

    2013-02-05

    ...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of... Meeting) (Contact: Ken Karwoski, 301-415-2752) This meeting will be webcast live at the web address--www... Uranium Recovery (Public Meeting) (Contact: Bill von Till, 301-415-0598) This meeting will be webcast live...

  1. 78 FR 69141 - Sunshine Act Meeting

    Science.gov (United States)

    2013-11-18

    ... POSTAL REGULATORY COMMISSION Sunshine Act Meeting TIME AND DATE: Wednesday, December 11, 2013, at.... STATUS: Part of this meeting will be open to the public. The rest of the meeting will be closed to the... December 11, 2013 meeting includes the items identified below. PORTIONS OPEN TO THE PUBLIC: 1. Report from...

  2. 78 FR 69086 - Sunshine Act Meeting

    Science.gov (United States)

    2013-11-18

    ... FEDERAL ELECTION COMMISSION Sunshine Act Meeting AGENCY: Federal Election Commission. Federal... 19, 2013 at 10:00 a.m. PLACE: 999 E Street NW., Washington, DC. STATUS: This meeting will be closed to the public. CHANGES IN THE MEETING: The meeting will begin at 11:00 a.m. ITEMS TO BE DISCUSSED...

  3. 20 CFR 200.6 - Open meetings.

    Science.gov (United States)

    2010-04-01

    ... information with respect to a meeting, the scheduling of a meeting, the establishment of the agenda of a meeting, or any change in the scheduling, agenda, or the open or closed status of a meeting; or (ii.... [42 FR 15312, Mar. 21, 1977, as amended at 42 FR 22865, Nov. 11, 1977. Redesignated at 52 FR 11010...

  4. Proceedings of the Annual Meeting of the Association for Education in Journalism and Mass Communication (82nd, New Orleans, Louisiana, August 3-8, 1999). Status of Women.

    Science.gov (United States)

    Association for Education in Journalism and Mass Communication.

    The Status of Women section of the Proceedings contains the following 8 papers: "Coverage of Mars Exploration: Media Messages about Women Scientists" (Karon R. Speckman and Lois A. Bichler); "The Case of President Clinton and the Feminists: Discourses of Feminism in the News" (Dustin Harp); "Liberal Feminist Theory and…

  5. Total absorption gamma-ray spectroscopy (TAGS): Current status of measurement programmes for decay heat calculations and other applications. Summary report of consultants' meeting

    International Nuclear Information System (INIS)

    Nichols, A.L.; Nordborg, C.

    2009-02-01

    A Consultants' Meeting on 'Total Absorption Gamma-ray Spectroscopy (TAGS)' was held on 27-28 January 2009 at the IAEA Headquarters, Vienna, Austria. All presentations, discussions and recommendations of this meeting are contained within this report. The purpose of the meeting was to report and discuss progress and plans to measure total gamma-ray spectra in order to derive mean beta and gamma decay data for decay heat calculations and other applications. This form of review had been recommended by contributors to Subgroup 25 of the OECD-NEA Working Party on International Evaluation Cooperation of the Nuclear Science Committee, for implementation in 2008/09. Hence, relevant specialists were invited to discuss their recently performed and planned TAGS studies, along with experimentalists proposing to assemble and operate such dedicated facilities. Knowledge and quantification of antineutrino spectra is believed to be a significant asset in the non-invasive monitoring of reactor operations and possible application in safeguards, as well as fundamental in the study of neutrino oscillations - these data needs were also debated in terms of appropriate TAGS measurements. A re-assessment of the current request list for TAGS studies is merited and was undertaken in the context of decay heat calculations, and agreement was reached to extend these requirements to the derivation of antineutrino spectra. (author)

  6. 78 FR 57621 - Sunshine Act Meeting

    Science.gov (United States)

    2013-09-19

    ... CONSUMER PRODUCT SAFETY COMMISSION Sunshine Act Meeting TIME AND DATE: Wednesday, September 25..., Maryland. STATUS: Commission Meeting--Open to the public Matters To Be Considered Briefing Matter: Voluntary Recall Notice--Notice of Proposed Rulemaking. [[Page 57622

  7. 75 FR 15419 - Sunshine Act Meetings

    Science.gov (United States)

    2010-03-29

    .... Status: Commission Meeting--Open to the Public. Matter To Be Considered 1. Pending Decisional Matter: Definition of Children's Product-- Notice of Proposed Rulemaking (NPR). A live Web cast of the Meeting can be...

  8. Interim report on the accident at Fukushima Nuclear Power Stations of Tokyo Electric Power Company

    International Nuclear Information System (INIS)

    2011-12-01

    The Investigation Committee on the Accident at the Fukushima Nuclear Power Stations (the Investigation Committee) of Tokyo Electric Power Company (TEPCO) was established by the Cabinet decision on May 24, 2011. Its objectives are: to conduct investigation for finding out the causes of accidents at the Fukushima Dai-ichi Nuclear Power Station (Fukushima Dai-ichi NPS) and Fukushima Dai-ni Nuclear Power Station (Fukushima Dai-ni NPS) of TEPCO as well as the causes of accident damage; and to make policy recommendations for limiting the expansion of damage and preventing reoccurrence of similar accidents. The Investigation Committee has conducted its investigation and evaluation since its first meeting on June 7, 2011. Its activities included: site visits to the Fukushima Dai-ichi and Dai-ni NPSs, as well as to other facilities; hearing of heads of local governments around the Fukushima Dai-ichi NPS; and hearing of people concerned through interviews mainly arranged by the Secretariat. As of December 16, 2011, the number of interviewees reached 456. The investigation and evaluation by the Investigation Committee are still ongoing and the Interim Report does not cover every item that the Committee aims at investigating and evaluating. Fact-finding of even some of those items discussed in the Interim Report are not yet completed. The Investigation Committee continues to conduct its investigation and evaluation and will issue its Final Report in the summer of 2012. This brief executive summary covers mainly considerations and evaluation of the issues in Chapter VII of the Interim Report, with brief reference to Chapters I to VI. The Investigation Committee recommendations are printed in bold. (author)

  9. Facility status and progress of the INEL's WERF MLLW and LLW incinerator

    International Nuclear Information System (INIS)

    Conley, D.; Corrigan, S.

    1996-01-01

    The Idaho National Engineering Laboratory's (INEL) Waste Experimental Reduction Facility (WERF) incinerator began processing beta/gamma- emitting low-level waste (LLW) in September 1984. A Resource Conservation and Recovery Act (RCRA) trial burn for the WERF incinerator was conducted in 1986, and in 1989 WERF began processing (hazardous and low-level radioactive) waste known as mixed low-level waste (MLLW). On February 14, 1991 WERF operations were suspended to improve operating procedures and configuration management. On July 12, 1995, WERF initiated incineration of LLW; and on September 20, 1995 WERF resumed its primary mission of incinerating MLLW. MLLW incineration is proceeding under RCRA interim status. State of Idaho issuance of the Part B permit is one of the State's highest permitting priorities. The State of Idaho's Division of Environmental Quality is reviewing the permit application along with a revised trial burn plan that was also submitted with the application. The trial burn has been proposed to be performed in 1996 to demonstrate compliance with the current incinerator guidance. This paper describes the experiences and problems associated with WERF's operations, incineration of MLLW, and the RCRA Part B Permit Application. Some of the challenges that have been overcome include waste characterization, waste repackaging, repackaged waste storage, and implementation of RCRA interim status requirements. A number of challenges remain. They include revision of the RCRA Part B Permit Application and the Trial Burn Plan in response to comments from the state permit application reviewers as well as facility and equipment upgrades required to meet RCRA Permitted Status

  10. High Temperature Materials Interim Data Qualification Report FY 2011

    International Nuclear Information System (INIS)

    Lybeck, Nancy

    2011-01-01

    Projects for the very high temperature reactor (VHTR) Technology Development Office provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the Next Generation Nuclear Plant (NGNP) Data Management and Analysis System (NDMAS) to ensure that VHTR data are qualified for use, stored in a readily accessible electronic form, and analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the High Temperature Materials characterization data stream, the processing of these data within NDMAS, and reports the interim fiscal year (FY) 2011 qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. The High Temperature Materials data are being collected under the Nuclear Quality Assurance (NQA)-1 guidelines and will be qualified data. For NQA-1 qualified data, the qualification activities include: (1) capture testing to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing to confirm that the data are an accurate representation of the system or object being measured, and (3) documenting that the data were collected under an NQA-1 or equivalent Quality Assurance program. Currently, data from seven test series within the High Temperature Materials data stream have been entered into the NDMAS vault, including tensile tests, creep tests, and cyclic tests. Of the 5,603,682 records currently in the vault, 4,480,444 have been capture passed, and capture testing is in process for the remaining 1,123,238.

  11. Evaluation of ERA-Interim precipitation data in complex terrain

    Science.gov (United States)

    Gao, Lu; Bernhardt, Matthias; Schulz, Karsten

    2013-04-01

    Precipitation controls a large variety of environmental processes, which is an essential input parameter for land surface models e.g. in hydrology, ecology and climatology. However, rain gauge networks provides the necessary information, are commonly sparse in complex terrains, especially in high mountainous regions. Reanalysis products (e.g. ERA-40 and NCEP-NCAR) as surrogate data are increasing applied in the past years. Although they are improving forward, previous studies showed that these products should be objectively evaluated due to their various uncertainties. In this study, we evaluated the precipitation data from ERA-Interim, which is a latest reanalysis product developed by ECMWF. ERA-Interim daily total precipitation are compared with high resolution gridded observation dataset (E-OBS) at 0.25°×0.25° grids for the period 1979-2010 over central Alps (45.5-48°N, 6.25-11.5°E). Wet or dry day is defined using different threshold values (0.5mm, 1mm, 5mm, 10mm and 20mm). The correspondence ratio (CR) is applied for frequency comparison, which is the ratio of days when precipitation occurs in both ERA-Interim and E-OBS dataset. The result shows that ERA-Interim captures precipitation occurrence very well with a range of CR from 0.80 to 0.97 for 0.5mm to 20mm thresholds. However, the bias of intensity increases with rising thresholds. Mean absolute error (MAE) varies between 4.5 mm day-1 and 9.5 mm day-1 in wet days for whole area. In term of mean annual cycle, ERA-Interim almost has the same standard deviation of the interannual variability of daily precipitation with E-OBS, 1.0 mm day-1. Significant wet biases happened in ERA-Interim throughout warm season (May to August) and dry biases in cold season (November to February). The spatial distribution of mean annual daily precipitation shows that ERA-Interim significant underestimates precipitation intensity in high mountains and northern flank of Alpine chain from November to March while pronounced

  12. Comparative assessment of radiation versus nutritional and other factors that may influence immune status. Report of a Joint IAEA/WHO advisory group meeting, Vienna, Austria, 3-6 May 1994

    International Nuclear Information System (INIS)

    1994-01-01

    An Advisory Group Meeting was convened jointly by the International Atomic Energy Agency and the World Health Organization in May 1994 to review the role of radiation, nutrition, toxic chemicals and other factors that may influence immune status in human populations. Priorities for future research were proposed, and possibilities for using isotope in such studies were identified. The Group recommended that the IAEA should initiate a broadly based Co-ordinated Research Programme (CRP) focussed mainly on the effects of low-level radiation on immune status in human populations. The main variables of interest are (i) the level of individual radiation exposure, and (ii) the nutritional status. Possible experimental groups include persons living in areas of high radiation background (e.g. in countries where areas of high radiation background are known to occur naturally, or at high altitudes, or in areas affected by Chernobyl accident). Other possible experimental groups comprise radiation workers and uranium miners. It was also recommended that the contribution of toxic chemical exposure to immune dysfunction in these population groups should be assessed. Such research should be complemented by animal studies, and possibly also by in vitro studies with human and animal cells, by some participants in the CRP. This report has been prepared as a source of information for potential participants in the proposed CRP and for other persons associated with related programmes of the IAEA and the WHO. 15 refs, 1 fig., 7 tabs

  13. 80th Annual Meeting | Annual Meetings | Events | Indian Academy of ...

    Indian Academy of Sciences (India)

    Current status and future prospects of neutrino mass measurement. View presentation ... Business Meeting of Fellows. 17.00. High Tea ... Hints of 'Beyond Standard Model' cosmology in the cosmic microwave background. View presentation.

  14. 76 FR 56409 - Notice of Interim Approval

    Science.gov (United States)

    2011-09-13

    ... relationship of mutual respect and trust between the parties and the preference customers to resolve... customers consistent with sound business principles. Environmental Impact Southeastern has reviewed the... meet repayment criteria. However, the Jim Woodruff preference customers asked Southeastern to revise...

  15. 340 Waste Handling Facility interim safety basis

    International Nuclear Information System (INIS)

    Bendixsen, R.B.

    1995-01-01

    This document establishes the interim safety basis (ISB) for the 340 Waste Handling Facility (340 Facility). An ISB is a documented safety basis that provides a justification for the continued operation of the facility until an upgraded final safety analysis report is prepared that complies with US Department of Energy (DOE) Order 5480.23, Nuclear Safety Analysis Reports. The ISB for the 340 Facility documents the current design and operation of the facility. The 340 Facility ISB (ISB-003) is based on a facility walkdown and review of the design and operation of the facility, as described in the existing safety documentation. The safety documents reviewed, to develop ISB-003, include the following: OSD-SW-153-0001, Operating Specification Document for the 340 Waste Handling Facility (WHC 1990); OSR-SW-152-00003, Operating Limits for the 340 Waste Handling Facility (WHC 1989); SD-RE-SAP-013, Safety Analysis Report for Packaging, Railroad Liquid Waste Tank Cars (Mercado 1993); SD-WM-TM-001, Safety Assessment Document for the 340 Waste Handling Facility (Berneski 1994a); SD-WM-SEL-016, 340 Facility Safety Equipment List (Berneski 1992); and 340 Complex Fire Hazard Analysis, Draft (Hughes Assoc. Inc. 1994)

  16. Interim Basis for PCB Sampling and Analyses

    International Nuclear Information System (INIS)

    BANNING, D.L.

    2001-01-01

    This document was developed as an interim basis for sampling and analysis of polychlorinated biphenyls (PCBs) and will be used until a formal data quality objective (DQO) document is prepared and approved. On August 31, 2000, the Framework Agreement for Management of Polychlorinated Biphenyls (PCBs) in Hanford Tank Waste was signed by the US. Department of Energy (DOE), the Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology) (Ecology et al. 2000). This agreement outlines the management of double shell tank (DST) waste as Toxic Substance Control Act (TSCA) PCB remediation waste based on a risk-based disposal approval option per Title 40 of the Code of Federal Regulations 761.61 (c). The agreement calls for ''Quantification of PCBs in DSTs, single shell tanks (SSTs), and incoming waste to ensure that the vitrification plant and other ancillary facilities PCB waste acceptance limits and the requirements of the anticipated risk-based disposal approval are met.'' Waste samples will be analyzed for PCBs to satisfy this requirement. This document describes the DQO process undertaken to assure appropriate data will be collected to support management of PCBs and is presented in a DQO format. The DQO process was implemented in accordance with the U.S. Environmental Protection Agency EPA QAlG4, Guidance for the Data Quality Objectives Process (EPA 1994) and the Data Quality Objectives for Sampling and Analyses, HNF-IP-0842/Rev.1 A, Vol. IV, Section 4.16 (Banning 1999)

  17. The EMEFS model evaluation. An interim report

    Energy Technology Data Exchange (ETDEWEB)

    Barchet, W.R. [Pacific Northwest Lab., Richland, WA (United States); Dennis, R.L. [Environmental Protection Agency, Research Triangle Park, NC (United States); Seilkop, S.K. [Analytical Sciences, Inc., Durham, NC (United States); Banic, C.M.; Davies, D.; Hoff, R.M.; Macdonald, A.M.; Mickle, R.E.; Padro, J.; Puckett, K. [Atmospheric Environment Service, Downsview, ON (Canada); Byun, D.; McHenry, J.N. [Computer Sciences Corp., Research Triangle Park, NC (United States); Karamchandani, P.; Venkatram, A. [ENSR Consulting and Engineering, Camarillo, CA (United States); Fung, C.; Misra, P.K. [Ontario Ministry of the Environment, Toronto, ON (Canada); Hansen, D.A. [Electric Power Research Inst., Palo Alto, CA (United States); Chang, J.S. [State Univ. of New York, Albany, NY (United States). Atmospheric Sciences Research Center

    1991-12-01

    The binational Eulerian Model Evaluation Field Study (EMEFS) consisted of several coordinated data gathering and model evaluation activities. In the EMEFS, data were collected by five air and precipitation monitoring networks between June 1988 and June 1990. Model evaluation is continuing. This interim report summarizes the progress made in the evaluation of the Regional Acid Deposition Model (RADM) and the Acid Deposition and Oxidant Model (ADOM) through the December 1990 completion of a State of Science and Technology report on model evaluation for the National Acid Precipitation Assessment Program (NAPAP). Because various assessment applications of RADM had to be evaluated for NAPAP, the report emphasizes the RADM component of the evaluation. A protocol for the evaluation was developed by the model evaluation team and defined the observed and predicted values to be used and the methods by which the observed and predicted values were to be compared. Scatter plots and time series of predicted and observed values were used to present the comparisons graphically. Difference statistics and correlations were used to quantify model performance. 64 refs., 34 figs., 6 tabs.

  18. Project management plan for the 105-C Reactor interim safe storage project. Revision 1

    International Nuclear Information System (INIS)

    Miller, R.L.

    1997-01-01

    In 1942, the Hanford Site was commissioned by the US Government to produce plutonium. Between 1942 and 1955, eight water-cooled, graphite-moderated reactors were constructed along the Columbia River at the Hanford Site to support the production of plutonium. The reactors were deactivated from 1964 to 1971 and declared surplus. The Surplus Production Reactor Decommissioning Project (BHI 1994b) will decommission these reactors and has selected the 105-C Reactor to be used as a demonstration project for interim safe storage at the present location and final disposition of the entire reactor core in the 200 West Area. This project will result in lower costs, accelerated schedules, reduced worker exposure, and provide direct benefit to the US Department of Energy for decommissioning projects complex wide. This project sets forth plans, organizational responsibilities, control systems, and procedures to manage the execution of the Project Management Plan for the 105-C Reactor Interim Safe Storage Project (Project Management Plan) activities to meet programmatic requirements within authorized funding and approved schedules. The Project Management Plan is organized following the guidelines provided by US Department of Energy Order 4700.1, Project Management System and the Richland Environmental Restoration Project Plan (DOE-RL 1992b)

  19. Yucca Mountain socioeconomic project: An interim report on the State of Nevada socioeconomic studies

    International Nuclear Information System (INIS)

    1989-06-01

    The State of Nevada formally initiated a study of the socioeconomic impacts of a proposed high-level nuclear waste repository at Yucca Mountain in southern Nevada in 1986 after the Nevada site had been chosen as a potential waste disposal site. The State and affected local governments that participated in the development of the study recognized that the effort would need to go well beyond what is traditionally considered adequate for socioeconomic impact assessment because of the unique nature of the repository project. This Interim Report is a report on work in progress and presents findings from the research to date on the potential consequences of a repository for the citizens of Nevada. The research and findings in the Report have been subjected to rigorous peer review as part of the state's effort to insure independent, objective analysis that meets the highest professional standards. The basic research effort will continue through June 1990 and will enable the state to refine and clarify the findings presented in this Interim Report

  20. Transport, handling, and interim storage of intermediate-level transuranic waste at the INEL

    International Nuclear Information System (INIS)

    Metzger, J.C.; Snyder, A.M.

    1977-09-01

    The Idaho National Engineering Laboratory stores transuranic (TRU)-contaminated waste emitting significant amounts of beta-gamma radiation. This material is referred to as intermediate-level TRU waste. The Energy Research and Development Administration requires that this waste be stored retrievably during the interim before a Federal repository becomes operational. Waste form and packaging criteria for the eventual storage of this waste at a Federal repository, i.e., the Waste Isolation Pilot Plant (WIPP), have been tentatively established. The packaging and storage techniques now in use at the Idaho National Engineering Laboratory are compatible with these criteria and also meet the requirement that the waste containers remain in a readily-retrievable, contamination-free condition during the interim storage period. The Intermediate Level Transuranic Storage Facility (ILTSF) provides below-grade storage in steel pipe vaults for intermediate-level TRU waste prior to shipment to the WIPP. Designated waste generating facilities, operated for the Energy Research and Development Administration, use a variety of packaging and transportation methods to deliver this waste to the ILTSF. Transfer of the waste containers to the ILTSF storage vaults is accomplished using handling methods compatible with these waste packaging and transport methods

  1. Power Transfer Potential to the Southeast in Response to a Renewable Portfolio Standard: Interim Report 1

    Energy Technology Data Exchange (ETDEWEB)

    Hadley, Stanton W [ORNL; Key, Thomas S [Electric Power Research Institute (EPRI)

    2009-03-01

    The power transfer potential for bringing renewable energy into the Southeast in response to a renewable portfolio standard (RPS) will depend not only on available transmission capacity but also on electricity supply and demand factors. This interim report examines how the commonly used EIA NEMS and EPRI NESSIE energy equilibrium models are considering such power transfers. Using regional estimates of capacity expansion and demand, a base case for 2008, 2020 and 2030 are compared relative to generation mix, renewable deployments, planned power transfers, and meeting RPS goals. The needed amounts of regional renewable energy to comply with possible RPS levels are compared to inter-regional transmission capacities to establish a baseline available for import into the Southeast and other regions. Gaps in the renewable generation available to meet RPS requirements are calculated. The initial finding is that the physical capability for transferring renewable energy into the SE is only about 10% of what would be required to meet a 20% RPS. Issues that need to be addressed in future tasks with respect to modeling are the current limitations for expanding renewable capacity and generation in one region to meet the demand in another and the details on transmission corridors required to deliver the power.

  2. 75 FR 47312 - Board Meeting; Sunshine Act Meetings

    Science.gov (United States)

    2010-08-05

    ... INTER-AMERICAN FOUNDATION Board Meeting; Sunshine Act Meetings Time and Date: August 9, 2010, 8:30 a.m.-5:30 p.m.. Place: 101 Constitution Avenue, Washington, DC 20001. Status: Closed session as provided in 22 CFR 1004.4(f). Matters to be Considered: Executive Session. Portions to be Closed to the...

  3. Industrial complementarities between interim storage and reversible geological repository - 59237

    International Nuclear Information System (INIS)

    Hoorelbeke, Jean-Michel

    2012-01-01

    The French Act voted in 2006 made the choice of deep geological disposal as the reference option for the long term management of high level (HLW) and intermediate level long-lived waste. The CIGEO repository project aims at avoiding or limiting burden to future generations, which could not be achieved by the extension in time of interim storage. The reversibility as provided by the Act will maintain a liberty of choice for waste management on a duration which is comparable to new storage facility. Interim storage is required to accommodate waste as long as the repository is not available. The commissioning of the repository in 2025 will not suppress needs for interim storage. The paper describes the complementarities between existing and future interim storage facilities and the repository project: repository operational issues and planning, HLW thermal decay, support for the reversibility, etc. It shows opportunities to prepare a global optimization of waste management including the utilization at best of storage capacities and the planning of waste emplacement in the repository in such a way to facilitate operational conditions and to limit cost. Preliminary simulations of storage-disposal scenarios are presented. Thanks to an optimal use of the waste management system, provision can be made for a progressive increase of waste emplacement flow during the first operation phase of the repository. It is then possible to stabilize the industrial activity level of the repository site. An optimal utilization of interim storage can also limit the diversity of waste packages emplaced simultaneously, which facilitates the operation of the repository. 60 years minimum interim storage duration is generally required with respect to HLW thermal output. Extending this interim storage period may reduce the underground footprint of the repository. Regarding reversibility, the capability to manage waste packages potentially retrieved from the repository should be analyzed. The

  4. Permitting plan for the high-level waste interim storage

    International Nuclear Information System (INIS)

    Deffenbaugh, M.L.

    1997-01-01

    This document addresses the environmental permitting requirements for the transportation and interim storage of solidified high-level waste (HLW) produced during Phase 1 of the Hanford Site privatization effort. Solidified HLW consists of canisters containing vitrified HLW (glass) and containers that hold cesium separated during low-level waste pretreatment. The glass canisters and cesium containers will be transported to the Canister Storage Building (CSB) in a U.S. Department of Energy (DOE)-provided transportation cask via diesel-powered tractor trailer. Tri-Party Agreement (TPA) Milestone M-90 establishes a new major milestone, and associated interim milestones and target dates, governing acquisition and/or modification of facilities necessary for: (1) interim storage of Tank Waste Remediation Systems (TWRS) immobilized HLW (IHLW) and other canistered high-level waste forms; and (2) interim storage and disposal of TWRS immobilized low-activity tank waste (ILAW). An environmental requirements checklist and narrative was developed to identify the permitting path forward for the HLW interim storage (HLWIS) project (See Appendix B). This permitting plan will follow the permitting logic developed in that checklist

  5. The IAEA co-ordinated research programme on improvement of measurements, theoretical computations and evaluations of neutron induced helium production cross sections. Status report. Prepared at the final CRP meeting in Sendai, Japan 25-29 September 1995

    International Nuclear Information System (INIS)

    Pashchenko, A.B.

    1996-12-01

    The present report describes the results of the IAEA Co-ordinated Research Programme (CRP) on ''Improvements of Measurements, Theoretical Computation and Evaluations of Neutron Induced Helium Production Cross Sections''. Summarized is the progress achieved under the CRP in the following areas: measurements of α-production cross sections for structural materials, theoretical computations at (nα) cross sections; measurements of activation cross sections; and improvement of experimental methods for (n,α) investigations. The status report gives also short summaries on the work of each laboratory which contributed to the results of the CRP. Attached is the list of program members and participants of CRP meetings. (author). Refs, 2 figs, 1 tab

  6. ITER management advisory committee meeting

    International Nuclear Information System (INIS)

    Yoshikawa, M.

    2001-01-01

    The ITER Management Advisory Committee (MAC) Meeting was held on 23 February in Garching, Germany. The main topics were: the consideration of the report by the Director on the ITER EDA Status, the review of the Work Programme, the review of the Joint Fund, the review of a schedule of ITER meetings, and the arrangements for termination and wind-up of the EDA

  7. ITER management advisory committee meeting

    International Nuclear Information System (INIS)

    Yoshikawa, M.

    2001-01-01

    The ITER Management Advisory Committee (MAC) Meeting was held in Vienna on 16 July 2001. It was the last MAC Meeting and the main topics were consideration of the report by the Director on the ITER EDA status, review of the Work Programme, review of the Joint Fund and arrangements for termination and wind-up of the EDA

  8. Informal meeting on ITER developments

    International Nuclear Information System (INIS)

    Canobbio, E.

    2000-01-01

    The International Fusion Research Council (IFRC), advisory body of the IAEA, organized an informal meeting on the general status and outlook for ITER, held October 9 at Sorrento, Italy, in conjunction with the 18th IAEA Fusion Energy Conference. This article describes the main events at the meeting

  9. A web-based endpoint adjudication system for interim analyses in clinical trials.

    Science.gov (United States)

    Nolen, Tracy L; Dimmick, Bill F; Ostrosky-Zeichner, Luis; Kendrick, Amy S; Sable, Carole; Ngai, Angela; Wallace, Dennis

    2009-02-01

    A data monitoring committee (DMC) is often employed to assess trial progress and review safety data and efficacy endpoints throughout a trail. Interim analyses performed for the DMC should use data that are as complete and verified as possible. Such analyses are complicated when data verification involves subjective study endpoints or requires clinical expertise to determine each subject's status with respect to the study endpoint. Therefore, procedures are needed to obtain adjudicated data for interim analyses in an efficient manner. In the past, methods for handling such data included using locally reported results as surrogate endpoints, adjusting analysis methods for unadjudicated data, or simply performing the adjudication as rapidly as possible. These methods all have inadequacies that make their sole usage suboptimal. For a study of prophylaxis for invasive candidiasis, adjudication of both study eligibility criteria and clinical endpoints prior to two interim analyses was required. Because the study was expected to enroll at a moderate rate and the sponsor required adjudicated endpoints to be used for interim analyses, an efficient process for adjudication was required. We created a web-based endpoint adjudication system (WebEAS) that allows for expedited review by the endpoint adjudication committee (EAC). This system automatically identifies when a subject's data are complete, creates a subject profile from the study data, and assigns EAC reviewers. The reviewers use the WebEAS to review the subject profile and submit their completed review form. The WebEAS then compares the reviews, assigns an additional review as a tiebreaker if needed, and stores the adjudicated data. The study for which this system was originally built was administratively closed after 10 months with only 38 subjects enrolled. The adjudication process was finalized and the WebEAS system activated prior to study closure. Some website accessibility issues presented initially. However

  10. U.S. Renewables Portfolio Standards: 2017 Annual Status Report

    Energy Technology Data Exchange (ETDEWEB)

    Barbose, Galen [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2017-07-25

    Berkeley Lab’s annual status report on U.S. renewables portfolio standards (RPS) provides an overview of key trends associated with U.S. state RPS policies. The report, published in slide-deck form, describes recent legislative revisions, key policy design features, compliance with interim targets, past and projected impacts on renewables development, and compliance costs. The 2017 edition of the report presents historical data through year-end 2016 and projections through 2030. Key trends from this edition of the report include the following: -Evolution of state RPS programs: Significant RPS-related policy revisions since the start of 2016 include increased RPS targets in DC, MD, MI, NY, RI, and OR; requirements for new wind and solar projects and other major reforms to the RPS procurement process in IL; and a new offshore wind carve-out and solar procurement program in MA. -Historical impacts on renewables development: Roughly half of all growth in U.S. renewable electricity (RE) generation and capacity since 2000 is associated with state RPS requirements. Nationally, the role of RPS policies has diminished over time, representing 44% of all U.S. RE capacity additions in 2016. However, within particular regions, RPS policies continue to play a central role in supporting RE growth, constituting 70-90% of 2016 RE capacity additions in the West, Mid-Atlantic, and Northeast. -Future RPS demand and incremental needs: Meeting RPS demand growth will require roughly a 50% increase in U.S. RE generation by 2030, equating to 55 GW of new RE capacity. To meet future RPS demand, total U.S. RE generation will need to reach 13% of electricity sales by 2030 (compared to 10% today), though other drivers will also continue to influence RE growth. -RPS target achievement to-date: States have generally met their interim RPS targets in recent years, with only a few exceptions reflecting unique state-specific policy designs. -REC pricing trends: Prices for renewable energy

  11. Next Generation Melter Optioneering Study - Interim Report

    International Nuclear Information System (INIS)

    Gray, M.F.; Calmus, R.B.; Ramsey, G.; Lomax, J.; Allen, H.

    2010-01-01

    The next generation melter (NOM) development program includes a down selection process to aid in determining the recommended vitrification technology to implement into the WTP at the first melter change-out which is scheduled for 2025. This optioneering study presents a structured value engineering process to establish and assess evaluation criteria that will be incorporated into the down selection process. This process establishes an evaluation framework that will be used progressively throughout the NGM program, and as such this interim report will be updated on a regular basis. The workshop objectives were achieved. In particular: (1) Consensus was reached with stakeholders and technology providers represented at the workshop regarding the need for a decision making process and the application of the D 2 0 process to NGM option evaluation. (2) A framework was established for applying the decision making process to technology development and evaluation between 2010 and 2013. (3) The criteria for the initial evaluation in 2011 were refined and agreed with stakeholders and technology providers. (4) The technology providers have the guidance required to produce data/information to support the next phase of the evaluation process. In some cases it may be necessary to reflect the data/information requirements and overall approach to the evaluation of technology options against specific criteria within updated Statements of Work for 2010-2011. Access to the WTP engineering data has been identified as being very important for option development and evaluation due to the interface issues for the NGM and surrounding plant. WRPS efforts are ongoing to establish precisely data that is required and how to resolve this Issue. It is intended to apply a similarly structured decision making process to the development and evaluation of LAW NGM options.

  12. Cost of implementing AECB interim criteria for the closeout of uranium tailings sites

    International Nuclear Information System (INIS)

    1981-04-01

    The main purpose of this study was to arrive at a gross approximation of the costs to the Canadian uranium mining industry of meeting the proposed closeout criteria established by the Atomic Energy Control Board for tailings deposits. Two options have been investigated: on-land disposal and underlake disposal. Given the budget allocated to the study, the estimates must be understood as approximations. Overall cost figures for the Canadian uranium mining industry are linear extensions from a hypothetical base case. The results of a conference held in Ottawa on February 25 and 26 to discuss the proposed AECB interim criteria for the closeout of uranium tailings sites are also included. Representatives from mining firms, provincial regulatory authorities, universities and the Atomic Energy Control board attended the conference

  13. Engineering report for interim solids removal modifications of the Steam Plant Wastewater Treatment Facility

    International Nuclear Information System (INIS)

    1995-04-01

    The Steam Plant Wastewater Treatment Facility (SPWTF) treats wastewater from the Y-12 Plant coal yard, steam plant, and water demineralizer facility. The facility is required to comply with National Pollutant Discharge Elimination System (NPDES) standards prior to discharge to East Fork Poplar Creek (EFPC). The existing facility was designed to meet Best Available Technology (BAT) standards and has been in operation since 1988. The SPWTF has had intermittent violations of the NPDES permit primarily due to difficulties in complying with the limit for total iron of 1.0 ppM. A FY-1997 Line Item project, SPWTF Upgrades, is planned to improve the capabilities of the SPWTF to eliminate non-compliances with the permit limits. The intent of the Interim Solids Removal Modification project is to improve the SPWTF effluent quality and to provide pilot treatment data to assist in the design and implementation of the SPWTF Upgrades Line Item Project

  14. Safety report for Central Interim Storage facility for radioactive waste from small producers

    International Nuclear Information System (INIS)

    Zeleznik, N.; Mele, I.

    2004-01-01

    In 1999 the Agency for Radwaste Management took over the management of the Central Interim Storage (CIS) in Brinje, intended only for radioactive waste from industrial, medical and research applications. With the transfer of the responsibilities for the storage operation, ARAO, the new operator of the facility, received also the request from the Slovenian Nuclear Safety Administration for refurbishment and reconstruction of the storage and for preparation of the safety report for the storage with the operational conditions and limitations. In order to fulfill these requirements ARAO first thoroughly reviewed the existing documentation on the facility, the facility itself and the stored inventory. Based on the findings of this review ARAO prepared several basic documents for improvement of the current conditions in the storage facility. In October 2000 the Plan for refurbishment and modernization of the CIS was prepared, providing an integral approach towards remediation and refurbishment of the facility, optimization of the inventory arrangement and modernization of the storage and storing utilization. In October 2001 project documentation for renewal of electric installations, water supply and sewage system, ventilation system, the improvements of the fire protection and remediation of minor defects discovered in building were completed according to the Act on Construction. In July 2003 the safety report was prepared, based on the facility status after the completion of the reconstruction works. It takes into account all improvements and changes introduced by the refurbishment and reconstruction of the facility according to project documentation. Besides the basic characteristics of the location and its surrounding, it also gives the technical description of the facility together with proposed solutions for the renewal of electric installations, renovation of water supply and sewage system, refurbishment of the ventilation system, the improvement of fire

  15. Interim process report for the safety assessment SR-Can

    International Nuclear Information System (INIS)

    Sellin, Patrick

    2004-08-01

    This report is a documentation of buffer processes identified as relevant to the long-term safety of a KBS-3 repository. The report is part of the interim reporting of the safety assessment SR-Can, see further the Interim main report. The final SR-Can reporting will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of this report is to document the scientific knowledge of the processes to a level required for an adequate treatment in the safety assessment. The documentation is thus from a scientific point of not exhaustive since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of an assessment. The purpose is further to determine the handling of each process in the safety assessment and to demonstrate how uncertainties are taken care of, given the suggested handling. The process documentation in the SR 97 version of the Process report is a starting point for this SR-Can interim version. As further described in the Interim main report, the list of relevant processes has been reviewed and slightly extended by comparison to other databases. Furthermore, the backfill has been included as a system part of its own, rather than being described together with the buffer as in SR 97. Apart from giving an interim account of the documentation and handling of buffer processes in SR-Can, this report is meant to serve as a template for the forthcoming documentation of processes occurring in other parts of the repository system. A complete list of processes can be found in the Interim FEP report for the safety assessment SR-Can. All material presented in this document is preliminary in nature and will possibly be updated as the SR-Can project progresses

  16. Single-shell tank interim stabilization project plan

    Energy Technology Data Exchange (ETDEWEB)

    Ross, W.E.

    1998-03-27

    Solid and liquid radioactive waste continues to be stored in 149 single-shell tanks at the Hanford Site. To date, 119 tanks have had most of the pumpable liquid removed by interim stabilization. Thirty tanks remain to be stabilized. One of these tanks (C-106) will be stabilized by retrieval of the tank contents. The remaining 29 tanks will be interim stabilized by saltwell pumping. In the summer of 1997, the US Department of Energy (DOE) placed a moratorium on the startup of additional saltwell pumping systems because of funding constraints and proposed modifications to the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) milestones to the Washington State Department of Ecology (Ecology). In a letter dated February 10, 1998, Final Determination Pursuant to Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) in the Matter of the Disapproval of the DOE`s Change Control Form M-41-97-01 (Fitzsimmons 1998), Ecology disapproved the DOE Change Control Form M-41-97-01. In response, Fluor Daniel Hanford, Inc. (FDH) directed Lockheed Martin Hanford Corporation (LNMC) to initiate development of a project plan in a letter dated February 25, 1998, Direction for Development of an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan in Support of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). In a letter dated March 2, 1998, Request for an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan, the DOE reaffirmed the need for an aggressive SST interim stabilization completion project plan to support a finalized Tri-Party Agreement Milestone M-41 recovery plan. This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities

  17. Single-shell tank interim stabilization project plan

    International Nuclear Information System (INIS)

    Ross, W.E.

    1998-01-01

    Solid and liquid radioactive waste continues to be stored in 149 single-shell tanks at the Hanford Site. To date, 119 tanks have had most of the pumpable liquid removed by interim stabilization. Thirty tanks remain to be stabilized. One of these tanks (C-106) will be stabilized by retrieval of the tank contents. The remaining 29 tanks will be interim stabilized by saltwell pumping. In the summer of 1997, the US Department of Energy (DOE) placed a moratorium on the startup of additional saltwell pumping systems because of funding constraints and proposed modifications to the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) milestones to the Washington State Department of Ecology (Ecology). In a letter dated February 10, 1998, Final Determination Pursuant to Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) in the Matter of the Disapproval of the DOE's Change Control Form M-41-97-01 (Fitzsimmons 1998), Ecology disapproved the DOE Change Control Form M-41-97-01. In response, Fluor Daniel Hanford, Inc. (FDH) directed Lockheed Martin Hanford Corporation (LNMC) to initiate development of a project plan in a letter dated February 25, 1998, Direction for Development of an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan in Support of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement). In a letter dated March 2, 1998, Request for an Aggressive Single-Shell Tank (SST) Interim Stabilization Completion Project Plan, the DOE reaffirmed the need for an aggressive SST interim stabilization completion project plan to support a finalized Tri-Party Agreement Milestone M-41 recovery plan. This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities

  18. Interim process report for the safety assessment SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Sellin, Patrick (ed.)

    2004-08-01

    This report is a documentation of buffer processes identified as relevant to the long-term safety of a KBS-3 repository. The report is part of the interim reporting of the safety assessment SR-Can, see further the Interim main report. The final SR-Can reporting will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of this report is to document the scientific knowledge of the processes to a level required for an adequate treatment in the safety assessment. The documentation is thus from a scientific point of not exhaustive since such a treatment is neither necessary for the purposes of the safety assessment nor possible within the scope of an assessment. The purpose is further to determine the handling of each process in the safety assessment and to demonstrate how uncertainties are taken care of, given the suggested handling. The process documentation in the SR 97 version of the Process report is a starting point for this SR-Can interim version. As further described in the Interim main report, the list of relevant processes has been reviewed and slightly extended by comparison to other databases. Furthermore, the backfill has been included as a system part of its own, rather than being described together with the buffer as in SR 97. Apart from giving an interim account of the documentation and handling of buffer processes in SR-Can, this report is meant to serve as a template for the forthcoming documentation of processes occurring in other parts of the repository system. A complete list of processes can be found in the Interim FEP report for the safety assessment SR-Can. All material presented in this document is preliminary in nature and will possibly be updated as the SR-Can project progresses.

  19. 10 CFR 431.401 - Petitions for waiver, and applications for interim waiver, of test procedure.

    Science.gov (United States)

    2010-01-01

    ... Renewable Energy, U.S. Department of Energy. Each Application for Interim Waiver must reference the Petition... Renewable Energy. (e) Provisions specific to interim waivers—(1) Disposition of application. If... 10 Energy 3 2010-01-01 2010-01-01 false Petitions for waiver, and applications for interim waiver...

  20. 78 FR 67442 - Congestion Mitigation and Air Quality Improvement Program Interim Guidance

    Science.gov (United States)

    2013-11-12

    ...] Congestion Mitigation and Air Quality Improvement Program Interim Guidance AGENCY: Federal Highway... Comment. SUMMARY: The FHWA is issuing Interim Guidance on the Congestion Mitigation and Air Quality.../environment/air_quality/cmaq/policy_and_guidance/2008_guidance/ guidance/. DATES: This Interim Guidance is...

  1. Single-shell tank interim stabilization risk analysis

    International Nuclear Information System (INIS)

    Basche, A.D.

    1998-01-01

    The purpose of the Single-Shell Tank (SST) Interim Stabilization Risk Analysis is to provide a cost and schedule risk analysis of HNF-2358, Rev. 1, Single-Shell Tank Interim Stabilization Project Plan (Project Plan) (Ross et al. 1998). The analysis compares the required cost profile by fiscal year (Section 4.2) and revised schedule completion date (Section 4.5) to the Project Plan. The analysis also evaluates the executability of the Project Plan and recommends a path forward for risk mitigation

  2. Interim safety basis for fuel supply shutdown facility

    International Nuclear Information System (INIS)

    Brehm, J.R.; Deobald, T.L.; Benecke, M.W.; Remaize, J.A.

    1995-01-01

    This ISB in conjunction with the new TSRs, will provide the required basis for interim operation or restrictions on interim operations and administrative controls for the Facility until a SAR is prepared in accordance with the new requirements. It is concluded that the risk associated with the current operational mode of the Facility, uranium closure, clean up, and transition activities required for permanent closure, are within Risk Acceptance Guidelines. The Facility is classified as a Moderate Hazard Facility because of the potential for an unmitigated fire associated with the uranium storage buildings

  3. Second meeting of the ITER Preparatory Committee

    International Nuclear Information System (INIS)

    Drew, M.

    2003-01-01

    The committee charged to oversee the ITER ITA (ITER transitional arrangements) the ITER preparatory committee, held its second meeting on 24 September at the JET facilities at Culham, UK. Dr. Umberto Finzi of the European Commission was chairman. This meeting was also the first since the succession by Dr. Yasuo Shimomura to Dr. Robert Aymar as Interim Project Leader (IPL). Welcoming Dr. Shimomura in his new capacity, the Committee paid tribute to the outstanding contributions of his predecessor to the definition, design and promotion of ITER, and expressed the gratitude of all Participants to Dr. Aymar and its best wishes for future success in his new appointment.The technical activities of the ITA were the main focus of the Committee's discussions. The Committee took note of the IPL's Status Report on ITA Technical Activities and endorsed the IPL's proposals for the top level structure of the International Team, including the designation of Dr. Pietro Barabaschi as Deputy to the IPL. The Committee took note of the IPL's proposals on Participants' contributions to the ITA and of the Participants' stated intentions and expectations in this regard. Several Delegations pointed out that access to necessary resources would depend strongly on progress made towards the Agreement. All Participants were invited, in the shared interests of the project, to respond constructively to the specific technical areas where the IPL reported a lack of resources. Following a presentation from the IT on Project Management Tools, the Committee expressed support, in general, for the proposed strategy designed to provide the current team with the CAD and Data Management elements necessary to prepare for an efficient start of ITER construction, and asked the IT Leader to report on an estimate and time profile of expenditure during the period to mid-2004. The Committee supported the proposals to re-establish the ITER Test Blanket Working. The Committee agreed that the phasing of planned

  4. Operational Implementation of the MARSSIM Process at the Wayne Interim Storage Site

    International Nuclear Information System (INIS)

    Hays, D. C. Jr.; Trujillo, P. A. IV.; Zoller, S. G.

    2002-01-01

    This paper describes the methodologies behind the operational implementation of the Multi Agency Radiation Site Survey and Investigation Manual (MARSSIM) process at the Wayne Interim Storage Site (WISS). The United States Army Corps of Engineers (USACE) and Environmental Chemical Corporation (ECC) have implemented the MARSSIM process using various surveys producing raw data. The final remedial status of a survey unit is derived through data reduction, while maintaining a high degree of efficiency in the construction aspects of the remedial action. Data reduction of field measurements is accomplished by merging the data outputs of a Digital Global Positioning System, an exposure rate meter, and laboratory analyses to produce maps which present exposure rates, elevations, survey unit boundaries, direct measurement locations, and sampling locations on a single map. The map serves as a data-posting plot and allows the project team to easily judge the survey unit's remedial status. The operational implementation of the MARSSIM process has been successful in determining the eligibility of survey units for final status surveys at the WISS and also in demonstrating final status radiological and chemical conditions while maintaining an efficient remedial action effort

  5. A quality assurance programme for radiation therapy dosimetry: Report of a consultants' meeting to review the status and to plant the development

    International Nuclear Information System (INIS)

    Izewska, J.; Andreo, P.

    1996-01-01

    Four national External Audit Groups (EAG) in charge of operating quality audits for radiotherapy dosimetry have been created through a Co-ordinated Research Programme ''Development of a Quality Assurance Programme for Radiation Therapy Dosimetry in Developing Countries'' (E2-40-07). The present status of the development of the measuring systems and measuring procedures for the EAGs has been compared to the methodology established by Quality Audit Networks operating at present in Europe. To harmonize different EAG procedures, a document entitled ''Guidelines to prepare a Quality Manual for External Audit Groups on Dosimetry in Radiotherapy '' has been outlined and a first draft prepared. The ''Guidelines...'' covers quality policy, quality systems and quality structures including process control following the recommendations of ISO 9000 series and ISO/IEC guide No. 25. When completed, this document can be used as a guide on how to prepare the quality manual for national EAGs in developing countries. Due to increased interest in the project three new participants have been admitted. (author)

  6. Interim dry cask storage of irradiated Fast Flux Test Facility fuel

    International Nuclear Information System (INIS)

    Scott, P.L.

    1994-09-01

    The Fast Flux Test Facility (FFTF), located at the US Department of Energy's (DOE'S) Hanford Site, is the largest, most modern, liquid metal-cooled test reactor in the world. This paper will give an overview of the FFTF Spent Fuel Off load project. Major discussion areas will address the status of the fuel off load project, including an overview of the fuel off load system and detailed discussion on the individual components that make up the dry cask storage portion of this system. These components consist of the Interim Storage Cask (ISC) and Core Component Container (CCC). This paper will also discuss the challenges that have been addressed in the evolution of this project

  7. Diesel Emission Control -- Sulfur Effects (DECSE) Program; Phase I Interim Data Report No. 1

    Energy Technology Data Exchange (ETDEWEB)

    DOE; ORNL; NREL; EMA; MECA

    1999-08-15

    The Diesel Emission Control-Sulfur Effects (DECSE) is a joint government/industry program to determine the impact of diesel fuel sulfur levels on emission control systems whose use could lower emissions of nitrogen oxides (NO{sub x}) and particulate matter (PM) from on-highway trucks in the 2002--2004 model years. Phase 1 of the program was developed with the following objectives in mind: (1) evaluate the effects of varying the level of sulfur content in the fuel on the emission reduction performance of four emission control technologies; and (2) measure and compare the effects of up to 250 hours of aging on selected devices for multiple levels of fuel sulfur content. This interim data report summarizes results as of August, 1999, on the status of the test programs being conducted on three technologies: lean-NO{sub x} catalysts, diesel particulate filters and diesel oxidation catalysts.

  8. Interim radiological safety standards and evaluation procedures for subseabed high-level waste disposal

    International Nuclear Information System (INIS)

    Klett, R.D.

    1997-06-01

    The Seabed Disposal Project (SDP) was evaluating the technical feasibility of high-level nuclear waste disposal in deep ocean sediments. Working standards were needed for risk assessments, evaluation of alternative designs, sensitivity studies, and conceptual design guidelines. This report completes a three part program to develop radiological standards for the feasibility phase of the SDP. The characteristics of subseabed disposal and how they affect the selection of standards are discussed. General radiological protection standards are reviewed, along with some new methods, and a systematic approach to developing standards is presented. The selected interim radiological standards for the SDP and the reasons for their selection are given. These standards have no legal or regulatory status and will be replaced or modified by regulatory agencies if subseabed disposal is implemented. 56 refs., 29 figs., 15 tabs

  9. Subsurface Interim Measures/Interim Remedial Action Plan/ Environmental Assessment and Decision Document, Operable Unit No. 2

    International Nuclear Information System (INIS)

    1992-01-01

    The subject Interim Measures/Interim Remedial Action plan/Environmental Assessment (IM/IRAP/EA) addresses residual free-phase volatile organic compound (VOC) contamination suspected in the subsurface within an area identified as Operable Unit No. 2 (OU2). This IM/IRAP/EA also addresses radionuclide contamination beneath the 903 Pad at OU2. Although subsurface VOC and radionuclide contamination on represent a source of OU2 ground-water contamination, they pose no immediate threat to public health or the environment. This volume contains five appendices

  10. A critique of the EC's expert (draft) reports on the status of alternatives for cosmetics testing to meet the 2013 deadline.

    Science.gov (United States)

    Taylor, Katy; Casalegno, Carlotta; Stengel, Wolfgang

    2011-01-01

    The 7th Amendment to the EU's Cosmetic Directive (now recast as Regulation 1223/2009) bans the testing of cosmetic ingredients and products on animals, effective 2009. An extension until 2013 was granted, for marketing purposes only, for three endpoints: repeated dose, toxicokinetics, and reproductive toxicity. If the European Commission determines that alternatives for these endpoints are not likely to be available, it can propose a further extension. To this end, the Commission has instructed experts to produce reports on the status of alternatives for the 2013 deadline. We criticized the draft reports on a number of issues. First, the experts fell into the "high fidelity fallacy trap," i.e. asserting that full replication of the in vivo response, as opposed to high predictivity, is required before an animal test can be considered useful for regulatory purposes. Second, the experts' reports were incomplete, omitting various methods and failing to provide data on the validity, reliability, and applicability of all the methods discussed, regardless of whether the methods were in vivo, in vitro, or in silico. In this paper we provide a summary of our criticisms and provide some of the missing data in an alternative proposal for replacement of animal tests by 2013. It is our belief that use of the Threshold of Toxicological Concern (TTC) will be a useful method to mitigate much animal testing. Alternative approaches for carcinogenicity and skin sensitization could be considered sufficient in the very near future, even though these tests are not listed under the 2013 extension. For repeated dose, toxicokinetics, and reproductive toxicity a combination of in vitro methods may be able to provide appropriate protection for consumers, especially when viewed in the context of the poor predictivity of the animal models they replace. We hope the revised report will incorporate these comments, since a more thorough and positive review is required if the elimination of animal

  11. Status of legislation

    International Nuclear Information System (INIS)

    Warner, C.

    1982-01-01

    The status of the House legislation, the major differences between the House and Senate legislation and a preview of what is likely to take place during the lame duck session in December are presented. The House legislation provides: long-term program leading toward permanent disposal of nuclear waste; an interim program for storage and for expansion of storage space for spent fuel; provides an R and D component through what is called a test and evaluation facility; an alternative long-term storage program based on a proposal to be completed by the Department of Energy on what's called Monitored Retrievable Storage; full upfront financing of the program through user fees based on contracts between the government and the users of the nuclear waste disposal services

  12. 78 FR 77736 - Sunshine Act Meetings

    Science.gov (United States)

    2013-12-24

    ..., 2013, January 6, 13, 20, 27, 2014. PLACE: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of December 23, 2013 There are no meetings scheduled... Casks (Public Meeting); (Contact: Kevin Witt, 301-415-2145) This meeting will be webcast live at the Web...

  13. 77 FR 10575 - Sunshine Act Meetings

    Science.gov (United States)

    2012-02-22

    ...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of... meeting will be webcast live at the Web address--www.nrc.gov. 9 a.m.--Briefing on Fort Calhoun (Public Meeting) (Contact: Jeff Clark, 817-860-8147). This meeting will be webcast live at the Web address--www...

  14. 78 FR 72931 - Sunshine Act Meeting Notice

    Science.gov (United States)

    2013-12-04

    ... 2, 9, 16, 23, 30, 2013, January 6, 2014. PLACE: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of December 2, 2013 There are no meetings scheduled for... Dry Casks (Public Meeting) (Contact: Kevin Witt, 301-415-2145). This meeting will be webcast live at...

  15. 77 FR 74883 - Sunshine Act Meeting Notice

    Science.gov (United States)

    2012-12-18

    .... PLACE: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of December 17, 2012 There are no meetings scheduled for the week of December 17, 2012. Week... Calhoun (Public Meeting) (Contact: Michael Hay, 817-200-1527) This meeting will be webcast live at the Web...

  16. 77 FR 33252 - Sunshine Act Meeting

    Science.gov (United States)

    2012-06-05

    .... PLACE: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and closed. Week of June 4, 2012 Thursday, June 7, 2012 9:25 a.m. Affirmation Session (Public Meeting... meeting will be webcast live at the Web address--www.nrc.gov. 9:30 a.m. Meeting with the Advisory...

  17. 76 FR 26775 - Sunshine Act Meeting Notice

    Science.gov (United States)

    2011-05-09

    ...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of...-415-3951). This meeting will be webcast live at the Web address-- http://www.nrc.gov . Week of May 16...) (Public Meeting) (Contact: Rani Franovich, 301-415-1868). This meeting will be webcast live at the Web...

  18. 78 FR 16893 - Sunshine Act Meetings

    Science.gov (United States)

    2013-03-19

    ...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. [[Page... Flannery, 301-415-0223) This meeting will be webcast live at the Web address--www.nrc.gov. Week of April 8... Accident (Public Meeting) (Contact: William D. Reckley, 301- 415-7490) This meeting will be webcast live at...

  19. 78 FR 39781 - Sunshine Act Meeting

    Science.gov (United States)

    2013-07-02

    ... LEGAL SERVICES CORPORATION Sunshine Act Meeting Notice Date and Time: The Legal Services... disrupting the meeting, please refrain from placing the call on hold if doing so will trigger recorded music or other sound. From time to time, the Chair may solicit comments from the public. Status of Meeting...

  20. 78 FR 33114 - Sunshine Act Meetings

    Science.gov (United States)

    2013-06-03

    ... LEGAL SERVICES CORPORATION Sunshine Act Meetings ACTION: Notice. Date And Time: The Legal Services... meeting, please refrain from placing the call on hold if doing so will trigger recorded music or other sound. From time to time, the Chair may solicit comments from the public. Status Of Meeting: Open...

  1. New York State interim waste management cost evaluation

    International Nuclear Information System (INIS)

    Ma, M.S.; Watts, R.J.; Jorgensen, J.R.; Rochester Gas and Electric Corp., NY)

    1985-01-01

    The purpose of this study is to investigate and quantify the comparative costs associated with including or excluding Class A utility wastes at a centralized interim waste management facility in New York State. The objective of the study is to assess the unit costs and total statewide costs associated with two distinct scenarios: (1) the case where non-utility Class A LLRW is received, incinerated and stored at the centralized interim facility, and utility Class A wastes are held without incineration at respective nuclear power plant interim onsite facilities without incineration; and (2) the alternative case where both utility and non-utility Class A wastes are accepted, incinerated and stored at the centralized facility. Unit costs to waste generators are estimated for each of the two cases described. This is followed by an estimation of the statewide cost impact to the public. The cost impact represents the cost differential resulting from the exclusion of utility Class A waste from the centralized NYS interim waste management facility. The principal factors comprising the cost differential include (1) higher unit disposal fees charged to non-utility waste generators, which are passed along in the costs of products and services; and (2) costs to utilities due to construction of additional onsite storage capacity, which in turn are charged to electric rate payers

  2. Options for the interim storage of spent fuel

    International Nuclear Information System (INIS)

    Kromar, M.; Kurincic, B.

    1995-01-01

    Different concepts for the interim storage of spent fuel arising from operation of a NPP are discussed. We considered at reactor as well as away from reactor storage options. Included are enhancements of existing storage capabilities and construction of a new wet or dry storage facility. (author)

  3. Fuel supply shutdown facility interim operational safety requirements

    International Nuclear Information System (INIS)

    Besser, R.L.; Brehm, J.R.; Benecke, M.W.; Remaize, J.A.

    1995-01-01

    These Interim Operational Safety Requirements (IOSR) for the Fuel Supply Shutdown (FSS) facility define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls to ensure safe operation. The IOSRs apply to the fuel material storage buildings in various modes (operation, storage, surveillance)

  4. 17 CFR 210.8-03 - Interim financial statements.

    Science.gov (United States)

    2010-04-01

    ... 17 Commodity and Securities Exchanges 2 2010-04-01 2010-04-01 false Interim financial statements... AND CONTENT OF AND REQUIREMENTS FOR FINANCIAL STATEMENTS, SECURITIES ACT OF 1933, SECURITIES EXCHANGE... ADVISERS ACT OF 1940, AND ENERGY POLICY AND CONSERVATION ACT OF 1975 Article 8 Financial Statements of...

  5. ASPECTS CONCERNING INTERIM FINANCIAL REPORTING IN ROMANIA: STANDARDS AND REGULATIONS

    Directory of Open Access Journals (Sweden)

    Aristita Rotila

    2014-12-01

    Full Text Available The mechanisms employed for the communication of accounting information that is necessary for users in their economic decision-making process consist of the financial statements of an entity. All legal entities, no matter the domain of their activity, have the obligation to draw up annual financial statements for every completed financial year. For certain categories of entities, reporting obligations are also required for periods other than the annual reporting, throughout the financial year. It is the case of interim financial reporting. At the level of the international accounting framework, the aspects related to interim financial reporting are the subject of a separate standard, namely, IAS 34 Interim Financial Reporting. In Romania, the current system of accounting regulations concerning the annual financial statements comprises accounting regulations that comply with the European directives and which apply to the various categories of entities, on the one hand and, on the other, accounting regulations in line with the IFRS, which are applicable to other classes of entities from certain activity sectors. The accounting regulations that apply to each category refer to, among other things, the contents and the format of financial statements that have to be presented. Analysing the system of norms and regulations, this article identifies the requirements concerning interim financial reporting in Romania, with reference to the different types of entities.

  6. 39 CFR 211.4 - Interim personnel regulations.

    Science.gov (United States)

    2010-07-01

    ... 39 Postal Service 1 2010-07-01 2010-07-01 false Interim personnel regulations. 211.4 Section 211.4... under the Postal Reorganization Act. (b) Continuation of Personnel Provisions of Former title 39, U.S.C... collective bargaining agreement under the Postal Reorganization Act, all provisions of former title 39, U.S.C...

  7. Students' interim literacies as a dynamic resource for teaching and ...

    African Journals Online (AJOL)

    This article explores the notion of 'interim literacies'by drawing on data from a research project which used linguistic and intertextual analysis of first year student writing in economics to investigate the intersection of academic discourse and student voice. This research has provided a rich set of data to illustrate the ways in ...

  8. 46 CFR 308.303 - Amounts insured under interim binder.

    Science.gov (United States)

    2010-10-01

    ... 308.303 Shipping MARITIME ADMINISTRATION, DEPARTMENT OF TRANSPORTATION EMERGENCY OPERATIONS WAR RISK INSURANCE Second Seamen's War Risk Insurance § 308.303 Amounts insured under interim binder. The amounts insured are the amounts specified in the Second Seamen's War Risk Policy (1955) or as modified by shipping...

  9. System Specification for Immobilized High-Level Waste Interim Storage

    International Nuclear Information System (INIS)

    CALMUS, R.B.

    2000-01-01

    This specification establishes the system-level functional, performance, design, interface, and test requirements for Phase 1 of the IHLW Interim Storage System, located at the Hanford Site in Washington State. The IHLW canisters will be produced at the Hanford Site by a Selected DOE contractor. Subsequent to storage the canisters will be shipped to a federal geologic repository

  10. Guidelines for interim storage of low level waste

    International Nuclear Information System (INIS)

    Hornibrook, C.; Castagnacci, A.; Clymer, G.; Kelly, J.; Naughton, M.; Saunders, P.; Stoner, P.; Walker, N.; Cazzolli, R.; Dettenmeier, R.; Loucks, L.; Rigsby, M.; Spall, M.; Strum, M.

    1992-12-01

    This report presents an overview of on-site storage of Low Level Waste while providing guidelines for using the complete Interim On-Site Storage of Low Level Waste report series. Overall, this report provides a methodology for planning and implementing on-site storage

  11. Single-Shell Tank (SST) Interim Stabilization Project Plan

    International Nuclear Information System (INIS)

    VLADIMIROFF, D.T.; BOYLES, V.C.

    2000-01-01

    This project plan establishes the management framework for the conduct of the CHG Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organization structure, roles, responsibilities, and interfaces; and operational methods. This plan serves as the project executional baseline

  12. Single-shell tank interim stabilization project plan

    Energy Technology Data Exchange (ETDEWEB)

    Ross, W.E.

    1998-05-11

    This project plan establishes the management framework for conduct of the TWRS Single-Shell Tank Interim Stabilization completion program. Specifically, this plan defines the mission needs and requirements; technical objectives and approach; organizational structure, roles, responsibilities, and interfaces; and operational methods. This plan serves as the project executional baseline.

  13. 78 FR 70244 - Electronic Interim Assistance Reimbursement Program

    Science.gov (United States)

    2013-11-25

    ..., Social Security Online, at http://www.socialsecurity.gov . SUPPLEMENTARY INFORMATION: Background To be... SOCIAL SECURITY ADMINISTRATION 20 CFR Part 416 [Docket No. SSA-2011-0104] RIN 0960-AH45 Electronic Interim Assistance Reimbursement Program AGENCY: Social Security Administration. ACTION: Notice of...

  14. 14 CFR 136.41 - Interim operating authority.

    Science.gov (United States)

    2010-01-01

    ... AND NATIONAL PARKS AIR TOUR MANAGEMENT National Parks Air Tour Management § 136.41 Interim operating... terminate 180 days after the date on which an air tour management plan is established for the park and tribal lands; (6) Shall promote protection of national park resources, visitor experiences, and tribal...

  15. Effectiveness Monitoring Report, MWMF Tritium Phytoremediation Interim Measures.

    Energy Technology Data Exchange (ETDEWEB)

    Hitchcock, Dan; Blake, John, I.

    2003-02-10

    This report describes and presents the results of monitoring activities during irrigation operations for the calendar year 2001 of the MWMF Interim Measures Tritium Phytoremediation Project. The purpose of this effectiveness monitoring report is to provide the information on instrument performance, analysis of CY2001 measurements, and critical relationships needed to manage irrigation operations, estimate efficiency and validate the water and tritium balance model.

  16. Public School Finance Problems in Texas. An Interim Report.

    Science.gov (United States)

    Texas Research League, Austin.

    The U.S. District Court ruling in Rodriguez vs San Antonio Independent School District, which struck down Texas' school finance system as inequitable and unconstitutional, provided the impetus for publishing this interim report. The report documents the growing cost of State-supported public school programs--the primary concern prior to the…

  17. Meeting Disorders.

    Science.gov (United States)

    Yager, Joel; Katzman, Jeffrey W

    2017-12-01

    Although meetings are central to organizational work, considerable time devoted to meetings in Academic Health Centers appears to be unproductively spent. The primary purposes of this article are to delineate and describe Meeting Disorders, pathological processes resulting in these inefficient and ineffective scenarios, and Meeting Fatigue Disorder (MFD), a clinical syndrome. The paper also offers preliminary approaches to remedies. The authors integrate observations made during tens of thousands of hours in administrative meetings in academic medical settings with information in the literature regarding the nature, causes and potential interventions for dysfunctional groups and meetings. Meeting Disorders, resulting from distinct pathologies of leadership and organization, constitute prevalent subgroups of the bureaucrapathologies, pathological conditions caused by dysfunctional bureaucratic processes that generate excesses of wasted time, effort, and other resources. These disorders also generate frustration and demoralization among participants, contributing to professional burnout. Meeting Fatigue Disorder (MFD) is a subjective condition that develops in individuals who overdose on these experiences and may reflect one manifestation of burnout. Meeting disorders and Meeting Fatigue Disorder occur commonly in bureaucratic life. Resources and potential remedies are available to help ameliorate their more deleterious effects.

  18. Interim report on nuclear power in Ontario

    International Nuclear Information System (INIS)

    1978-01-01

    An exhaustive report is presented on the implications of nuclear electric generation for Ontario's energy future. Such aspects as electrical demand and power planning, the CANDU fuel cycle, the nuclear debate, health, environmental and safety concerns, economics, social impacts and the status of the nuclear industry, uranium resources, ethical and political issues, nuclear weapons proliferation and plant security, and the regulation of nuclear power are dealt with in detail. (E.C.B.)

  19. STAFF MEETING

    CERN Document Server

    2003-01-01

    I should like to invite all members of the CERN Personnel to a meeting on Wednesday 25th June 2003 at 11.00 hrs - Auditorium, bldg. 500 to give a report on the outcome of the June Meetings of Council and its Committees. Closed-circuit transmission of the meeting will be available in the AB Auditorium (Prévessin), the AB Auditorium (Meyrin - bldg. 6), the IT Auditorium (bldg. 31) and the AT Auditorium (bldg. 30). Luciano Maiani Director General

  20. Subsurface Interim Measures/Interim Remedial Action Plan/Environmental Assessment and Decision Document, Operable Unit No. 2

    International Nuclear Information System (INIS)

    1992-01-01

    The subject Interim Measures/Interim Remedial Action plan/Environmental Assessment (IM/IRAP/EA) addresses residual free-phase volatile organic compound (VOC) contamination suspected in the subsurface within an area identified as Operable Unit No. 2 (OU2). This IM/IRAP/EA also addresses radionuclide contamination beneath the 903 Pad at OU2. Although subsurface VOC and radionuclide contamination on represent a source of OU2 ground-water contamination, they pose no immediate threat to public health or the environment. This IM/IRAP/EA identifies and evaluates interim remedial actions for removal of residual free-phase VOC contamination from three different subsurface environments at OU2. The term ''residual'' refers to the non-aqueous phase contamination remaining in the soil matrix (by capillary force) subsequent to the passage of non-aqueous or free-phase liquid through the subsurface. In addition to the proposed actions, this IM/IRAP/EA presents an assessment of the No Action Alternative. This document also considers an interim remedial action for the removal of radionuclides from beneath the 903 Pad

  1. 76 FR 21043 - Notice of Public Meeting: Technical Aspects of Mandatory Deposit of Published Electronic Works...

    Science.gov (United States)

    2011-04-14

    ... mandatory deposit requirements of the copyright law. The objective is to identify file submission, packaging... mandatory deposit provisions of the copyright law. Under the interim regulation, certain works available... LIBRARY OF CONGRESS Copyright Office [Docket No. 2011-3] Notice of Public Meeting: Technical...

  2. AES Water Architecture Study Interim Results

    Science.gov (United States)

    Sarguisingh, Miriam J.

    2012-01-01

    The mission of the Advanced Exploration System (AES) Water Recovery Project (WRP) is to develop advanced water recovery systems in order to enable NASA human exploration missions beyond low earth orbit (LEO). The primary objective of the AES WRP is to develop water recovery technologies critical to near term missions beyond LEO. The secondary objective is to continue to advance mid-readiness level technologies to support future NASA missions. An effort is being undertaken to establish the architecture for the AES Water Recovery System (WRS) that meets both near and long term objectives. The resultant architecture will be used to guide future technical planning, establish a baseline development roadmap for technology infusion, and establish baseline assumptions for integrated ground and on-orbit environmental control and life support systems (ECLSS) definition. This study is being performed in three phases. Phase I of this study established the scope of the study through definition of the mission requirements and constraints, as well as indentifying all possible WRS configurations that meet the mission requirements. Phase II of this study focused on the near term space exploration objectives by establishing an ISS-derived reference schematic for long-duration (>180 day) in-space habitation. Phase III will focus on the long term space exploration objectives, trading the viable WRS configurations identified in Phase I to identify the ideal exploration WRS. The results of Phases I and II are discussed in this paper.

  3. Logic Meeting

    CERN Document Server

    Tugué, Tosiyuki; Slaman, Theodore

    1989-01-01

    These proceedings include the papers presented at the logic meeting held at the Research Institute for Mathematical Sciences, Kyoto University, in the summer of 1987. The meeting mainly covered the current research in various areas of mathematical logic and its applications in Japan. Several lectures were also presented by logicians from other countries, who visited Japan in the summer of 1987.

  4. 78 FR 20359 - Sunshine Act Meetings; National Science Board

    Science.gov (United States)

    2013-04-04

    ... for May 2013 meeting. STATUS: Open. LOCATION: This meeting will be held by teleconference at the... visitors must report to the NSF visitor desk located in the lobby at the 9th and N. Stuart Streets entrance... information and updates (time, place, subject matter or status of meeting) may be found at http://www.nsf.gov...

  5. Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 3. Alternatives for interim storage and transportation

    International Nuclear Information System (INIS)

    1976-05-01

    Volume III of the five-volume report contains information on alternatives for interim storage and transportation. Section titles are: interim storage of spent fuel elements; interim storage of chop-leach fuel bundle residues; tank storage of high-level liquid waste; interim storage of solid non-high-level wastes; interim storage of solidified high-level waste; and, transportation alternatives

  6. Periodic Safety Review in Interim Storage Facilities - Current Regulation and Experiences in Germany

    International Nuclear Information System (INIS)

    Neles, Julia Mareike; Schmidt, Gerhard

    2014-01-01

    Periodic safety reviews in nuclear power plants in Germany have been performed since the end of the 1980's as an indirect follow-up of the accident in Chernobyl and, in the meantime, are formally required by law. During this process the guidelines governing this review were developed in stages and reached their final form in 1996. Interim storage facilities and other nuclear facilities at that time were not included, so the guidelines were solely focused on the specific safety issues of nuclear power plants. Following IAEA's recommendations, the Western European Nuclear Regulator Association (WENRA) introduced PSRs in its safety reference levels for storage facilities (current version in WGWD report 2.1 as of Feb 2011: SRLs 59 - 61). Based on these formulations, Germany improved its regulation in 2010 with a recommendation of the Nuclear Waste Management Commission (Entsorgungskommission, ESK), an expert advisory commission for the federal regulatory body BMU. The ESK formulated these detailed requirements in the 'ESK recommendation for guides to the performance of periodic safety reviews for interim storage facilities for irradiated fuel elements and heat-generating radioactive waste'. Before finalization of the guideline a test phase was introduced, aimed to test the new regulation in practice and to later include the lessons learned in the final formulation of the guideline. The two-year test phase started in October 2011 in which the performance of a PSR will be tested at two selected interim storage facilities. Currently these recommendations are discussed with interested/concerned institutions. The results of the test phase shall be considered for improvements of the draft and during the final preparation of guidelines. Currently the PSR for the first ISF is in an advanced stage, the second facility just started the process. Preliminary conclusions from the test phase show that the implementation of the draft guideline requires interpretation. The aim of a

  7. Cost studies concerning decontamination and dismantling. The interim store for spent fuel at Studsvik

    International Nuclear Information System (INIS)

    Sjoeblom, Rolf; Sjoeoe, Cecilia; Lindskog, Staffan; Cato, Anna

    2006-04-01

    The interim store for spent fuel at Studsvik was designed and constructed in 1962-64. It has been used for wet storage of fuel from the Aagesta Nuclear Power Plant as well as the R2 reactor at Studsvik. The interim store comprises three cylindrical pools for fuel storage as well as equipment for handling and decontamination. The purpose of the present work is to develop methodology for calculation of future costs for decontamination and dismantling of nuclear research facilities. The analysis is based on information from Studsvik as well as results from information searches. The requirements on precision of cost calculations is high, also at early stages. The reason for this is that the funds are to be collected now but are to be used some time in the future. At the same time they should neither be insufficient nor superfluous. It is apparent from the compilation and analysis that when methodology that has been developed for the purpose of cost calculations for power reactors is applied to research facilities certain drawbacks become apparent, e.g. difficulties to carry out variation analyses. Generally, feedback of data on incurred costs for the purpose of cost calculations can be achieved by using one or more scaling factors together with weighing factors which are established based on e.g. expert judgement. For development and utilisation of such tools it is necessary to have access to estimated costs together with incurred ones. In the report, the following combination of aspects is identified as being of primary significance for achieving a high precision: Calculations with the possibility to calibrate against incurred costs; Radiological surveying tailored to the needs for calculations; Technical planning including selection of techniques to be used; Identification of potential sources for systematic deviations. In the case of the interim store, some of the sources of uncertainty are as follows: Damaged surface layers in the pools; Maintenance status for the

  8. Mirror Advanced Reactor Study interim design report

    Energy Technology Data Exchange (ETDEWEB)

    1983-04-01

    The status of the design of a tenth-of-a-kind commercial tandem-mirror fusion reactor is described at the midpoint of a two-year study. When completed, the design is to serve as a strategic goal for the mirror fusion program. The main objectives of the Mirror Advanced Reactor Study (MARS) are: (1) to design an attractive tandem-mirror fusion reactor producing electricity and synfuels (in alternate versions), (2) to identify key development and technology needs, and (3) to exploit the potential of fusion for safety, low activation, and simple disposal of radioactive waste. In the first year we have emphasized physics and engineering of the central cell and physics of the end cell. Design optimization and trade studies are continuing, and we expect additional modifications in the end cells to further improve the performance of the final design.

  9. Mirror Advanced Reactor Study interim design report

    International Nuclear Information System (INIS)

    1983-04-01

    The status of the design of a tenth-of-a-kind commercial tandem-mirror fusion reactor is described at the midpoint of a two-year study. When completed, the design is to serve as a strategic goal for the mirror fusion program. The main objectives of the Mirror Advanced Reactor Study (MARS) are: (1) to design an attractive tandem-mirror fusion reactor producing electricity and synfuels (in alternate versions), (2) to identify key development and technology needs, and (3) to exploit the potential of fusion for safety, low activation, and simple disposal of radioactive waste. In the first year we have emphasized physics and engineering of the central cell and physics of the end cell. Design optimization and trade studies are continuing, and we expect additional modifications in the end cells to further improve the performance of the final design

  10. Plutonium Finishing Plant. Interim plutonium stabilization engineering study

    Energy Technology Data Exchange (ETDEWEB)

    Sevigny, G.J.; Gallucci, R.H.; Garrett, S.M.K.; Geeting, J.G.H.; Goheen, R.S.; Molton, P.M.; Templeton, K.J.; Villegas, A.J. [Pacific Northwest Lab., Richland, WA (United States); Nass, R. [Nuclear Fuel Services, Inc. (United States)

    1995-08-01

    This report provides the results of an engineering study that evaluated the available technologies for stabilizing the plutonium stored at the Plutonium Finishing Plant located at the hanford Site in southeastern Washington. Further processing of the plutonium may be required to prepare the plutonium for interim (<50 years) storage. Specifically this document provides the current plutonium inventory and characterization, the initial screening process, and the process descriptions and flowsheets of the technologies that passed the initial screening. The conclusions and recommendations also are provided. The information contained in this report will be used to assist in the preparation of the environmental impact statement and to help decision makers determine which is the preferred technology to process the plutonium for interim storage.

  11. Rosiglitazone evaluated for cardiovascular outcomes--an interim analysis

    DEFF Research Database (Denmark)

    Home, Philip D; Pocock, Stuart J; Beck-Nielsen, Henning

    2007-01-01

    BACKGROUND: A recent meta-analysis raised concern regarding an increased risk of myocardial infarction and death from cardiovascular causes associated with rosiglitazone treatment of type 2 diabetes. METHODS: We conducted an unplanned interim analysis of a randomized, multicenter, open...... group). The primary end point was hospitalization or death from cardiovascular causes. RESULTS: Because the mean follow-up was only 3.75 years, our interim analysis had limited statistical power to detect treatment differences. A total of 217 patients in the rosiglitazone group and 202 patients...... in the control group had the adjudicated primary end point (hazard ratio, 1.08; 95% confidence interval [CI], 0.89 to 1.31). After the inclusion of end points pending adjudication, the hazard ratio was 1.11 (95% CI, 0.93 to 1.32). There were no statistically significant differences between the rosiglitazone...

  12. Interim safety basis compliance matrix for Trenches 31 and 34

    International Nuclear Information System (INIS)

    Ames, R.R.

    1994-01-01

    The tables provided in this document identify the specific requirements and basis for the administrative controls established in the Westinghouse Hanford Company (WHC) Solid Waste Burial Ground (SWBG) Interim Safety Basis (ISB) for operation of the Project W-025, Mixed Waste Lined Landfill (Trenches 31 and 34). The tables document the necessary controls and implementing procedures to ensure compliance with the requirements of the ISB. These requirements provide a basis for future Unreviewed Safety Questions (USQ) screening of applicable procedure changes, proposed physical modifications, tests, experiments, and occurrences. Table 1 provides the SWBG interim Operational Safety Requirements administrative controls matrix. The specific assumptions and commitments used in the safety analysis documents applicable to disposal of mixed wastes in Trenches 31 and 34 are provided in Table 2. Table 3 is provided to document the potential engineered and administrative mitigating features identified in the Preliminary Hazard Analysis (PHA) for disposal of mixed waste

  13. Plutonium Finishing Plant. Interim plutonium stabilization engineering study

    International Nuclear Information System (INIS)

    Sevigny, G.J.; Gallucci, R.H.; Garrett, S.M.K.; Geeting, J.G.H.; Goheen, R.S.; Molton, P.M.; Templeton, K.J.; Villegas, A.J.; Nass, R.

    1995-08-01

    This report provides the results of an engineering study that evaluated the available technologies for stabilizing the plutonium stored at the Plutonium Finishing Plant located at the hanford Site in southeastern Washington. Further processing of the plutonium may be required to prepare the plutonium for interim (<50 years) storage. Specifically this document provides the current plutonium inventory and characterization, the initial screening process, and the process descriptions and flowsheets of the technologies that passed the initial screening. The conclusions and recommendations also are provided. The information contained in this report will be used to assist in the preparation of the environmental impact statement and to help decision makers determine which is the preferred technology to process the plutonium for interim storage

  14. 105-C Reactor interim safe storage project technology integration plan

    International Nuclear Information System (INIS)

    Pulsford, S.K.

    1997-01-01

    The 105-C Reactor Interim Safe Storage Project Technology Integration Plan involves the decontamination, dismantlement, and interim safe storage of a surplus production reactor. A major goal is to identify and demonstrate new and innovative D and D technologies that will reduce costs, shorten schedules, enhance safety, and have the potential for general use across the RL complex. Innovative technologies are to be demonstrated in the following areas: Characterization; Decontamination; Waste Disposition; Dismantlement, Segmentation, and Demolition; Facility Stabilization; and Health and Safety. The evaluation and ranking of innovative technologies has been completed. Demonstrations will be selected from the ranked technologies according to priority. The contractor team members will review and evaluate the demonstration performances and make final recommendations to DOE

  15. Ad interim legal remedy in case of large projects

    International Nuclear Information System (INIS)

    Limberger, J.

    1985-01-01

    Action for ad interim judicial relief in response to large projects approved of by the authorities very frequently take several years until a decision is taken by the court. Experience has shown that this applies in particular to large projects such as the construction of nuclear power plants, large-size industrial plants, or airports. It has become regular practice by the authorities concerned to issue an order for immediate execution upon the plan approving decision and granting of licence for said projects, in accordance with section 80, sub-section (2), no.4 of the VwGO. The problems thus created with regard to interim legal remedy sought by the parties concerned are of great significance. The book in hand discusses the question as to whether the practice of the administrative authorities and the courts satisfies the requirements embodied in the law, to provide for efficient legal protection. (orig./HSCH) [de

  16. AGR-2 Data Qualification Interim Report

    Energy Technology Data Exchange (ETDEWEB)

    Michael L. Abbott

    2010-09-01

    Projects for the very high temperature reactor (VHTR) Technology Development Office program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program established the NGNP Data Management and Analysis System (NDMAS) to manage and document VHTR data qualification, for storage of the data in a readily accessible electronic form, and to assist in the analysis and presentation of the data. This document gives the status of NDMAS processing and qualification of data associated with the initial reactor cycle (147A) of the second Advanced Gas Reactor (AGR-2) experiment which began on June 21, 2010. Because it is early in the AGR-2 experiment, data from only two AGR-2 data streams are reported on: Fuel Fabrication and Fuel Irradiation data. As of August 1, 2010, approximately 311,000 irradiation data records have been stored in NDMAS, and qualification tests are in progress. Preliminary information indicates that TC 2 in Capsule 2 failed prior to start of the experiment, and NDMAS testing has thus far identified only two invalid data values from the METSO data collection system Data from the Fission Product Monitoring System (FPMS) are not currently processed until after reactor cycle shutdown and have not yet been received. A description of the ATR operating conditions data associated with the AGR-2 experiment (e.g., power levels) are summarized in the AGR-1 data qualification report (INL/EXT-09-16460). Since ATR data are collected under ATR program data quality requirements (i.e., outside the VHTR program), the NGNP program and NDMAS do not take additional actions to qualify these data other than NDMAS capture testing. Data qualification of graphite characterization data collected under the Graphite Technology Development Project is reported in a separate status report (Hull 2010).

  17. AGR-2 Data Qualification Interim Report

    International Nuclear Information System (INIS)

    Abbott, Michael L.

    2010-01-01

    Projects for the very high temperature reactor (VHTR) Technology Development Office program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program established the NGNP Data Management and Analysis System (NDMAS) to manage and document VHTR data qualification, for storage of the data in a readily accessible electronic form, and to assist in the analysis and presentation of the data. This document gives the status of NDMAS processing and qualification of data associated with the initial reactor cycle (147A) of the second Advanced Gas Reactor (AGR-2) experiment which began on June 21, 2010. Because it is early in the AGR-2 experiment, data from only two AGR-2 data streams are reported on: Fuel Fabrication and Fuel Irradiation data. As of August 1, 2010, approximately 311,000 irradiation data records have been stored in NDMAS, and qualification tests are in progress. Preliminary information indicates that TC 2 in Capsule 2 failed prior to start of the experiment, and NDMAS testing has thus far identified only two invalid data values from the METSO data collection system Data from the Fission Product Monitoring System (FPMS) are not currently processed until after reactor cycle shutdown and have not yet been received. A description of the ATR operating conditions data associated with the AGR-2 experiment (e.g., power levels) are summarized in the AGR-1 data qualification report (INL/EXT-09-16460). Since ATR data are collected under ATR program data quality requirements (i.e., outside the VHTR program), the NGNP program and NDMAS do not take additional actions to qualify these data other than NDMAS capture testing. Data qualification of graphite characterization data collected under the Graphite Technology Development Project is reported in a separate status report (Hull 2010).

  18. Interim Sanitary Landfill Groundwater Monitoring Report. 1997 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-01

    Eight wells of the LFW series monitor groundwater quality in the Steed Pond Aquifer (Water Table) beneath the Interim Sanitary Landfill at the Savannah River Site (SRS). These wells are sampled semiannually to comply with the South Carolina Department of Health and Environmental Control Modified Municipal Solid Waste Permit 025500-1120 (formerly dWP-087A) and as part of the SRS Groundwater Monitoring Program.

  19. 105-H Reactor Interim Safe Storage Project Final Report

    International Nuclear Information System (INIS)

    Ison, E.G.

    2008-01-01

    The following information documents the decontamination and decommissioning of the 105-H Reactor facility, and placement of the reactor core into interim safe storage. The D and D of the facility included characterization, engineering, removal of hazardous and radiologically contaminated materials, equipment removal, decontamination, demolition of the structure, and restoration of the site. The ISS work also included construction of the safe storage enclosure, which required the installation of a new roofing system, power and lighting, a remote monitoring system, and ventilation components.

  20. Interim reliability evaluation program, Browns Ferry fault trees

    International Nuclear Information System (INIS)

    Stewart, M.E.

    1981-01-01

    An abbreviated fault tree method is used to evaluate and model Browns Ferry systems in the Interim Reliability Evaluation programs, simplifying the recording and displaying of events, yet maintaining the system of identifying faults. The level of investigation is not changed. The analytical thought process inherent in the conventional method is not compromised. But the abbreviated method takes less time, and the fault modes are much more visible

  1. Interim dry storage system technologies and innovations VARNA 2002

    International Nuclear Information System (INIS)

    Chollet, P.; Guenon, Y.

    2002-01-01

    The main concepts of the TN24 Family and NUHOMS System are explained in the paper. It is discussed how the NPPs specific requirements and economics trends contributes to the growing families of interim dry storage systems delivered under COGEMA LOGICTICS license. It is concluded that modular solutions are currently dominating because they are derived from main concepts evolved over time, benefited from both the transport aspects with internationally recognised stringent regulations, and various specific ISFSI requirements and economic trends

  2. Interim Stabilization Equipment Essential and Support Drawing Plan

    International Nuclear Information System (INIS)

    HORNER, T.M.

    2000-01-01

    The purpose of this document is to list the Interim Stabilization equipment drawings that are classified as Essential or Support drawings. Essential Drawings are those drawings identified by the facility staff as necessary to directly support the safe operation of the facility or equipment. [CHG 2000a]. Support Drawings are those drawings identified by the facility staff that further describe the design details of structures, systems or components shown on essential drawings. [CHG 2000a

  3. Interim Stabilization Equipment Essential and Support Drawing Plan

    International Nuclear Information System (INIS)

    KOCH, M.R.

    1999-01-01

    The purpose of this document is to list the Interim Stabilization equipment drawings that are classified as Essential or Support drawings. Essential Drawings: Those drawings identified by the facility staff as necessary to directly support the safe operation of the facility or equipment. Support Drawings: Those drawings identified by the facility staff that further describe the design details of structures, systems or components shown on essential drawings

  4. FRACTIONAL CRYSTALLIZATION TESTING WITH INTERIM PRETREATMENT SYSTEM FEEDS

    International Nuclear Information System (INIS)

    HERTING DL

    2008-01-01

    The fractional crystallization process was developed as a pretreatment method for saltcake waste retrieved from Hanford single-shell tanks (SST). The process separates the retrieved SST waste into a high-level waste stream containing the bulk of the radionuclides and a low-activity waste stream containing the bulk of the nonradioactive sodium salts. The Interim Pretreatment System project shifted the focus on pretreatment planning from SST waste to double-shell tank waste

  5. Waste Encapsulation and Storage Facility interim operational safety requirements

    CERN Document Server

    Covey, L I

    2000-01-01

    The Interim Operational Safety Requirements (IOSRs) for the Waste Encapsulation and Storage Facility (WESF) define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation during receipt and inspection of cesium and strontium capsules from private irradiators; decontamination of the capsules and equipment; surveillance of the stored capsules; and maintenance activities. Controls required for public safety, significant defense-in-depth, significant worker safety, and for maintaining radiological consequences below risk evaluation guidelines (EGs) are included.

  6. Transport casks help solve spent fuel interim storage problems

    International Nuclear Information System (INIS)

    Dierkes, P.; Janberg, K.; Baatz, H.; Weinhold, G.

    1980-01-01

    Transport casks can be used as storage modules, combining the inherent safety of passive cooling with the absence of secondary radioactive waste and the flexibility to build up storage capacity according to actual requirements. In the Federal Republic of Germany, transport casks are being developed as a solution to its interim storage problems. Criteria for their design and licensing are outlined. Details are given of the casks and the storage facility. Tests are illustrated. (U.K.)

  7. Dry storage of spent fuel elements: interim facility

    International Nuclear Information System (INIS)

    Quihillalt, O.J.

    1993-01-01

    Apart from the existing facilities to storage nuclear fuel elements at Argentina's nuclear power stations, a new interim storage facility has been planned and projected by the Argentinean Atomic Energy Commission (CNEA) that will be constructed by private group. This article presents the developments and describes the activities undertaken until the national policy approach to the final decision for the most suitable alternative to be adopted. (B.C.A.). 09 refs, 01 fig, 09 tabs

  8. 77 FR 31894 - Sunshine Act Meeting Notice, Regular Board of Directors Meeting

    Science.gov (United States)

    2012-05-30

    ...,Washington, DC 20005. STATUS: Open. CONTACT PERSON FOR MORE INFORMATION: Erica Hall, Assistant Corporate... Meeting Minutes V. Approval of the Finance, Budget and Program Committee Meeting Minutes VI. Approval of the Corporate Administration Committee Meeting Minutes VII. Executive Session VIII. Board Elections...

  9. Report of a consultants meeting on control rod insertion reliability for WWER-1000 nuclear power plants. Extrabudgetary programme on the safety of WWER and RBMK nuclear power plants

    International Nuclear Information System (INIS)

    1995-09-01

    Starting from 1992, an increased drop time of control rods exceeding the design limit of four seconds has been observed in most of the operating WWER-1000 reactors in Russia and in the Ukraine. In some cases a dropped control rod became stuck in an intermediate position near the bottom of the core. In October 1994, a similar control rod problem was also observed at Unit 6 of the Kozloduy NPP. The issue of control rod insertion reliability was considered at a consultants' meeting on ''Core Control and Protection Strategy of WWER-1000 Reactors'' in April 1994. A consultants' meeting specifically focused on ''Control Rod Insertion Reliability'' was convened in Vienna in February 1995 attended by 15 international experts. The objectives of this meeting were: The exchange of international experience on problems and solutions related to anomalous control rod insertion; judgement of the safety concern of this issue for WWER-1000 reactors based on safety analyses; consideration of regulatory requirements and interim measures to continue operation in short term including modifications implemented or planned; and, status of root cause analyses and pending problems. The technical discussions were held in plenary sessions and in three working groups devoted to specific aspects of the issue. Refs, figs, tabs

  10. Interim data report for the safety assessment SR-Can

    International Nuclear Information System (INIS)

    Vahlund, Fredrik; Andersson, Johan

    2004-08-01

    This document is the interim data report in the project SR-Can. The purpose of the data report is to present input data, with uncertainty estimates, for the SR-Can assessment calculations. Besides input data, the report also describes the standardised procedures used when deriving the input data and the corresponding uncertainty estimates. However, in the present interim version of the report (written in the initial stage of the project when site characterisation has yet not been completed) the standardised procedures have not been possible to apply for most of the data and, in order to present a compilation of the data used in the assessment, much of the input data is presented without following the standardised procedures. This will however be changed for the final version of the SR-Can data report, in order to show the methodology that will be used in the final version one example of how input data will be presented is included (migration data for buffer) . The recommended input data for the assessment calculations are, for the interim version, mainly based on SR 97 Beberg data, these are merely presented without any background or uncertainty discussion (this is presented in the SR 97 data report)

  11. August Meeting

    African Journals Online (AJOL)

    chifaou.amzat

    2011-10-19

    Oct 19, 2011 ... rural hometowns, where they unite with their rural-based colleagues for ... extent have they empowered the women-folk in the public sphere? ...... It would be safe, therefore, for one to conceptualise the 'August Meeting'.

  12. Public meetings

    CERN Multimedia

    Staff Association

    2014-01-01

    You were hundreds of persons to participate in our information meetings of October 3 and 6 2014, and we thank you for your participation! The full presentation is available here. A summary of the topics is available here (in french).

  13. Public meetings

    CERN Multimedia

    Staff Association

    2017-01-01

    Do you have questions about the elections to the Staff Council, 2017 MERIT exercise, EVE and School, LD to IC exercise, CHIS, the Pension Fund… Come get informed and ask your questions at our public meetings. These public meetings are also an opportunity to get the more information on current issues. Benefit from this occasion to get the latest news and to discuss with the representatives of the statutory body that is the Staff Association!

  14. The Interim Financial Reporting in the Spirit of the IAS 34 Norm

    OpenAIRE

    Ovidia Doinea

    2008-01-01

    The role of an interim financial reporting is to allow the information users to acknowledge the activity of an entity on period shorter than financial exercise from the perspective of the available profits and cash flows generated as well as from the point of view of its financial position and liquidity. The interim financial reporting includes a complete or condensed set of financial statements which target to update the last financial reporting, usually the annual report. The interim financ...

  15. Immobilized high-level waste interim storage alternatives generation and analysis and decision report

    International Nuclear Information System (INIS)

    CALMUS, R.B.

    1999-01-01

    This report presents a study of alternative system architectures to provide onsite interim storage for the immobilized high-level waste produced by the Tank Waste Remediation System (TWRS) privatization vendor. It examines the contract and program changes that have occurred and evaluates their impacts on the baseline immobilized high-level waste (IHLW) interim storage strategy. In addition, this report documents the recommended initial interim storage architecture and implementation path forward

  16. Interim guidelines for protecting fire-fighting personnel from multiple hazards at nuclear plant sites

    International Nuclear Information System (INIS)

    Klein, A.R.; Bloom, C.W.

    1989-07-01

    This report provides interim guidelines for reducing the impact to fire fighting and other supporting emergency response personnel from the multiple hazards of radiation, heat stress, and trauma when fighting a fire in a United States commercial nuclear power plant. Interim guidelines are provided for fire brigade composition, training, equipment, procedures, strategies, heat stress and trauma. In addition, task definitions are provided to evaluate and further enhance the interim guidelines over the long term. 19 refs

  17. DEMONSTRATION OF THE DOE INTERIM ENERGY CONSERVATION STANDARDS FOR NEW FEDERAL RESIDENTIAL BUILDINGS

    Energy Technology Data Exchange (ETDEWEB)

    Lee, A. D.; Baechler, H. C.; Di Massa, F. V.; Lucas, R. G.; Shankle, D. L.

    1992-01-01

    system to develop a design which would comply with the standards. PNL conducted extensive interviews with the federal agencies and design contractors to determine what impacts the standards would have on the existing agency procurement process as well as on designers. Overall, PNL found that the interim standards met the basic intent of the law. Specific actions were identified, however, that DOE could take to improve the standards and encourage the agencies to implement them. Agency personnel found the minimum efficiency levels established by the standards to be lower than expected, and lower than their existing requirements. Generally, this was because the standards factor in fuel costs, as well as energy savings due to various conservation measures such as insulation, when they determine the minimum efficiency levels required. The demonstration showed that federal agencies often pay low prices for heating fuel and electricity; these lower costs "tipped the scales," allowing designers to meet the efficiency target with designs that were relatively inefficient. It appeared, however, that the low prices paid by agencies directly to suppliers did not capture the agencies' full costs of providing energy, such as the costs of distribution and storage. Agency personnel expressed some concern about the standards' ability to incorporate new energy-efficient technologies and renewable resource technologies like solar heating systems. An alternative compliance procedure was developed to incorporate new technologies; however, demonstration participants said the procedure was not well documented and was difficult and time consuming to use. Despite these concerns, most agency personnel thought that the standards would fit into current procurement procedures with no big changes or cost increases. Many said use of the standards would decrease the time and effort they now spend to establish energy-efficiency requirements and to confirm that proposed designs comply. Personnel praised

  18. 244-AR Vault Interim Stabilization Project Plan

    International Nuclear Information System (INIS)

    LANEY, T.

    2000-01-01

    The 244-AR Vault Facility, constructed between 1966 and 1968, was designed to provide lag storage and treatment for the Plutonium-Uranium Extraction Facility (PUREX) tank farm sludges. Tank farm personnel transferred the waste from the 244-AR Vault Facility to B Plant for recovery of cesium and strontium. B Plant personnel then transferred the treatment residuals back to the tank farms for storage of the sludge and liquids. The last process operations, which transferred waste supporting the cesium/strontium recovery mission, occurred in April 1978. After the final transfer in 1978, the 244-AR facility underwent a cleanout. However, 2,271 L (600 gal) of sludge were left in Tank 004AR from an earlier transfer from Tank 241-AX-104. When the cleanout was completed, the facility was placed in a standby status. The sludge had been transferred to Tank 004AR to support Pacific Northwest National Laboratory [PNNL] vitrification work. Documentation of waste transfers suggests that a portion of the sludge may have been moved from Tank 004AR to Tank 002AR in preparation for transfer back to the AX Tank Farm; however, quantities of the sludge that were moved to Tank 002AR from that transfer must be estimated

  19. Sampling and analysis plan for Wayne Interim Storage Site (WISS), Wayne, New Jersey

    International Nuclear Information System (INIS)

    Brown, K.S.; Murray, M.E.; Rodriguez, R.E.

    1998-10-01

    This field sampling plan describes the methodology to perform an independent radiological verification survey and chemical characterization of a remediated area of the subpile at the Wayne Interim Storage Site, Wayne, New Jersey.Data obtained from collection and analysis of systematic and biased soil samples will be used to assess the status of remediation at the site and verify the final radiological status. The objective of this plan is to describe the methods for obtaining sufficient and valid measurements and analytical data to supplement and verify a radiological profile already established by the Project Remediation Management Contractor (PMC). The plan describes the procedure for obtaining sufficient and valid analytical data on soil samples following remediation of the first layer of the subpile. Samples will be taken from an area of the subpile measuring approximately 30 m by 80 m from which soil has been excavated to a depth of approximately 20 feet to confirm that the soil beneath the excavated area does not exceed radiological guidelines established for the site or chemical regulatory limits for inorganic metals. After the WISS has been fully remediated, the Department of Energy will release it for industrial/commercial land use in accordance with the Record of Decision. This plan provides supplemental instructions to guidelines and procedures established for sampling and analysis activities. Procedures will be referenced throughout this plan as applicable, and are available for review if necessary

  20. 78 FR 42111 - National Science Board; Sunshine Act Meetings; Notice

    Science.gov (United States)

    2013-07-15

    ...'s badge. All visitors must report to the NSF visitor desk located in the lobby at the 9th and N... information. Meeting information and updates (time, place, subject matter or status of meeting) may be found...

  1. 76 FR 29727 - Sunshine Act Meeting-Change of Time

    Science.gov (United States)

    2011-05-23

    ... meetings on the following dates: May 20, 2011; May 27, 2011.\\1\\ \\1\\ These meetings were announced... Lafayette Center, 1155 21st St., NW., Washington, DC, 9th Floor Commission Conference Room. STATUS: Closed...

  2. Interim policy on establishment and operation of internet open, anonymous information servers and services

    OpenAIRE

    Acting Dean of Computer and Information Services

    1995-01-01

    Purpose. To establish interim NPS general policy regarding establishment and operation of Open, Anonymous Information Servers and Services, such as World Wide Web (http), Gopher, Anonymous FTP, etc...

  3. VERITAS: status c.2005

    International Nuclear Information System (INIS)

    Weekes, T. C.; Atkins, R. W.; Badran, H. M.; Blaylock, G.; Bond, I. H.; Boyle, P. J.; Bradbury, S. M.; Buckley, J. H.; Bryum, K. L.; Carter-Lewis, D. A.; Celik, O.; Chow, Y. C. K.; Cogan, P.; Cui, W.; Daniel, M. K.; Calle Perez, I. de la; Dowdall, C.; Dowkontt, P.; Duke, C.; Ergin, T.

    2006-01-01

    VERITAS (Very Energetic Radiation Imaging Telescope Array System), is one of a new generation of TeV gamma-ray observatories. The current status of its construction is described here. The first two telescopes and cameras have been completed and meet the design specifications; the full array of four telescopes could be operational by the end of 2006

  4. Meeting Mid-Year Meeting

    Indian Academy of Sciences (India)

    23 Newsletter of the Indian Academy of ScienCE. 57th Annual. Meeting ... Srinivas, Institute for Social and Economic. Change ... "Quantum mechanics and statistical mechanics of anyons" .... Special Issue on Geomagnetic Methods and.

  5. 78 FR 290 - National Conference on Weights and Measures 98th Interim Meeting

    Science.gov (United States)

    2013-01-03

    ... (e.g., coal, grains and chemicals) totaling billions of dollars each year. The intent of this... valve is activated. BOV packaging has been in the marketplace for many years and is used to sell the...

  6. 76 FR 81477 - National Conference on Weights and Measures 97th Interim Meeting

    Science.gov (United States)

    2011-12-28

    ... consumers on fuel prices in connection with marketing services and dispensing product. The items that follow... proposal would modify the device specification to recognize current marketing practices that offer post... of tolerances applied to small meters. Electronic Livestock, Meat and Poultry Carcass Evaluation...

  7. 78 FR 78819 - National Conference on Weights and Measures 99th Interim Meeting

    Science.gov (United States)

    2013-12-27

    ... specifications would require that measuring devices used in retail applications to fill motor vehicles have a... to 17, 2014, at the Westin Book Cadillac Detroit, 1114 Washington Boulevard, Detroit, MI 48226. Some... specifications, tolerances, and other requirements for devices used in the retail sales of engine fuels and the...

  8. Public meeting

    CERN Multimedia

    HR Department

    2010-01-01

    Dear Colleagues, I am pleased to invite you to a public meeting which will be held on Thursday 11 November 2010 at 2:30 p.m., in the Main Auditorium (welcome coffee from 2 p.m.) In this meeting Sigurd Lettow, Director for Administration and General Infrastructure will present the Management’s proposals towards restoring full funding of the Pension Fund. The meeting will follow discussions which took place with the Staff Association, at the Standing Concertation Committee (CCP) of 1 November 2010 and will be held with the Members States, at the Tripartite Employment Conditions Forum (TREF) of 4 November 2010. You will be able to attend this presentation in the Main Auditorium or via the webcast. The Management will also be available to reply to your questions on this subject. Best regards, Anne-Sylvie Catherin

  9. ACCU Meeting

    CERN Multimedia

    PH Department

    2010-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 8 December 2010 at 9:15 a.m. in room 60-6-002 Chairperson's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Report on services from GS department The CERN Ombuds The new account management system Crèche progress + Restaurants Reports from ACCU representatives on other committees Users’ Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 12 is invited to send them to the Chairperson in writing or by e-mail to Michael.Hauschild@cern.ch   Michael Hauschild (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): ...

  10. ACCU Meeting

    CERN Multimedia

    PH Department

    2011-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 9 March 2011 At 9:15 a.m. in room 60-6-002   Chairperson's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Report on services from GS department Update on Safety at CERN The new account management system Users’ Office news Any Other Business Agenda for the next meeting   Anyone wishing to raise any points under item 10 is invited to send them to the Chairperson in writing or by e-mail to Michael.Hauschild@cern.ch Michael Hauschild (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria G. Walzel (76592) Belgium ...

  11. ACCU MEETING

    CERN Multimedia

    PH Department

    2010-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 8 September 2010 at 9:15 a.m. in Room 60-6-002 Chairperson’s remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Report on services from GS Department An update on Safety at CERN The CERN Summer Student program Bringing Library services to users Reports from ACCU representatives on other committees Users’ Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 12 is invited to send them to the Chairperson in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): ...

  12. ACCU Meeting

    CERN Multimedia

    PH Department

    2010-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 9 June 2010 At 9:15 a.m. in room 60-6-002 Chairperson’s remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Report on services from GS department CERN Global Network An update on Safety at CERN Reports from ACCU representatives on other committees Users’ Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 11 is invited to send them to the Chairperson in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria G. Walzel (76592) ...

  13. 77 FR 28626 - Sunshine Act Meetings

    Science.gov (United States)

    2012-05-15

    ..., Tucson, Arizona 85745. STATUS: This meeting will be open to the public, unless it is necessary for the... governance and (6) personnel matters. PORTIONS OPEN TO THE PUBLIC: All agenda items except as noted below...

  14. 94TH ACCU MEETING

    CERN Multimedia

    PH Department

    2011-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 7 December 2011 at 9:15 a.m. in room 60-6-002   Chairperson's remarks Adoption of the agenda      Minutes of the previous meeting Matters arising       News from the CERN Management Report on services from GS department Users’ Office news Report on new CHIS rules Creche status Report on Summer Students Users Organization in the U.S. (US LUO) Reports from ACCU representatives on other Committees Accommodation Facilities Working Group Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 13 is invited to send them to the Chairperson in writing or by e-mail to mailto:Michael.Hauschild@cern.ch subject = Next ACCU meeting.   Michael Hauschild (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review th...

  15. Staff meeting

    CERN Document Server

    2006-01-01

    I would like to invite all members of the CERN Personnel to a meeting on Thursday 18 January 2007 at 3:00 p.m. Main Auditorium (bldg.. 500) to convey my best wishes for the new year, to review CERN's activities during 2006 and to present the perspectives for this special year of the LHC start-up. Closed-circuit transmission of the meeting will be available in the Council Chamber and in the AB Auditorium (Meyrin), the AB Auditorium (Prévessin), the IT Auditorium (bldg.. 31) and the AT Auditorium (bldg.. 30). Simultaneous translation into English will be available in the main Auditorium. Robert AYMAR

  16. Scientific meetings

    International Nuclear Information System (INIS)

    1973-01-01

    One of the main aims of the IAEA is to foster the exchange of scientific and technical information and one of the main ways of doing this is to convene international scientific meetings. They range from large international conferences bringing together several hundred scientists, smaller symposia attended by an average of 150 to 250 participants and seminars designed to instruct rather than inform, to smaller panels and study groups of 10 to 30 experts brought together to advise on a particular programme or to develop a set of regulations. The topics of these meetings cover every part of the Agency's activities and form a backbone of many of its programmes. (author)

  17. STAFF MEETING

    CERN Multimedia

    Robert Aymar

    2005-01-01

    I would like to invite all members of the CERN Personnel to a meeting on Thursday 12 January 2006 at 4:00 p.m. - Main Auditorium (bldg. 500) to convey my best wishes for the new year, to review CERN's activities during 2005 and to present the perspectives for this coming year. Closed-circuit transmission of the meeting will be available in the Council Chamber and in the AB Auditorium (Meyrin), the AB Auditorium (Prévessin), the IT Auditorium (bldg. 31) and the AT Auditorium (bldg. 30). A simultaneous translation into English will be available in the main Auditorium. Best wishes for the festive season Robert AYMAR

  18. STAFF MEETING

    CERN Multimedia

    2004-01-01

    I would like to invite all members of the CERN Personnel to a meeting on Tuesday 13 January 2004 at 4:00 p.m. - Main Auditorium (bldg. 500) to convey my best wishes for the new year and to present a perspective of CERN's future activities. Closed-circuit transmission of the meeting will be available in the Council Chamber and in the AB Auditorium (Meyrin), the AB Auditorium (Prévessin), the IT Auditorium (bldg. 31) and the AT Auditorium (bldg. 30). A simultaneous translation into English will be available in the main Auditorium. Robert AYMAR

  19. Public meetings

    CERN Multimedia

    Staff Association

    2014-01-01

      Public meetings : Come and talk about your future employment conditions !   The Staff Association will come and present the results of our survey on the 2015 five-yearly review. Following the survey, the topics discussed, will be contract policy, recognition of merit (MARS), working time arrangements and family policy. After each meeting and around a cup of coffee or tea you will be able to continue the discussions. Do not hesitate to join us, the five-yearly review, it is with YOU!

  20. CMS MANAGEMENT MEETINGS

    CERN Multimedia

    Management Board Agendas and minutes of meetings of the Management Board are accessible to CMS members at: http://indico.cern.ch/categoryDisplay.py?categId=223 Collaboration Board Agendas and minutes of meetings of the Collaboration Board are accessible to CMS members at: http://indico.cern.ch/categoryDisplay.py?categId=174 LHCC: Feedback from the CMS Referees, LHCC 97 February 25, 2009. The CMS LHCC referees met with representatives of CMS on 17-2-09, to review progress since the last November minireview. The main topics included  shutdown construction, maintenance and repairs;  status of the preshower detector; commissioning and physics analysis results from cosmic ray running and CSA08;   preparations for physics, off line analysis, computing, and data distribution. TOTEM management and the TOTEM referees then joined us for a joint session to examine the readiness of the TOTEM detector. Detector construction, maintenance, and repairs. The referees congratulate C...

  1. CMS MANAGEMENT MEETINGS

    CERN Multimedia

    Jim Virdee

    Management Board Agendas and minutes of meetings of the Management Board are accessible to CMS members at: http://indico.cern.ch/categoryDisplay.py?categId=223 Collaboration Board Agendas and minutes of meetings of the Collaboration Board are accessible to CMS members at: http://indico.cern.ch/categoryDisplay.py?categId=174 LHCC: Feedback from the CMS Referees, LHCC 97 February 25, 2009. The CMS LHCC referees met with representatives of CMS on 17-2-09, to review progress since the last November minireview. The main topics included  shutdown construction, maintenance and repairs;  status of the preshower detector; commissioning and physics analysis results from cosmic ray running and CSA08;   preparations for physics, off line analysis, computing, and data distribution. TOTEM management and the TOTEM referees then joined us for a joint session to examine the readiness of the TOTEM detector. Detector construction, maintenance, and repairs. The referees congratula...

  2. CMS MANANGEMENT MEETINGS

    CERN Multimedia

    Management Board Agendas and minutes of meetings of the Management Board are accessible to CMS members at: http://indico.cern.ch/categoryDisplay.py?categId=223 Collaboration Board Agendas and minutes of meetings of the Collaboration Board are accessible to CMS members at: http://indico.cern.ch/categoryDisplay.py?categId=174 LHCC: Feedback from the CMS Referees, LHCC 97 February 25, 2009. The CMS LHCC referees met with representatives of CMS on 17-2-09, to review progress since the last November minireview. The main topics included shutdown construction, maintenance and repairs; status of the preshower detector; commissioning and physics analysis results from cosmic ray running and CSA08; preparations for physics, off line analysis, computing, and data distribution. TOTEM management and the TOTEM referees then joined us for a joint session to examine the readiness of the TOTEM detector. Detector construction, maintenance, and repairs. The referees congratulate CMS Management and the Detector Groups for the...

  3. Environmental survey of two interim dumpsites, Middle Atlantic Bight from 05 November 1973 to 10 November 1973 (NODC Accession 7501280)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — A second oceanographic survey cruise was made to an interim municipal sludge dumpsite and initially to an interim dumpsite for the disposal of industrial acid waste...

  4. Crisis meeting

    CERN Multimedia

    Staff Association

    2014-01-01

      To all CERN staff: your rights are at risk ! We invite you to come to a crisis meeting on Wednesday 2nd April at 10:30 a.m., Auditorium, Main Building, Meyrin site. Your presence is crucial, we are ALL concerned !

  5. Crisis meeting

    CERN Multimedia

    Staff Association

    2015-01-01

    To all CERN staff: your rights are at risk! We invite you to come to a crisis meeting on Thursday 7th May 2015 at 9 a.m., Auditorium, Main Building, Meyrin site. Your presence is crucial, we are ALL concerned!

  6. ACCU MEETING

    CERN Multimedia

    Chris Onions

    2002-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 4 December 2002 At 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Fellows, Associates and Summer Student Programmes Particle Data Book distribution Revoking Computer accounts Equipment insurance on site Reports from ACCU representatives on other committees Users' Office news Any Other Business Dates for meetings in 2003 Agenda for the next meeting Anyone wishing to raise any points under item 12 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch   ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria R. Tzenov (74837...

  7. ACCU MEETING

    CERN Multimedia

    Chris Onions (Secretary)

    2001-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 5 December 2001 At 9:15 a.m. in room 60-6-002 1. Chairman's remarks 2. Adoption of the agenda 3. Minutes of the previous meeting 4. Matters arising 5. News from the CERN Management 6. Housing 7. Restaurant Surveillance Committee 8. Users' Office news 9. Election of ACCU chairman 10. Any Other Business 11. Dates for meetings in 2002 12. Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria  W. Adam  (71661) Belgium  G. Wilquet  (74664) Bulgaria  R. Tzenov  (77958) Czech Republic  P. Závada&am...

  8. ACCU MEETING

    CERN Multimedia

    Chris Onions (Secretary)

    2001-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 5 December 2001 At 9:15 a.m. in room 60-6-002 1. Chairman's remarks 2. Adoption of the agenda 3. Minutes of the previous meeting 4. Matters arising 5. News from the CERN Management 6. Housing 7. Restaurant Surveillance Committee 8. Users' Office news 9. Election of ACCU chairman 10. Any Other Business 11. Dates for meetings in 2002 12. Agenda for the next meetingAnyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria R. Tzenov (77958) Czech Republic P. Závada (75877) Denmark A. Waananen (75941) Finland A. Kiiskinen (79387) Fr...

  9. ACCU MEETING

    CERN Multimedia

    2000-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 6 December 2000 At 10 a.m. in the 6th floor Conference Room, Main Building Chairman's remarks Adoption of the agenda News from the CERN Management Minutes of the previous meeting Matters arising Equal Opportunities at CERN The Summer Student programme CERN Programme for Physics High School Teachers Users' Office News Any Other Business Dates for Meetings in 2001 Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Secretary in writing via the CERN Users' Office or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets) :   Austria G. Neuhofer (74094) Belgium G. Wilquet (74664) Bulgaria R. Tzenov (77958)...

  10. ACCU MEETING

    CERN Multimedia

    Chris Onions (Secretary)

    2000-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 6 December 2000 At 10 a.m. in the 6th floor Conference Room, Main Building Chairman's remarks Adoption of the agenda News from the CERN Management Minutes of the previous meeting Matters arising Equal Opportunities at CERN The Summer Student programme CERN Programme for Physics High School Teachers Users' Office News Any Other Business Dates for Meetings in 2001 Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Secretary in writing via the CERN Users' Office or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets) : Austria G. Neuhofer (74094) Belgium G. Wilquet (74664) Bulgaria R. Tzenov (77958) Czech Re...

  11. ACCU Meeting

    CERN Multimedia

    PH Department

    2011-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 15 June 2011 At 9:15 a.m. in room 60-6-002 Chairperson’s remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Report on services from GS department Update on Safety at CERN Reports from ACCU representatives on other Committees a. Scientific Information Policy Board (SIPB) b. IT Service Review Meeting (ITSRM) c. GS User Commission Users’ Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairperson in writing or by e-mail to Michael.Hauschild@cern.ch Michael Hauschild (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in bra...

  12. Interim safety evaluation report related to operation of Enrico Fermi Atomic Power Plant, Unit 2, Detroit Edison Company

    International Nuclear Information System (INIS)

    1977-09-01

    This interim report summarizes the scope and results of the radiological safety review performed to date by the NRC staff with respect to the operating license phase for the Enrico Fermi Atomic Power Plant, Unit 2. The major effort was the review of the facility design and proposed operating procedures described in applicant's Final Safety Analysis Report. In the course of the review, several meetings were held with representatives of the applicant to discuss plant design, construction and proposed operation. Additional information was requested, which the applicant provided through Amendment 7 to the Final Safety Analysis Report. A chronology of the principal actions relating to the review of the application is attached as Appendix A to the report. The Final Safety Analysis Report and amendments thereto are available for public inspection at the Nuclear Regulatory Commission Public Document Room, 1717 H Street, N. W., Washington, D.C. and at Monroe County Library System, 3700 South Custer Road, Monroe, Michigan 48161

  13. Safety system status monitoring

    International Nuclear Information System (INIS)

    Lewis, J.R.; Morgenstern, M.H.; Rideout, T.H.; Cowley, P.J.

    1984-03-01

    The Pacific Northwest Laboratory has studied the safety aspects of monitoring the preoperational status of safety systems in nuclear power plants. The goals of the study were to assess for the NRC the effectiveness of current monitoring systems and procedures, to develop near-term guidelines for reducing human errors associated with monitoring safety system status, and to recommend a regulatory position on this issue. A review of safety system status monitoring practices indicated that current systems and procedures do not adequately aid control room operators in monitoring safety system status. This is true even of some systems and procedures installed to meet existing regulatory guidelines (Regulatory Guide 1.47). In consequence, this report suggests acceptance criteria for meeting the functional requirements of an adequate system for monitoring safety system status. Also suggested are near-term guidelines that could reduce the likelihood of human errors in specific, high-priority status monitoring tasks. It is recommended that (1) Regulatory Guide 1.47 be revised to address these acceptance criteria, and (2) the revised Regulatory Guide 1.47 be applied to all plants, including those built since the issuance of the original Regulatory Guide

  14. Safety system status monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, J.R.; Morgenstern, M.H.; Rideout, T.H.; Cowley, P.J.

    1984-03-01

    The Pacific Northwest Laboratory has studied the safety aspects of monitoring the preoperational status of safety systems in nuclear power plants. The goals of the study were to assess for the NRC the effectiveness of current monitoring systems and procedures, to develop near-term guidelines for reducing human errors associated with monitoring safety system status, and to recommend a regulatory position on this issue. A review of safety system status monitoring practices indicated that current systems and procedures do not adequately aid control room operators in monitoring safety system status. This is true even of some systems and procedures installed to meet existing regulatory guidelines (Regulatory Guide 1.47). In consequence, this report suggests acceptance criteria for meeting the functional requirements of an adequate system for monitoring safety system status. Also suggested are near-term guidelines that could reduce the likelihood of human errors in specific, high-priority status monitoring tasks. It is recommended that (1) Regulatory Guide 1.47 be revised to address these acceptance criteria, and (2) the revised Regulatory Guide 1.47 be applied to all plants, including those built since the issuance of the original Regulatory Guide.

  15. 42 CFR 93.401 - Interaction with other offices and interim actions.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 1 2010-10-01 2010-10-01 false Interaction with other offices and interim actions. 93.401 Section 93.401 Public Health PUBLIC HEALTH SERVICE, DEPARTMENT OF HEALTH AND HUMAN SERVICES... Human Services General Information § 93.401 Interaction with other offices and interim actions. (a) ORI...

  16. A comparison of the value relevance of interim and annual financial statements

    Directory of Open Access Journals (Sweden)

    Mbalenhle Zulu

    2017-03-01

    Aim: It explores whether the value relevance of interim financial statements is higher than the value relevance of annual financial statements. Finally, it investigates whether accounting information published in interim and annual financial statements has incremental value relevance. Setting: Data for the period from 1999 to 2012 were collected from a sample of non-financial companies listed on the Johannesburg Stock Exchange. Method: The Ohlson model to investigate the value relevance of accounting information was used for the study. Results: The results show that interim book value of equity is value relevant while interim earnings are not. Interim financial statements appear to have higher value relevance than annual financial statements. The value relevance of interim and annual accounting information has remained fairly constant over the sample period. Incremental comparisons provide evidence that additional book value of equity and earnings that accrue to a company between interim and annual reporting dates are value relevant. Conclusion: The study was conducted over a long sample period (1999–2012, in an era when a technology-driven economy and more timely reporting media could have had an effect on the value relevance of published accounting information. To the best of our knowledge, this is the first study to evaluate and compare the value relevance of published interim and annual financial statements.

  17. PROJECT W-551 INTERIM PRETREATMENT SYSTEM TECHNOLOGY SELECTION SUMMARY DECISION REPORT AND RECOMMENDATION

    International Nuclear Information System (INIS)

    CONRAD EA

    2008-01-01

    This report provides the conclusions of the tank farm interim pretreatment technology decision process. It documents the methodology, data, and results of the selection of cross-flow filtration and ion exchange technologies for implementation in project W-551, Interim Pretreatment System. This selection resulted from the evaluation of specific scope criteria using quantitative and qualitative analyses, group workshops, and technical expert personnel

  18. Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

    International Nuclear Information System (INIS)

    Burgard, K.C.

    1998-01-01

    The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis

  19. 18 CFR 300.20 - Interim acceptance and review of Bonneville Power Administration rates.

    Science.gov (United States)

    2010-04-01

    ... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Interim acceptance and review of Bonneville Power Administration rates. 300.20 Section 300.20 Conservation of Power and Water... Director of the Office of Energy Market Regulation; or (ii) Deny the Administrator's interim rate request...

  20. 78 FR 41125 - Interim Enforcement Policy for Permanent Implant Brachytherapy Medical Event Reporting

    Science.gov (United States)

    2013-07-09

    ... NUCLEAR REGULATORY COMMISSION [NRC-2013-0114] Interim Enforcement Policy for Permanent Implant Brachytherapy Medical Event Reporting AGENCY: Nuclear Regulatory Commission. ACTION: Policy statement; revision. SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an interim Enforcement Policy that allows...

  1. Interim format and content for a physical security plan for nuclear power plants

    International Nuclear Information System (INIS)

    1977-02-01

    The document serves as interim guidance to assist the licensee or applicant in the preparation of a physical security plan. It is to be used in conjunction with interim acceptance criteria for physical security programs, which will be distributed at a later date

  2. 42 CFR 417.572 - Budget and enrollment forecast and interim reports.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 3 2010-10-01 2010-10-01 false Budget and enrollment forecast and interim reports... PLANS, AND HEALTH CARE PREPAYMENT PLANS Medicare Payment: Cost Basis § 417.572 Budget and enrollment forecast and interim reports. (a) Annual submittal. The HMO or CMP must submit an annual operating budget...

  3. Conceptual design report for immobilized high-level waste interim storage facility (Phase 1)

    Energy Technology Data Exchange (ETDEWEB)

    Burgard, K.C.

    1998-04-09

    The Hanford Site Canister Storage Building (CSB Bldg. 212H) will be utilized to interim store Phase 1 HLW products. Project W-464, Immobilized High-Level Waste Interim Storage, will procure an onsite transportation system and retrofit the CSB to accommodate the Phase 1 HLW products. The Conceptual Design Report establishes the Project W-464 technical and cost basis.

  4. 30 CFR 827.13 - Coal preparation plants: Interim performance standards.

    Science.gov (United States)

    2010-07-01

    ... 30 Mineral Resources 3 2010-07-01 2010-07-01 false Coal preparation plants: Interim performance...-COAL PREPARATION PLANTS NOT LOCATED WITHIN THE PERMIT AREA OF A MINE § 827.13 Coal preparation plants: Interim performance standards. (a) Persons operating or who have operated coal preparation plants after...

  5. Interim Action Proposed Plan for the Chemicals, Metals, and Pesticides (CMP) Pits Operable Unit; FINAL

    International Nuclear Information System (INIS)

    Bradley, J.

    2002-01-01

    The purpose of this Interim Action Proposed Plan (IAPP) is to describe the preferred interim remedial action for addressing the Chemicals, Metals, and Pesticides (CMP) Pits Operable Unit and to provide an opportunity for public input into the remedial action selection process

  6. The PDF4LHC Working Group Interim Report

    CERN Document Server

    Alekhin, Sergey; Ball, Richard D.; Bertone, Valerio; Blumlein, Johannes; Botje, Michiel; Butterworth, Jon; Cerutti, Francesco; Cooper-Sarkar, Amanda; de Roeck, Albert; Del Debbio, Luigi; Feltesse, Joel; Forte, Stefano; Glazov, Alexander; Guffanti, Alberto; Gwenlan, Claire; Huston, Joey; Jimenez-Delgado, Pedro; Lai, Hung-Liang; Latorre, Jose I.; McNulty, Ronan; Nadolsky, Pavel; Olaf Moch, Sven; Pumplin, Jon; Radescu, Voica; Rojo, Juan; Sjostrand, Torbjorn; Stirling, W.J.; Stump, Daniel; Thorne, Robert S.; Ubiali, Maria; Vicini, Alessandro; Watt, Graeme; Yuan, C.-P.

    2011-01-01

    This document is intended as a study of benchmark cross sections at the LHC (at 7 TeV) at NLO using modern parton distribution functions currently available from the 6 PDF fitting groups that have participated in this exercise. It also contains a succinct user guide to the computation of PDFs, uncertainties and correlations using available PDF sets. A companion note, also submitted to the archive, provides an interim summary of the current recommendations of the PDF4LHC working group for the use of parton distribution functions and of PDF uncertainties at the LHC, for cross section and cross section uncertainty calculations.

  7. Interim report on the TMI-2 purification filter examination

    International Nuclear Information System (INIS)

    Mason, R.E.; Hobbins, R.R.; Cook, B.A.; MacDonald, P.E.

    1983-02-01

    Filters from the purification/makeup system of the Three Mile Island Unit 2 Reactor were examined after the March 28, 1979, accident to determine the character of the debris transported to the filters. The general condition of the filters is presented. Material was removed from the filters and examined. The elemental and radionuclide makeup of the debris is discussed. Distribution of particle size and shape is presentd for some of the material examined. This is an interim report. When the investigation is completed, another report summarizing all of the data will be issued

  8. Cost estimation of interim dry storage for Atucha I NPP

    International Nuclear Information System (INIS)

    Bergallo, Juan E.; Fuenzalida Troyano, Carlos S.

    2007-01-01

    A joint effort between NASA and CNEA has been performed in order to evaluate and fix the strategy of interim spent fuel storage for Atucha I nuclear power plant. In this work the cost estimation on the proposed system was performed in order to fix the parameter and design criteria for the next engineering step. The main results achieved show that both alternatives are all in the same range of costs per unit of mass to be stored, the impact on electricity cost is less than 1 US mills/KWh and the scaling factor achieved is 0.85. (author) [es

  9. Nondestructive evaluation of creep-fatigue damage: an interim report

    International Nuclear Information System (INIS)

    Nickell, R.E.

    1977-02-01

    In view of the uncertainties involved in designing against creep-fatigue failure and the consequences of such failures in Class 1 nuclear components that operate at elevated temperature, the possibility of intermittent or even continuous non-destructive examination of these components has been considered. In this interim report some preliminary results on magnetic force and ultrasonic evaluation of creep-fatigue damage in an LMFBR steam generator material are presented. These results indicate that the non-destructive evaluation of pure creep damage will be extremely difficult. A set of biaxial creep-fatigue tests that are designed to discriminate between various failure theories is also described

  10. Dry interim storage of radioactive material in Germany

    International Nuclear Information System (INIS)

    Drobniewski, Christian; Palmes, Julia

    2013-01-01

    In accordance with the waste management concept in Germany, spent fuel is stored in interim storage facilities for a period of up to 40 years until deposition in a geological repository. In twelve on-site interim storages in the vicinity or directly on the sites of the nuclear power plants, spent fuel elements from reactor operation are stored after the necessary period of decay in wet storage basins inside the reactors. Additionally, three central interim storage facilities for storage of spent fuel of different origin are in operation. The German facilities realize the concept of dry interim storage in metallic transport and storage casks. The confinement of the radioactive material is ensured by the double lid system of the casks, of which the leak tightness is monitored constantly. The casks are constructed to provide adequate heat removal and shielding of gamma and neutron radiation. Usually the storage facilities are halls of thick concrete structures, which ensure the removal of the decay heat by natural convection. The main safety goal of the storage concept is to prevent unnecessary exposure of persons, material goods and environment to ionizing radiation. Moreover any exposure should be kept as low as reasonable achievable. To reach this goal the containment of the radioactive materials, the disposal of decay heat, the sub criticality and the shielding of ionizing radiation has to be demonstrated by the applicant and verified by the licensing authority. In particular accidents, incidents and disasters have to be considered in the facility and cask design. This includes mechanical impacts onto the cask, internal and external fire, and environmental effects like wind, rain, snowfall, flood, earthquakes and landslides. In addition civilizatoric influences like plane crashes and explosions have to be taken into account. In all mentioned cases the secure confinement of the radioactive materials has to be ensured. On-site storage facilities have to consider the

  11. 75 FR 12583 - Sunshine Act; Meeting Notice

    Science.gov (United States)

    2010-03-16

    ...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. Status: Public and Closed. Week of..., 301-415-3152). This meeting will be webcast live at the Web address-- http://www.nrc.gov . Week of...) (Contact: Jose Ibarra, 301-415-2581). This meeting will be webcast live at the Web address-- http://www.nrc...

  12. 78 FR 4476 - Sunshine Act; Meeting Notice

    Science.gov (United States)

    2013-01-22

    ...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of... live at the Web address--www.nrc.gov. 9:00 a.m. Briefing on Public Participation in NRC Regulatory Decision- Making (Public Meeting) (Contact: Lance Rakovan, 301-415-2589). This meeting will be webcast live...

  13. 78 FR 60331 - Sunshine Act Meeting

    Science.gov (United States)

    2013-10-01

    ..., October 7, 14, 21, 28, November 4, 2013. PLACE: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of September 30, 2013 There are no meetings scheduled..., 301-415-1711). This meeting will be webcast live at the Web address-- http://www.nrc.gov/ . Friday...

  14. 78 FR 51234 - Sunshine Act Meetings

    Science.gov (United States)

    2013-08-20

    ...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of... (Closed--Ex. 2 and 6). Tuesday, August 27, 2013 9:00 a.m. Briefing on NRC's Construction Activities (Public Meeting); (Contact: Michelle Hayes, 301-415-8375). This meeting will be webcast live at the Web...

  15. 76 FR 77574 - Sunshine Act Meeting Notice

    Science.gov (United States)

    2011-12-13

    ..., 16, 2012. Place: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. Status: Public and closed. Week of December 12, 2011 Tuesday, December 13, 2011 9 a.m. Briefing on NFPA 805 Fire Protection (Public Meeting), (Contact: Alex Klein, (301) 415-2822.) This meeting will be webcast live at the...

  16. 78 FR 19757 - Sunshine Act Meetings

    Science.gov (United States)

    2013-04-02

    ...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland STATUS: Public and Closed Week of... Quash Subpoena Filed by the Shaw Group, Inc. (Tentative) This meeting will be webcast live at the Web... meeting will be webcast live at the Web address--www.nrc.gov Week of April 8, 2013--Tentative There are no...

  17. 78 FR 79021 - Sunshine Act Meeting Notice

    Science.gov (United States)

    2013-12-27

    ... 30, 2013, January 6, 13, 20, 27, February 3, 2014. PLACE: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of December 30, 2013 There are no... to Dry Casks (Public Meeting) (Contact: Kevin Witt, 301-415-2145). This meeting will be webcast live...

  18. 78 FR 23960 - Sunshine Act Meetings

    Science.gov (United States)

    2013-04-23

    ...' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of April 22, 2013... Meeting) (Contact: Brett Rini, 301-251-7615). This meeting will be webcast live at the Web address--www.nrc.gov. 2:30 p.m. Discussion of Management and Personnel Issues (Closed--Ex. 2 and 6). Tuesday April...

  19. 78 FR 28258 - Sunshine Act Meetings

    Science.gov (United States)

    2013-05-14

    ...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of...) (Public Meeting) (Contact: Kristin Davis, 301-287- 0707). This meeting will be webcast live at the Web... Security Issues (Closed--Ex. 1). Wednesday, May 29, 2013 9:00 a.m. Briefing on Results of the Agency Action...

  20. 78 FR 962 - Sunshine Act Meetings

    Science.gov (United States)

    2013-01-07

    ...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of...: Michael Hay, 817-200-1527) This meeting will be webcast live at the Web address--www.nrc.gov Wednesday..., 2012) (Tentative) This meeting will be webcast live at the Web address--www.nrc.gov 9:00 a.m. Briefing...

  1. 78 FR 52990 - Sunshine Act Meetings Notice

    Science.gov (United States)

    2013-08-27

    ...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of August 26, 2013 Monday August 26, 2013 2:00 p.m. Discussion of Management and Personnel Issues (Closed... Meeting) (Contact: Michelle Hayes, 301-415-8375). This meeting will be webcast live at the Web address...

  2. 78 FR 21171 - Sunshine Act Meetings

    Science.gov (United States)

    2013-04-09

    ...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of... Meeting) (Contact: Brett Rini, 301-251-7615) This meeting will be webcast live at the Web address--www.nrc.gov. 2:30 p.m. Discussion of Management and Personnel Issues (Closed-- Ex. 2 and 6) Tuesday, April 23...

  3. 78 FR 18376 - Sunshine Act Meetings

    Science.gov (United States)

    2013-03-26

    ...: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. Week of...-0223). This meeting will be webcast live at the Web address--www.nrc.gov. Week of April 8, 2013...) (Contact: Brett Rini, 301-251-7615). This meeting will be webcast live at the Web address--www.nrc.gov. 2...

  4. 75 FR 64748 - Sunshine Act Meeting

    Science.gov (United States)

    2010-10-20

    ... NATIONAL CREDIT UNION ADMINISTRATION Sunshine Act Meeting Notice of a Matter To Be Added to the Agenda for Consideration at an Agency Meeting TIME AND DATE: 10 a.m., Thursday, October 21, 2010. PLACE: Board Room, 7th Floor, Room 7047, 1775 Duke Street, Alexandria, VA 22314-3428. STATUS: Open. Matters To...

  5. 78 FR 67201 - Sunshine Act Meeting

    Science.gov (United States)

    2013-11-08

    ... LEGAL SERVICES CORPORATION Sunshine Act Meeting DATE AND TIME: The Legal Services Corporation's... disrupting the meeting, please refrain from placing the call on hold if doing so will trigger recorded music or other sound. From time to time, the presiding Chair may solicit comments from the public. STATUS...

  6. 78 FR 38409 - Sunshine Act Meeting; Notice

    Science.gov (United States)

    2013-06-26

    ... LEGAL SERVICES CORPORATION Sunshine Act Meeting; Notice DATE AND TIME: The Legal Services... disrupting the meeting, please refrain from placing the call on hold if doing so will trigger recorded music or other sound. From time to time, the presiding Chair may solicit comments from the public. STATUS...

  7. 75 FR 32538 - Sunshine Act Meeting Notice

    Science.gov (United States)

    2010-06-08

    ... news media following the Board meeting. Status: Open Agenda Old Business Approval of minutes of April 16, 2010, Board Meeting New Business 1. Chairman's Remarks 2. President's Report 3. Report of the..., Governance, and Ethics Committee A. Board governance update 6. Report of the Community Relations and Energy...

  8. 75 FR 19465 - Sunshine Act; Meeting Notice

    Science.gov (United States)

    2010-04-14

    ... news media following the Board meeting. STATUS: Open. Agenda Old Business Approval of minutes of February 11, 2010, Board Meeting. New Business 1. Chairman's Report. 2. President's Report. 3. Report of..., and Ethics Committee. A. Designation of Corporate Secretary 6. Report of the Community Relations and...

  9. Sacramento Municipal Utility district's interim onsite storage building for low level radioactive waste

    International Nuclear Information System (INIS)

    Gillis, E.

    1986-01-01

    In order to meet current and anticipated needs for the low level radwaste management program at the Rancho Seco Nuclear Generating Station, the Sacramento Municipal Utility District has a design and construction program underway which will provide an onsite interim storage facility that can be expanded in two and one-half year increments. The design approach utilized allows capital investment to be minimized and still provides radwaste management flexibility in anticipation of delays in resolution of the nationwide long term radwaste disposal situation. The facility provides storage and material accountability for all low level radwastes generated by the plant. Wastes are segregated by radioactivity level and are stored in two separate storage areas located within one facility. Lower activity wastes are stored in a lightly shielded structure and handled by lift trucks, while the higher activity wastes are stored in a highly shielded structure and handled remotely by manual bridge crane. The layout of the structure provides for economy of operation and minimizes personnel radiation exposure. Design philosophy and criteria, building layout and systems, estimated costs and construction schedule are discussed

  10. Evaluation of Dynamic Behavior of Pile Foundations for Interim Storage Facilities Through Geotechnical Centrifuge Tests

    International Nuclear Information System (INIS)

    Shizuo Tsurumaki; Hiroyuki Watanabe; Akira Tateishi; Kenichi Horikoshi; Shunichi Suzuki

    2002-01-01

    In Japan, there is a possibility that interim storage facilities for recycled nuclear fuel resources may be constructed on quaternary layers, rather than on hard rock. In such a case, the storage facilities need to be supported by pile foundations or spread foundations to meet the required safety level. The authors have conducted a series of experimental studies on the dynamic behavior of storage facilities supported by pile foundations. A centrifuge modeling technique was used to satisfy the required similitude between the reduced size model and the prototype. The centrifuge allows a high confining stress level equivalent to prototype deep soils to be generated (which is considered necessary for examining complex pile-soil interactions) as the soil strength and the deformation are highly dependent on the confining stress. The soil conditions were set at as experimental variables, and the results are compared. Since 2000, the Nuclear Power Engineering Corporation (NUPEC) has been conducting these research tests under the auspices on the Ministry of Economy, Trade and Industry of Japan. (authors)

  11. Interim Report of the Commission to Review the Effectiveness of the National Energy Laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Cohon, Jared L. [Carnegie Mellon Univ., Pittsburgh, PA (United States); Glauthier, T. J. [TJG Energy Associates, LLC., Bloomberg, VA (United States); Augustine, Norman R. [U.S. Dept. of Homeland Security, Washington, DC (United States); Austin, Wanda M. [Aerospace Corporation, El Segundo, CA (United States); Elachi, Charles [California Inst. of Technology (CalTech), Pasadena, CA (United States); Fleury, Paul A. [Yale Univ., New Haven, CT (United States); Hockfield, Susan J. [Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Meserve, Richard A. [Covington and Burling LLP, Washington, DC (United States); Murray, Cherry A. [Harvard Univ., Cambridge, MA (United States)

    2015-02-27

    The Commission to Review the Effectiveness of the National Energy Laboratories was charged by Congress in January 2014 to evaluate the mission, capabilities, size, performance, governance, and agency oversight of the 17 Department of Energy (DOE) laboratories. Given the incredibly broad scope and aggressive timeline (the original deadline was February 2015), the Secretary of Energy and Congress agreed to split the task into two phases. This interim report contains the preliminary observations and recommendations gleaned from Phase 1 of the study, which consisted of a literature review; visits to five of the National Laboratories; semi-structured interviews with staff from across the National Laboratories, DOE, other Federal agencies, companies, other non-governmental organizations, and additional interested parties; and presentations at monthly public Commission meetings. The Commission notes that the purpose of the National Laboratories is to provide critical capabilities and facilities in service of DOE’s mission and the needs of the broader national and international science and technology (S&T) community, including other Federal agencies, academia, and private industry. The National Laboratories are successfully fulfilling that mission today. While the Commission believes significant improvements can be made to many aspects of DOE management and governance of the laboratories, those issues do not detract from the National Laboratories’ remarkable contributions to the American public. In Phase 2 the Commission will focus on ways to make the process of carrying out their missions more efficient and effective.

  12. Replacement of a hopeless maxillary central incisor: a technique for the fabrication of an immediate implant-supported interim restoration.

    Science.gov (United States)

    Graiff, Lorenzo; Vigolo, Paolo

    2012-04-01

    Placement of a dental implant and an interim restoration in the esthetic zone immediately following tooth extraction is now a common procedure. However, in such clinical situations, the fabrication of an appropriate interim restoration may be challenging. The aim of this article is to present a technique for modifying the extracted tooth so it can be used as an implant-supported interim restoration.

  13. Meeting of the ITER CTA Project Board

    International Nuclear Information System (INIS)

    Vlasenkov, V.

    2002-01-01

    The meeting of the ITER CTA Project Board (PB) took place in Toronto, Canada on 16 September 2002 on the occasion of the fifth Negotiations Meeting (N-5). Thirteen participants, PB members and experts from Canada, EU, Japan, RF and the International Team (IT) attended the meeting chaired by Acad. E. Velikhov. PB heard progress reports of the participating parties and the comments concerning the status of participants team (PT) and the IT were presented

  14. Fast Flux Test Facility interim examination and maintenance cell: Past, present, and future

    International Nuclear Information System (INIS)

    Vincent, J.R.

    1990-09-01

    The Fast Flux Test Facility Interim Examination and Maintenance Cell was designed to perform interim examination and/or disassembly of experimental core components for final analysis elsewhere, as well as maintenance of sodium-wetted or neutron-activated internal reactor parts and plant support hardware. The Interim Examination and Maintenance Cell equipment developed and used for the first ten years of operation has been primarily devoted to the disassembly and examination of core component test assemblies. While no major reactor equipment has required remote repair or maintenance, the Interim Examina Examination and Maintenance Cell has served as the remote repair facility for its own in-cell equipment, and several innovative remote repairs have been accomplished. The Interim Examination and Maintenance Cell's demonstrated versatility has shown its capability to support a challenging future. 12 refs., 9 figs

  15. Public meetings

    CERN Multimedia

    Staff Association

    2012-01-01

    MARS PENSIONS CONTRACT POLICY GENERAL INFORMATION   PUBLIC MEETINGS COME AND BE INFORMED! Public meetings Monday 15 Oct. 2 pm Amphi IT, 31-3-004 Meyrin Wednesday 17 Oct. 10 am Amphi BE, 864-1-D02 Prévessin Thursday 18 Oct. 10 am Salle du Conseil/ Council Chamber 503-1-001 Meyrin Thursday 18 Oct. 2 pm Filtration Plant, 222-R-001(in English) Meyrin   Overview of the topics to be discussed Recognition of Merit – MARS Outcome of last exercise 2007 to 2012 : lessons learned Pension Fund Capital preservation policy : what is it ? Contract policy LC2IC statistics SA proposal General information CVI 2013 Voluntary programmes (PRP, SLS)  

  16. Staff meeting

    CERN Multimedia

    2007-01-01

    I would like to invite all members of the CERN Personnel to a meeting on Wednesday 16 January 2008 at 3:00 p.m. Main Auditorium (bldg 500) to convey my best wishes for the new year, to review CERN’s activities during 2007 and to present the perspectives for 2008, the year of the LHC start-up. Closed-circuit transmission of the meeting will be available in the Council Chamber and in the AB Auditorium (Meyrin), the AB Auditorium (Prévessin), the IT Auditorium (Bldg. 31) and the AT Auditorium (Bldg. 30). Simultaneous translation into English will be available in the main Auditorium. Best wishes for the festive season! Robert AYMAR

  17. Meeting information

    Science.gov (United States)

    The 1986 Ocean Sciences Meeting of the American Geophysical Union and the American Society of Limnology and Oceanography (ASLO) will be held January 13-17, 1986, in New Orleans, La., at the Fairmont Hotel. Co-sponsoring societies are the Acoustical Society of America (ASA), the American Meteorological Society (AMS), the Marine Technology Society (MTS), and the Institute of Electrical and Electronics Engineers, Oceanic Engineering Society (OES).

  18. ACCU Meeting

    CERN Multimedia

    2004-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 10 March 2004 At 9:15 a.m. in room 60-6-002 1. Chairman's remarks 6. The PH Department 2. Adoption of the agenda 7. Reports from ACCU representatives on other committees 3. Minutes of the previous meeting 8. Users' Office news 4. News from the CERN Management 9. Any Other Business 5. Matters arising 10. Agenda for the next meeting Anyone wishing to raise any points under item 9 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Norway H. Helstrup (73601) Belgium G. Wilquet (74664) Poland Z. Hajduk (75917) Bulgaria R. Tsenov (79573) Portugal P. Bordalo (74704) Czech Republic P. Závada ...

  19. ACCU MEETING

    CERN Multimedia

    Chris Onions

    2004-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 10 March 2004 At 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting News from the CERN Management Matters arising The PH Department Reports from ACCU representatives on other committees Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 9 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria R. Tzenov (77958) Czech Republic P. Závada (75877) Denmark P. Hansen (75941) Finland E. Tuominen (71534) France F. Bauer (71247) L. Serin...

  20. ACCU MEETING

    CERN Multimedia

    Chris Onions/EP (Secretary)

    2001-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 6 June 2001 At 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda News from the CERN Management Minutes of the previous meeting Matters arising EP Space management Cars Housing EDH from the User's point of view VRVS Users' Office News Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 12 is invited to send them to the Secretary in writing via the CERN Users' Office or by e-mail to Christopher.Onions@cern.ch ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria R. Tzenov (77958) Czech Republic P. Závada (75877) Denmark A. Waananen (75941) Finland A. Kiiskinen (79387) France M. Déj...

  1. ACCU Meeting

    CERN Document Server

    Chris Onions

    2006-01-01

    DRAFT Agenda of the meeting to be held on Wednesday 8 March 2006 At 9:15 a.m. in Room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Proposal for a centralised access control service Report from PH Space Management Policy Board Reports from ACCU representatives on other committees Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under Item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives on ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria Czech Republic P. Závada (75877) Denmark J.B. Hansen (75941) ...

  2. ACCU MEETING

    CERN Document Server

    2007-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 5 December 2007 at 9:15 a.m. in room 60-6-002 1.\tChairman’s remarks7.\tEmergency Services at CERN 2.\tAdoption of the agenda\t8.\tThe Meyrin Tram project 3.\tMinutes of the previous meeting9.\tReports from ACCU representatives on other committees 4.\tMatters arising10.\tUsers’ Office news 5.\tNews from the CERN Management11.\tElection of ACCU Chair 6. LHC 2008 start-up events 6.\tLogistics and transport at CERN 12.\tAny Other Business 13.\tAgenda for the next meeting Anyone wishing to raise any points under item 12 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Aust...

  3. ACCU MEETING

    CERN Multimedia

    PH Department

    2008-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 11 June 2008 At 9:15 a.m. in Room 60-6-002 1.\tChairman’s remarks 2.\tAdoption of the agenda 3.\tMinutes of the previous meeting 4.\tMatters arising 5.\tNews from the CERN Management 6.\tAn update on safety at CERN 7.\tChildcare initiative 8.\tReports from ACCU representatives on other committees 9.\tUsers’ Office news 10.\tAny Other Business 11.\tAgenda for the next meeting Anyone wishing to raise any points under Item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium C. Vander Velde (71539) Bulgaria Czech Republic P. Závada (75...

  4. ACCU meeting

    CERN Document Server

    2007-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 5 December 2007 At 9:15 a.m. in room 60-6-002 1.\tChairman’s remarks 2.\tAdoption of the agenda 3.\tMinutes of the previous meeting 4.\tMatters arising 5.\tNews from the CERN Management 6.\tLHC 2008 start-up events 7.\tEmergency Services at CERN 8.\tThe Meyrin Tram project 9.\tReports from ACCU representatives on other committees 10.\tUsers’ Office news 11.\tElection of ACCU Chair 12.\tAny Other Business 13.\tAgenda for the next meeting Anyone wishing to raise any points under item 12 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilq...

  5. ACCU MEETING

    CERN Document Server

    Chris Onions

    2004-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 9 June 2004 at 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Update on CERN's 50th anniversary celebrations Report from the EPOG (European Particle Physics Outreach Group) Reports from ACCU representatives on other committees Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria R. Tzenov (77958) Czech Republic P. Závada (75877) Denmark P. Hansen (75941...

  6. ACCU Meeting

    CERN Document Server

    Chris Onions

    2005-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 7 September 2005 At 9:15 a.m. in room 60-6-002 Chairman’s remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Logistics at CERN Reports from ACCU representatives on other committees Users’ Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria Czech Republic P. Závada (75877) Denmark J.B. Hansen (75941) Finland K. Lassila-Perini (79354) France F. Bauer S. Laplace...

  7. ACCU Meeting

    CERN Document Server

    Chris Onions

    2004-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 8 September 2004 At 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management The Visits Service Lifetime of Computer Accounts Reports from ACCU representatives on other committees Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria R. Tsenov (79573) Czech Republic P. Závada (75877) Denmark P. Hansen (75941) Finland K. Lassila-Perini (79354) France F. Bauer (7...

  8. ACCU MEETING

    CERN Document Server

    2006-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 6 September 2006 at 9:15 a.m. in room 60-6-002 1.     Chairman's remarks 2.     Adoption of the agenda 3.     Minutes of the previous meeting 4.     Matters arising 5.     News from the CERN Management 6.     Report on Fellows and Associates programme 7.     Overview of safety at CERN 8.     Reports from ACCU representatives on other committees 9.     Users' Office news 10.  Any Other Business 11.  Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets):Austria W. Adam  (71661) Belgium G. Wilquet (74664) Bulgaria ...

  9. ACCU Meeting

    CERN Document Server

    Chris Onions

    2005-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 7 December 2005 At 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Closure of computer accounts upon CERN contract expiry Reports from ACCU representatives on other committees Users' Office news Election of ACCU Chair Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets). Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria Czech Republic P. Závada (75877) Denmark J.B. Hansen (75941) ...

  10. ACCU Meeting

    CERN Multimedia

    Chris Onions

    2005-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 8 June 2005 At 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Logistics at CERN Open Access Publishing Reports from ACCU representatives on other committees Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria R. Tsenov (79573) Czech Republic P. Závada (75877) Denmark J.B. Hansen (75941) Finland K. Lassila-Perini ...

  11. ACCU Meeting

    CERN Document Server

    Chris Onions

    2006-01-01

    DRAFT Agendafor the meeting to be held on Wednesday 8 March 2006At 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Proposal for a centralised access control service Report from PH Space Management Policy Board Reports from ACCU representatives on other committees Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria Czech Republic P. Závada (75877) Denmark J.B. Hansen (75941) Fin...

  12. ACCU Meeting

    CERN Multimedia

    Chris Onions

    2005-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 9 March 2005 At 9:15 a.m. in room 160-1-009 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Purchasing procedures at CERN Reports from ACCU representatives on other committees Users' Office news CERN Clubs Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria R. Tsenov (79573) Czech Republic P. Závada (75877) Denmark J.B. Hansen (75941) Finland K. Las...

  13. ACCU MEETING

    CERN Document Server

    2007-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 12 September 2007 at 9:15 a.m. in room 60-6-002 1.\tChairman’s remarks7.\tCar sharing pilot project 2.\tAdoption of the agenda\t8.\tReports from ACCU representatives on other committees 3.\tMinutes of the previous meeting9.\tUsers’ Office newss 4.\tMatters arising10.\tAny Other Business 5.\tNews from the CERN Management11.\tAgenda for the next meeting 6.\tLogistics and transport at CERN Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria\tW. Adam (71661)NorwayG. Løvhøiden (73176)Belgium\tG. Wilquet (74664)PolandM. Witek (78967)...

  14. ACCU MEETING

    CERN Multimedia

    PH Department

    2008-01-01

    DRAFT Agenda for the meeting to be heldon Wednesday 5 March 2008 At 9:15 a.m. in room 60-6-002 Chairman’s remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management An update on Safety at CERN The CERN Ombudsperson proposal Childcare initiative Reports from ACCU representatives on other committees Users’ Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 11 is invited to send them to the Chairman in writing or by e-mail to mailto:Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) BelgiumnC. Vander Velde (71539) Bulgaria Czech Republic P. Závada (75877) Denm...

  15. ACCU MEETING

    CERN Document Server

    2006-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 6 December 2006 At 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Safety at CERN Car sharing pilot project CERN Public Web Sites and Intranet Reports from ACCU representatives on other committees Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 11 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria   Czech Republic P. Závada (75877) Denmark J.B. Hansen (75941) Finl...

  16. ACCU Meeting

    CERN Multimedia

    Chris Onions

    2004-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 8 December 2004 At 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting The effects of the reorganization of CERN's structure, one year on Matters arising News from the CERN Management Computer Security The new CERN Dosimeter Reports from ACCU representatives on other committees Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria R. Tsenov (79573) Czech Republic P. Závada (75877) Denmark P. Hansen (7594...

  17. ACCU MEETING

    CERN Multimedia

    2006-01-01

    DRAFT Agenda of the meeting to be held on Wednesday 6 September 2006 at 9:15 a.m. in Room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Report on Fellows and Associates Programme Overview of safety at CERN Reports from ACCU representatives on other committees Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under Item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria Czech Republic P. Závada (75877) Denmark J.B. Hansen (75941) Finland K....

  18. ACCU meeting

    CERN Document Server

    PH Department

    2008-01-01

    DRAFT Agenda for the meeting to be heldon Wednesday 5 March 2008 At 9:15 a.m. in room 60-6-002 Chairman’s remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management An update on Safety at CERN The CERN Ombudsperson proposal Childcare initiative Reports from ACCU representatives on other committees Users’ Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 11 is invited to send them to the Chairman in writing or by e-mail to mailto:Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) BelgiumnC. Vander Velde (71539) Bulgaria Czech Republic P. Závada (75877) Denm...

  19. ACCU MEETING

    CERN Document Server

    PH Department

    2008-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 10 September 2008 At 9:15 a.m. in Room 60-6-002 Chairman’s remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management An update on Safety at CERN Reports from ACCU representatives on other committees Users’ Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 9 is invited to send them to the Chairman in writing or by e-mail to mailto:Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria, W. Adam (71661) Belgium, C. Vander Velde (71539) Bulgaria Czech Republic, P. Závada (75877) Denmark, J.B. Hansen (...

  20. ACCU Meeting

    CERN Document Server

    2007-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 7 March 2007 at 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Car-sharing pilot project Reports from ACCU representatives on other committees Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 9 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria Czech Republic P. Závada (75877) Denmark J.B. Hansen (75941) Finland K. Lassila-Perini (79354) France F. Kunne S. ...

  1. ACCU Meeting

    CERN Document Server

    Chris Onions

    2004-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 8 September 2004 At 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management The Visits Service Lifetime of Computer Accounts Reports from ACCU representatives on other committees Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria R. Tsenov (79573) Czech Republic P. Závada (75877) Denmark P. Hansen (75941) Finland K. Lassila-Perini (79354) France F. Bauer (...

  2. ACCU Meeting

    CERN Multimedia

    2006-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 6 December 2006 At 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Safety at CERN Car sharing pilot project CERN Public Web Sites and Intranet Reports from ACCU representatives on other committees Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 11 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria   Czech Republic P. Závada (75877) Denmark J.B. Hansen (75941) Finl...

  3. ACCU Meeting

    CERN Multimedia

    PH Department

    2008-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 11 June 2008 At 9:15 a.m. in room 60-6-002 Chairman’s remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management An update on Safety at CERN Childcare initiative Reports from ACCU representatives on other committees Users’ Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to mailto:Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria - W. Adam (71661) Belgium - C. Vander Velde (71539) Bulgaria Czech Republic - P. Závada (75877) Denmark - J.B. Hansen...

  4. ACCU Meeting

    CERN Multimedia

    Chris Onions

    2004-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 8 December 2004 At 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting The effects of the reorganization of CERN's structure, one year on Matters arising News from the CERN Management Computer Security The new CERN Dosimeter Reports from ACCU representatives on other committees Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria R. Tsenov (79573) Czech Republic P. Závada (75877) Denmark P. Hansen (75941) Finl...

  5. ACCU Meeting

    CERN Multimedia

    Chris Onions

    2004-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 9 June 2004 at 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Update on CERN's 50th anniversary celebrations Report from the EPOG (European Particle Physics Outreach Group) Reports from ACCU representatives on other committees Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria R. Tsenov (79573) Czech Republic P. Závada (75877) Denmark P. Hansen (75941) Finlan...

  6. ACCU MEETING

    CERN Document Server

    PH Department

    2008-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 3 December 2008 at 9:15 a.m. in Room 60-6-002 1.\tChairman’s remarks 2.\tAdoption of the agenda 3.\tMinutes of the previous meeting 4.\tMatters arising 5.\tNews from the CERN Management 6.\tReport from the new Director-General 7.\tReport on the Fellows and Associates programme 8.\tAn update on Safety at CERN 9.\tReports from ACCU representatives on other committees 10.\tUsers’ Office news 11.\tAny Other Business 12.\tAgenda for the next meeting Anyone wishing to raise any points under item 11 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium C. ...

  7. ACCU MEETING

    CERN Document Server

    2007-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 12 September 2007 at 9:15 a.m. in room 60-6-002 1.\tChairman’s remarks6.\tLogistics and transport at CERN2.\tAdoption of the agenda\t7.\tCar sharing pilot project3.\tMinutes of the previous meeting8.\tReports from ACCU representatives on other committees4.\tMatters arising9.\tUsers’ Office newss5.\tNews from the CERN Management10.\tAny Other Business11.\tAgenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria\tW. Adam (71661)NorwayG. Løvhøiden (73176)Belgium\tG. Wilquet (74664)PolandM. Witek (78967)Bulgaria\tPortugalP...

  8. ACCU Meeting

    CERN Document Server

    2007-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 7 March 2007 at 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Car-sharing pilot project Reports from ACCU representatives on other committees Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 9 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria Czech Republic P. Závada (75877) Denmark J.B. Hansen (75941) Finland K. Lassila-Perini (79354) France F. Kunne S. La...

  9. ACCU MEETING

    CERN Multimedia

    Chris Onions (Secretary)

    2001-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 6 June 2001 At 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda News from the CERN Management Minutes of the previous meeting Matters arising Logistics and Self-service stores EP Space management follow-up How to improve IT User Support? Users' Office News Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Secretary in writing via the CERN Users' Office or by e-mail to Roger.Jones@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria R. Tzenov (77958) Czech Republic P. Závada (75877) Denmark A. Waananen (75941) Finland A. Kiis...

  10. ACCU MEETING

    CERN Multimedia

    Chris Onions (Secretary)

    2001-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 12 September 2001 At 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda News from the CERN Management Minutes of the previous meeting Matters arising Logistics and Self-service stores EP Space management follow-up How to improve IT User Support? Users' Office News Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Secretary in writing via the CERN Users' Office or by e-mail to Roger.Jones@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria R. Tzenov (77958) Czech Republic P. Závada (75877) Denmark A. Waananen (75941) Finland A. Kiiskin...

  11. ACCU MEETING

    CERN Multimedia

    Chris Onions

    2001-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 7 March 2001 At 9:15 a.m. in the 6th floor Conference Room, Main Building Chairman's remarks Adoption of the agenda News from the CERN Management Minutes of the previous meeting Matters arising Video-conferencing/recording Fellows programme Operational Circular No. 6 EP Space management Update on Computing Issues Users' Office News Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 12 is invited to send them to the Secretary in writing via the CERN Users' Office or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary)  ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria R. Tzenov (77958) Czech Republic...

  12. ACCU Meeting

    CERN Multimedia

    2003-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 10 September 2003 At 9:15 a.m. in room 60-6-002 1. Chairman's remarks 7. Equal Opportunities Commission 2. Adoption of the agenda 8. Registration plans for portables 3. Minutes of the previous meeting 9. Reports from ACCU representatives on other committees 4. Matters arising 10. Users' Office news 5. News from the CERN Management 11. Any Other Business 6. The Press Office 12. Agenda for the next meeting Anyone wishing to raise any points under item 11 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Norway H. Helstrup (73601) Belgium G. Wilquet (74664) Poland Z. Hajduk (75917) Bulgar...

  13. ACCU MEETING

    CERN Multimedia

    2003-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 5 March 2003 At 9:15 a.m. in room 60-6-002 1. Chairman's remarks 7. Equipment insurance on site 2. Adoption of the agenda,8. ACCU reporting mechanisms in the different countries 3. Minutes of the previous meeting9. Reports from ACCU representatives on other committees 4. Matters arising10. Users' Office news 5. News from the CERN Management11. Any Other Business 6. CHIS news and follow-up of survey12. Agenda for the next meeting Anyone wishing to raise any points under item 11 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661)NorwayH. Helstrup (73601) Belgium G. Wilquet (74664) Poland Z. Hajduk (7591...

  14. ACCU MEETING

    CERN Multimedia

    Chris Onions

    2002-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 11 September 2002 At 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Health Insurance Questionnaire Host States Relations Service Update on EP Space management Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria R. Tzenov (77958) Czech Republic P. Závada (75877) Denmark A. Waananen (75941) Finland E. Tuominen (71534) France F. Bauer (71247) L. Serin (...

  15. ACCU MEETING

    CERN Multimedia

    2003-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 10 December 2003 At 9:15 a.m. in room 60-6-002 1. Chairman's remarks 8. Report from IT division on Computing matters 2. Adoption of the agenda 9. Young Particle Physicists Association 3. Minutes of the previous meeting 10. Reports from ACCU representatives on other committees 4. Matters arising 11. Users' Office news 5. News from the CERN Management 12. Election of the ACCU Chair 6. Report from the new Director-General 13. Any Other Business 7. CERN's 50th anniversary 14. Agenda for the next meeting Anyone wishing to raise any points under item 13 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Ada...

  16. ACCU MEETING

    CERN Multimedia

    2003-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 5 March 2003 At 9:15 a.m. in room 60-6-002 1. Chairman's remarks 7. Equipment insurance on site 2. Adoption of the agenda 8. ACCU reporting mechanisms in the different countries 3. Minutes of the previous meeting 9. Reports from ACCU representatives on other committees 4. Matters arising 10. Users' Office news 5. News from the CERN Management 11. Any Other Business 6. Health Insurance news and follow-up of survey 12. Agenda for the next meeting Anyone wishing to raise any points under item 11 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Norway H. Helstrup (73601) Belgium G. Wil...

  17. ACCU MEETING

    CERN Multimedia

    2003-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 11 June 2003 At 9:15 a.m. in room 60-6-002 1. Chairman's remarks 7. Reports from ACCU representatives 2. Adoption of the agenda on other committees 3. Minutes of the previous meeting 8. Users' Office news 4. Matters arising 9. Any Other Business 5. News from the CERN Management 10. Agenda for the next meeting 6. Property Protection at CERN Anyone wishing to raise any points under item 9 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Norway H. Helstrup (73601) Belgium G. Wilquet (74664) Poland Z. Hajduk (75917) Bulgaria R. Tsenov (74837) Portugal P. Bordalo (74704) Czech Republic ...

  18. ACCU Meeting

    CERN Multimedia

    2003-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 10 September 2003 At 9:15 a.m. in room 60-6-002 1. Chairman's remarks 8. Registration plans for portables 2. Adoption of the agenda 9. Reports from ACCU representatives 3. Minutes of the previous meeting on other committees 4. Matters arising 10. Users' Office news 5. News from the CERN Management 11. Any Other Business 6. The Press Office 12. Agenda for the next meeting 7. Equal Opportunities Commission Anyone wishing to raise any points under item 11 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): AustriaW. Adam (71661) Norway H. Helstrup (73601) Belgium G. Wilquet (74664) Poland Z. Hajduk (75917) Bulgari...

  19. ACCU MEETING

    CERN Multimedia

    2003-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 10 December 2003 At 9:15 a.m. in room 60-6-002 1. Chairman's remarks 8. Report from IT division on Computing matters 2. Adoption of the agenda 9. Young Particle Physicists Association 3. Minutes of the previous meeting 10. Reports from ACCU representatives on other committees 4. Matters arising 11. Users' Office news 5. News from the CERN Management 12. Election of the ACCU Chair 6. Report from the new Director-General 13. Any Other Business 7. CERN's 50th anniversary 14. Agenda for the next meeting Anyone wishing to raise any points under item 13 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (716...

  20. ACCU MEETING

    CERN Multimedia

    Chris Onions

    2002-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 6 March 2002 At 9:15 a.m. in the Council Chamber Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Follow-up on Space Management Users' Desktop needs PIE procedures Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria R. Tzenov (77958) Czech Republic P. Závada (75877) Denmark A. Waananen (75941) Finland E. Tuominen (71534) France F. Bauer L. Serin (712...

  1. ACCU MEETING

    CERN Multimedia

    Chris Onions

    2002-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 12 June 2002 At 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management PIE procedures CERN Cars EP Electronics Advisory Board Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch   ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria R. Tzenov (77958) Czech Republic P. Závada (75877) Denmark A. Waananen (75941) Finland E. Tuominen (71534) France F. Bauer (71247) L. Serin (71143) Germany H. Kroha...

  2. ACCU MEETING

    CERN Multimedia

    2000-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 13 September 2000 At 10 a.m. in the 6th floor Conference Room, Main Building 1. Chairman's remarks 2. Adoption of the agenda 3. News from the CERN Management 4. Minutes of the previous meeting 5. Matters arising 6. Report from the Scientific Information Policy Board 7. Report from ETT Division: The Press Office 8. Update on Computing Issues 9. Users' Office News 10. Any Other Business 11. Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Secretary in writing via the CERN Users' Office or by e-mail to Bryan Pattison (Secretary). ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets) : Austria G. Neuhofer (74094) Belgium G. Wilquet (74664) Bulgaria R. Tzenov (77958) Czech Republic P. Z vada (75...

  3. ACCU MEETING

    CERN Multimedia

    Bryan Pattison

    2000-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 13 September 2000 At 10 a.m. in the 6th floor Conference Room, Main Building1. Chairman's remarks2. Adoption of the agenda3. News from the CERN Management4. Minutes of the previous meeting5. Matters arising6. Report from the Scientific Information Policy Board7. Report from ETT Division: The Press Office8. Update on Computing Issues9. Users' Office News10. Any Other Business11. Agenda for the next meetingAnyone wishing to raise any points under item 10 is invited to send them to the Secretary in writing via the CERN Users' Office or by e-mail toBryan Pattison(Secretary).ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets) :Austria G. Neuhofer (74094)Belgium G. Wilquet (74664) Bulgaria R. Tzenov (77958)Czech Republic P. Závada (75877)Den...

  4. ACCU MEETING

    CERN Multimedia

    Chris Onions

    2002-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 12 June 2002 At 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management PIE procedures CERN Cars EP Electronics Advisory Board Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch   ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria R. Tzenov (77958) Czech Republic P. Závada (75877) Denmark A. Waananen (75941) Finland E. Tuominen (71534) France F. Bauer (71247) L. Serin (71143) Germany H. Kroha ...

  5. ACCU MEETING

    CERN Multimedia

    PH Department

    2009-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 11 March 2009 At 9:15 a.m. in room 60-6-002 Chairman’s remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management The CERN Press Office An update on Safety at CERN The Burotel project Reports from ACCU representatives on other committees Users’ Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 11 is invited to send them to the Chairman in writing or by e-mail to mailto:Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria G. Walzel () Belgium C. Vander Velde (71539) Bulgaria Czech Republic P. Závada (75877) Denmark...

  6. ACCU MEETING

    CERN Multimedia

    PH Department

    2010-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 10 March 2010 At 9:15 a.m. in room 60-6-002 Chairperson’s remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Report on services from GS department An update on Safety at CERN Reports from ACCU representatives on other committees Users’ Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 10 is invited to send them to the Chairman in writing or by e-mail to Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives on ACCU are (CERN internal telephone numbers in brackets): Austria G. Walzel (76592) Belgium C. Vander Velde (Chairperson) (71539) Bulgaria Czech Republic S. Nemecek (71144) ...

  7. ACCU MEETING

    CERN Multimedia

    PH Department

    2011-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 7 September 2011 at 9:15 a.m. in room 60-6-002   Chairperson's remarks Adoption of the agenda      Minutes of the previous meeting Matters arising       News from the CERN Management Report on services from GS department Report on new CHIS rules Users’ Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 9 is invited to send them to the Chairperson in writing or by e-mail to Michael.Hauschild@cern.ch Michael Hauschild (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria M. Jeitler (76307) Belgium C. Vander Velde (Chairperson)...

  8. ACCU MEETING

    CERN Multimedia

    PH Department

    2009-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 9 September 2009 At 9:15 a.m. in room 60-6-002 1.\tChairman’s remarks 2.\tAdoption of the agenda 3.\tMinutes of the previous meeting 4.\tMatters arising 5.\tNews from the CERN Management 6.\tCode of conduct 7.\tEqual Opportunities at CERN 8.\tAn update on safety at CERN 9.\tThe CERN shuttle service 10.\tReports from ACCU representatives on other committees 11.\tUsers’ Office news 12.\tOther business 13.\tAgenda of the next meeting Anyone wishing to raise any points under item 12 is invited to send them to the Chairman in writing or by e-mail to mailto:Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives on ACCU are (CERN internal telephone numbers in brackets): Austria G. Walzel (76592) Belgium C. Vander Velde (71539) Bulgaria Czech Re...

  9. ACCU MEETING

    CERN Multimedia

    PH Department

    2009-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 10 June 2009At 9:15 a.m. in room 60-6-002 Chairman’s remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management CERN Social Services User services in GS Department An update on Safety at CERN Reports from ACCU representatives on other committees Users’ Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 11 is invited to send them to the Chairman in writing or by e-mail to mailto:Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria - G. Walzel (76592) Belgium - C. Vander Velde (71539) Bulgaria Czech Republic - P. Závada (7587...

  10. ACCU Meeting

    CERN Multimedia

    Chris Onions

    DRAFT Agenda for the meeting to be held on Wednesday 9 December 2009 At 9:15 a.m. in Room 60-6-002 Chairman’s remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Restaurant No. 1 extension An update on Safety at CERN Reports from ACCU representatives on other committees Users’ Office news Election of the ACCU Chair Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 11 is invited to send them to the Chairman in writing or by e-mail to Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria G. Walzel (76592) Belgium C. Vander Velde (71539) Bulgaria Czech Republic P. Záv...

  11. ACCU MEETING

    CERN Multimedia

    PH Department

    2009-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 9 September 2009 At 9:15 a.m. in room 60-6-002 1.\tChairman’s remarks 2.\tAdoption of the agenda 3.\tMinutes of the previous meeting 4.\tMatters arising 5.\tNews from the CERN Management 6.\tCode of Conduct 7.\tEqual Opportunities at CERN 8.\tAn update on Safety at CERN 9.\tThe CERN shuttle service 10.\tReports from ACCU representatives on other committees 11.\tUsers’ Office news 12.\tAny Other Business 13.\tAgenda for the next meeting Anyone wishing to raise any points under item 12 is invited to send them to the Chairman in writing or by e-mail to mailto:Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria G. Walzel (76592) Belgium C. Vander Velde (71539) Bulgaria Cze...

  12. ACCU MEETING

    CERN Multimedia

    PH Department

    2009-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 11 March 2009 At 9:15 a.m. in room 60-6-002 1.\tChairman’s remarks 2.\tAdoption of the agenda 3.\tMinutes of the previous meeting 4.\tMatters arising 5.\tNews from the CERN Management 6.\tThe CERN Press Office 7.\tAn update on Safety at CERN 8.\tThe Burotel project 9.\tReports from ACCU representatives on other committees 10.\tUsers’ Office news 11.\tAny Other Business 12.\tAgenda for the next meeting Anyone wishing to raise any points under item 11 is invited to send them to the Chairman in writing or by e-mail to mailto:Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria G. Walzel () Belgium C. Vander Velde (71539) Bulgaria C...

  13. ACCU Meeting

    CERN Document Server

    Chris Onions

    2006-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 14 June 2006 At 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Car sharing pilot project The CERN Document Server : the portal to Open Access Videoconferencing and collaborative tools at CERN Reports from ACCU representatives on other committees Users' Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 11 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria Czech Republic P. Závada (7...

  14. ACCU Meeting

    CERN Document Server

    Chris Onions

    2006-01-01

    DRAFT Agenda for the meeting to be held on Wednesday 14 June 2006 At 9:15 a.m. in room 60-6-002 Chairman's remarks Adoption of the agenda Minutes of the previous meeting Matters arising News from the CERN Management Car sharing pilot project The CERN Document Server : the portal to Open Access Videoconferencing and collaborative tools at CERN Reports from ACCU representatives on other committees Users'Office news Any Other Business Agenda for the next meeting Anyone wishing to raise any points under item 11 is invited to send them to the Chairman in writing or by e-mail to Christopher.Onions@cern.ch Chris Onions (Secretary) ACCU is the forum for discussion between the CERN Management and the representatives of CERN Users to review the practical means taken by CERN for the work of Users of the Laboratory. The User Representatives to ACCU are (CERN internal telephone numbers in brackets): Austria W. Adam (71661) Belgium G. Wilquet (74664) Bulgaria Czech Republic P. Závada (75877) ...

  15. Advantages on dry interim storage for spent nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Romanato, L.S. [Centro Tecnologico da Marinha em Sao Paulo, Av. Professor Lineu Prestes 2468, 05508-900 Sao Paulo (Brazil); Rzyski, B.M. [IPEN/ CNEN-SP, 05508-000 Sao Paulo (Brazil)]. e-mail: romanato@ctmsp.mar.mil.br

    2006-07-01

    When the nuclear fuel lose its ability to efficiently create energy it is removed from the core reactor and moved to a storage unit waiting for a final destination. Generally, the spent nuclear fuel (SNF) remains inside concrete basins with water within the reactors facility for the radioactive activity decay. Water cools the generated heat and shields radioactivity emissions. After some period of time in water basins the SNF can be sent to a definitive deposition in a geological repository and handled as radioactive waste or to reprocessing installations, or still wait for a future solution. Meanwhile, SNF remains stored for a period of time in dry or wet installations, depending on the method adopted by the nuclear power plant or other plans of the country. In many SNF wet storage sites the capacity can be fulfilled very quickly. If so, additional area or other alternative storage system should be given. There are many options to provide capacity increase in the wet storage area, but dry storages are worldwide preferred since it reduces corrosion concerns. In the wet storage the temperature and water purity should be constantly controlled whereas in the dry storage the SNF stands protected in specially designed canisters. Dry interim storages are practical and approved in many countries especially that have the 'wait and see' philosophy (wait to see new technologies development). This paper shows the advantages of dry interim storages sites in comparison with the wet ones and the nowadays problems as terrorism. (Author)

  16. Climate change : we are at risk : interim report

    International Nuclear Information System (INIS)

    Oliver, D.; Wiebe, J.

    2003-06-01

    Between November 2002 and May 2003 the Standing Senate Committee on Agriculture and Forestry travelled across Canada to hear the views of farmer organizations, rural associations, ecotourism groups and environmental organizations regarding concerns about climate change and the impact it may have on the agriculture and forestry sectors and rural communities. The Committee also examined potential adaptation strategies focusing on primary production, practices, technologies, ecosystems and other related areas. Farmers and forest operators are already facing changes in market conditions, domestic regulations, trade policies and technology. This interim report expressed the concerns of farmers and forest operators. It includes a review of the Saguenay flood of 1996, the Red River flood of 1997, the ice storm of 1998, and droughts since 1999. It also includes a discussion on climate change and its biophysical and economic effects on agriculture, forestry, water resources, rural communities, and Aboriginal communities. This interim report also briefly outlines the Kyoto Protocol, the emissions trading system, and the decarbonization of global energy systems. It emphasized the need for integrated research and government policies and programs that encourage adaptation to climate change. The final report will be released in October 2003 and will provide specific recommendations to ensure that Canada responds to the concerns of farmers and forest operators and to ensure continued prosperity in these sectors. refs., figs

  17. Nuclear waste: Is there a need for federal interim storage

    International Nuclear Information System (INIS)

    1989-01-01

    The Congress created the Monitored Retrievable Storage Review Commission to provide a report on the need for a Federal monitored retrievable storage facility (MRS) as part of the Nation's nuclear waste management system. The Commission concludes that the MRS as presently described in the law, which links the capacity and schedule of operation of the MRS to a permanent geologic repository, cannot be justified. The Commission finds, however, that while no single factor would favor an MRS over the No-MRS option, cumulatively the advantages of an MRS would justify the building of an MRS if: there were no linkages between the MRS and the repository; the MRS could be constructed at an early date; and the opening of the repository were delayed considerably beyond its presently scheduled date of operation. The Commission therefore recommends that the Congress take the following actions: Authorize construction of a Federal Emergency Storage facility with a capacity limit of 2,000 metric tons of uranium; Authorize construction of a User-Funded Interim Storage facility with a capacity limit of 5,000 metric tons of uranium; Reconsider the subject of interim storage by the year 2000

  18. Glass packages in interim storage; Les verres dans les stockages

    Energy Technology Data Exchange (ETDEWEB)

    Jacquet-Francillon, N

    1994-10-01

    This report summarize the current state of knowledge concerning the behavior of type C waste packages consisting of vitrified high-level solutions produced by reprocessing spent fuel. The composition and the physical and chemical properties of the feed solutions are reviewed, and the vitrification process is described. Sodium alumino-borosilicate glass compositions are generally employed - the glass used at la Hague for LWR fuel solutions, for example, contains 45 % SiO{sub 2}. The major physical, chemical, mechanical and thermal properties of the glass are reviewed. In order to allow their thermal power to diminish, the 3630 glass packages produced (as of January 1993) in the vitrification facilities at Marcoule and La Hague are placed in interim storage for several decades. The actual interim storage period has not been defined, as it is closely related to the concept and organization selected for the final destination of the packages: a geological repository. The glass behavior under irradiation is described. Considerable basic and applied research has been conducted to assess the aqueous leaching behavior of nuclear containment glass. The effects of various repository parameters (temperature, flow rate, nature of the environmental materials) have been investigated. The experimental findings have been used to specify a model describing the kinetics of aqueous corrosion of the glass. More generally all the ``source term`` models developed in France by the CEA or by ANDRA are summarized. (author). 152 refs., 33 figs.

  19. Safety of Long-term Interim Storage Facilities - Workshop Proceedings

    International Nuclear Information System (INIS)

    2014-01-01

    The objective of this workshop was to discuss and review current national activities, plans and regulatory approaches for the safety of long term interim storage facilities dedicated to spent nuclear fuel (SF), high level waste (HLW) and other radioactive materials with prolonged storage regimes. It was also intended to discuss results of experiments and to identify necessary R and D to confirm safety of fuel and cask during the long-term storage. Safety authorities and their Technical Support Organisation (TSO), Fuel Cycle Facilities (FCF) operating organisations and international organisations were invited to share information on their approaches, practices and current developments. The workshop was organised in an opening session, three technical sessions, and a conclusion session. The technical sessions were focused on: - National approaches for long term interim storage facilities; - Safety requirements, regulatory framework and implementation issues; - Technical issues and operational experience, needs for R and D. Each session consisted of a number of presentations followed by a panel discussion moderated by the session Chairs. A summary of each session and subsequent discussion that ensued are provided as well as a summary of the results of the workshop with the text of the papers given and presentations made

  20. Advantages on dry interim storage for spent nuclear fuel

    International Nuclear Information System (INIS)

    Romanato, L.S.; Rzyski, B.M.

    2006-01-01

    When the nuclear fuel lose its ability to efficiently create energy it is removed from the core reactor and moved to a storage unit waiting for a final destination. Generally, the spent nuclear fuel (SNF) remains inside concrete basins with water within the reactors facility for the radioactive activity decay. Water cools the generated heat and shields radioactivity emissions. After some period of time in water basins the SNF can be sent to a definitive deposition in a geological repository and handled as radioactive waste or to reprocessing installations, or still wait for a future solution. Meanwhile, SNF remains stored for a period of time in dry or wet installations, depending on the method adopted by the nuclear power plant or other plans of the country. In many SNF wet storage sites the capacity can be fulfilled very quickly. If so, additional area or other alternative storage system should be given. There are many options to provide capacity increase in the wet storage area, but dry storages are worldwide preferred since it reduces corrosion concerns. In the wet storage the temperature and water purity should be constantly controlled whereas in the dry storage the SNF stands protected in specially designed canisters. Dry interim storages are practical and approved in many countries especially that have the 'wait and see' philosophy (wait to see new technologies development). This paper shows the advantages of dry interim storages sites in comparison with the wet ones and the nowadays problems as terrorism. (Author)