WorldWideScience

Sample records for safety 2007-2010 interim

  1. 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.)

  2. 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

  3. 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.

  4. 33 CFR 96.360 - Interim Safety Management Certificate: what is it and when can it be used?

    Science.gov (United States)

    2010-07-01

    ...? § 96.360 Interim Safety Management Certificate: what is it and when can it be used? (a) A responsible... 33 Navigation and Navigable Waters 1 2010-07-01 2010-07-01 false Interim Safety Management Certificate: what is it and when can it be used? 96.360 Section 96.360 Navigation and Navigable Waters COAST...

  5. Safety of laboratories, plants, facilities being dismantled, waste processing, interim storage and disposal facilities. Lessons learned from events reported in 2009 and 2010

    International Nuclear Information System (INIS)

    2013-01-01

    This report presents the cross-disciplinary analysis performed by IRSN relating to significant events reported to the French Nuclear Safety Authority (ASN) during 2009 - 2010 for LUDD-type facilities (laboratories, plants, facilities being dismantled, and waste processing, interim storage and disposal facilities). It constitutes a follow-up to DSU Report 215 published in December 2009, relating to events reported to ASN during 2005 to 2008. The main developments observed since the analysis presented in that report have been underlined here, in order to highlight improvements, opportunities for progress and the main areas requiring careful attention. The present report is a continuation of DSU Report 215. Without claiming to be exhaustive, it presents lessons from IRSN's cross-disciplinary analysis of events reported to ASN during 2009 and 2010 at LUDD facilities while highlighting major changes from the previous analysis in order to underline improvements, areas where progress has been made, and main points for monitoring. The report has four sections: - the first gives a brief introduction to the various kinds of LUDD facilities and highlights changes with DSU Report 215; - the second provides a summary of major trends involving events reported to ASN during 2007-2010 as well as overall results of consequences of events reported during 2009 and 2010 for workers, the general public and the environment; - the third section gives a cross-disciplinary analysis of significant events reported during 2009 and 2010, performed from two complementary angles (analysis of main types of events grouped by type of risk and analysis of generic causes). Main changes from the analysis given in DSU Report 215 are considered in detail; - the last section describes selected significant events that occurred in 2009 and 2010 in order to illustrate the cross-disciplinary analysis with concrete examples. IRSN will publish this type of report periodically in coming years in order to

  6. 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

  7. 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.

  8. 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.

  9. 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

  10. 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

  11. 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

  12. 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.

  13. 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)

  14. 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

  15. 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

  16. 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.

  17. The Australian radiation protection and nuclear safety agency megavoltage photon thermoluminescence dosimetry postal audit service 20072010

    International Nuclear Information System (INIS)

    Oliver, C.P.; Butler, D.J.; Webb, D.V.

    2012-01-01

    The Australian radiation protection and nuclear safety agency (ARPANSA) has continuously provided a level 1 mailed thermoluminescence dosimetry audit service for megavoltage photons since 2007. The purpose of the audit is to provide an independent verification of the reference dose output of a radiotherapy linear accelerator in a clinical environment. Photon beam quality measurements can also be made as part of the audit in addition to the output measurements. The results of all audits performed between 2007 and 2010 are presented. The average of all reference beam output measurements calculated as a clinically stated dose divided by an ARPANSA measured dose is 0.9993. The results of all beam quality measurements calculated as a clinically stated quality divided by an ARPANSA measured quality is 1.0087. Since 2011 the provision of all auditing services has been transferred from the Ionizing Radiation Standards section to the Australian Clinical Dosimetry Service (ACDS) which is currently housed within ARPANSA.

  18. 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

  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. Toward introduction of risk informed safety regulation. Nuclear Safety Commission taskforce's interim report

    International Nuclear Information System (INIS)

    2006-01-01

    Nuclear Safety Commission's taskforce on 'Introduction of Safety Regulation Utilizing Risk Information' completed the interim report on its future subjects and directions in December 2005. Although current safety regulatory activities have been based on deterministic approach, this report shows the risk informed approach is expected to be very useful for making nuclear safety regulation and assurance activities reasonable and also for appropriate allocation of regulatory resources. For introduction of risk informed regulation, it also recommends pileups of experiences with gradual introduction and trial of the risk informed approach, improvement of plant maintenance rules and regulatory requirements utilizing risk information, and establishment of framework to assure quality of risk evaluation. (T. Tanaka)

  2. 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

  3. 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)

  4. 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

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

    International Nuclear Information System (INIS)

    Stahl, S.M.

    1994-01-01

    This report provides results of a review of recently completed safety analyses related to hazards associated with Interim Stabilization of Single analyses related to hazards included oh the Hanford Site Waste Tank-Watch Shell Tanks (SSTs) that are included on the Hanford List. The purpose of the review was to identify and summarize conclusions regarding the safety of interim stabilization of Watch List SSTs, and to highlight applicable limitations, restrictions, and controls. The scope of this review was restricted to SSTs identified List in the categories of flammable gas ferrocyanide, and organic salts. High heat tanks were not included in the scope. A Watch List tank is defined as an underground storage tank containing waste that requires special safety precautions because it may have a serious potential for release of high level radioactive waste because of uncontrolled increases in temperature or pressure. Special restrictions have been placed on these tanks

  6. Move smoothly to Office 2007 or 2010

    CERN Multimedia

    CERN. Geneva

    2011-01-01

    Overview of the user interface of Office 2007 and Office 2010 programs: Word, Excel, Powerpoint and Outlook. Special attention will be drawn to: changes of the user interface as compared with Office 2003, new features that improve user-productivity. At the beginning of the presentation, the demonstrations will focus on Office 2007, which is available on both Windows XP and Windows 7. Towards the end, the demonstrations will focus on Office 2010, which will soon become the default version of Office on Windows 7. Video and slides of the presentation: http://indico.cern.ch/conferenceDisplay.py?confId=95532-->

  7. 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...

  8. 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)

  9. 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)

  10. Suicide in Pretoria: A retrospective review, 2007 - 2010

    Directory of Open Access Journals (Sweden)

    Cornelia Engelbrecht

    2017-08-01

    Full Text Available Background. The World Health Organization has declared suicide a global ealth crisis, predicting that ~1.53 million people will commit suicide annually by 2020. Objective. A study from South Africa reviewed 1 018 suicide cases in Pretoria over 4 years (1997 - 2000. Our study was undertaken to establish whether there have been substantial changes in the profile of suicide victims who died in Pretoria a decade later. Methods. Case records at the Pretoria Medico-Legal Laboratory were reviewed retrospectively from 2007 to 2010. Results. A total of 957 suicide cases were identified. Hanging was the most common method of suicide, followed by self-inflicted firearm injury. The true incidence of suicidal intake of prescription drugs/medication was difficult to determine, because of a backlog at the state toxicology laboratories. White males and females appeared to be over-represented among suicide victims, but there has been an increase in suicide among blacks. There seems to have been a substantial decrease in the use of firearms to commit suicide – possibly reflecting a positive outcome of gun control legislation that has been introduced in the interim. Conclusion. Suicide continues to constitute almost 10% of all fatalities admitted to the Pretoria Medico-Legal Laboratory, confirming suicide as a major cause of mortality in our society. Further research is needed to clarify the profile of suicidal deaths, with a view to informing resource allocation and to improve preventive strategies.

  11. 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...

  12. Safety Consideration for a Wet Interim Spent Fuel Store at Conceptual Design Stage

    International Nuclear Information System (INIS)

    Astoux, Marion

    2014-01-01

    EDF Energy plans to build and operate two UK EPRs at the Hinkley Point C (HPC) site in Somerset, England. Spent fuel from the UK EPRs will need to be managed from the time it is discharged from the reactor until it is ultimately disposed of and this will involve storing the spent fuel for a period in the fuel building and thereafter in a dedicated interim facility until it can be emplaced within the UK Geological Disposal Facility. EDF Energy has proposed that this interim store should be located on the Hinkley Point site which is consistent with UK policy. This Interim Spent Fuel Store (ISFS) will have the capability to store for at least one hundred years the spent fuel arising from the operation of the two EPR units (sixty years operation). Therefore, specificities regarding the lifetime of the facility have to be accounted for its design. The choice of interim storage technology was considered in some depth for the HPC project and wet storage (pool) was selected. The facility is currently at conceptual design stage, although its construction will be part of main site construction phase. Safety functions and safety requirements for this storage facility have been defined, in compliance with WENRA 'Waste and Spent Fuel Storage - Safety Reference Level Report' and IAEA Specific Safety Guide no. 15 'Storage of Spent Nuclear Fuel'. EDF technical know-how, operational feedback on existing storage pools, UK regulatory context and Fukushima experience feedback have also been accounted for. Achievement of the safety functions as passively as reasonably practicable is a key issue for the design, especially in accident situations. Regarding lifetime aspects, ageing management of equipments, optimisation of the refurbishment, climate change, passivity of the facility, and long-term achievement of the safety functions are among the subjects to consider. Adequate Operational Limits and Conditions will also have to be defined, to enable the long-term achievement of the safety

  13. 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...

  14. Evaluation of the Finnish nuclear safety research program 'SAFIR2010'

    International Nuclear Information System (INIS)

    2010-01-01

    A panel of three members has been asked by the Ministry of Employment and the Economy (MEE) to evaluate SAFIR2010, the Finnish research program on nuclear power plant safety. The program was established for the period 2007-2010 to help maintain expertise in nuclear safety, to integrate young people into the research in order to help assure the future availability of expertise, and to support international collaborations. The program is directed by a Steering Group, appointed by MEE, with representatives from all organizations involved with nuclear safety in Finland. SAFIR2010 has consisted of approximately 30 projects from year to year that fall into eight subject areas: 1. Organization and human factors 2. Automation and control room 3. Fuel and reactor physics 4. Thermal hydraulics 5. Severe accidents 6. Structural safety of reactor circuit 7. Construction safety 8. Probabilistic safety analysis (PSA) For each of these areas there are Reference Groups that provide oversight of the projects within their jurisdiction. The panel carried out its evaluation by reviewing copies of relevant documents and, during a one-week period 17-22 January 2010, meeting with key individuals. The results of the panel are provided as general conclusions, responses to questions posed by MEE, challenges and recommendations and comments on specific projects in each subject area. The general conclusions reflect the panel's view that SAFIR2010 is meeting its objectives and carrying out quality research. The questions addressed are: (a.) Are the achieved results in balance with the funding? Are the results exploited efficiently in practice? (b.) How well does the expertise cover the field? Is the entire SAFIR2010 programme balanced to all different fields in nuclear safety? Does it raise efficiently new experts? (c.) Have the 2006 evaluation results been implemented successfully into SAFIR2010 program? (d.) Challenges and recommendations. In general the panel was very positive about SAFIR

  15. Final hazard classification and auditable safety analysis for the 105-C Reactor Interim Safe Storage Project

    International Nuclear Information System (INIS)

    Rodovsky, T.J.; Larson, A.R.; Dexheimer, D.

    1996-12-01

    This document summarizes the inventories of radioactive and hazardous materials present in the 105-C Reactor Facility and the operations associated with the Interim Safe Storage Project which includes decontamination and demolition and interim safe storage of the remaining facility. This document also establishes a final hazard classification and verifies that appropriate and adequate safety functions and controls are in place to reduce or mitigate the risk associated with those operations

  16. Psychotherapy Utilization Among Rural and Urban Veterans From 2007 to 2010.

    Science.gov (United States)

    Mott, Juliette M; Grubbs, Kathleen M; Sansgiry, Shubhada; Fortney, John C; Cully, Jeffrey A

    2015-01-01

    This study evaluated change in rural and urban veterans' psychotherapy use during a period of widespread effort within the Veterans Health Administration (VHA) to engage rural veterans in mental health care. National VHA administrative databases were queried for patients receiving a new diagnosis of depression, anxiety, or posttraumatic stress disorder in fiscal years (FY) 2007 and 2010. Using the US Department of Agriculture Rural-Urban Continuum Codes, we identified urban (FY 2007: n = 192,347; FY 2010: n = 231,471) and rural (FY 2007: n = 72,923; FY 2010: n = 81,905) veterans. Veterans' psychotherapy use during the 12 months following diagnosis was assessed. From FY 2007 to 2010, the proportion of veterans receiving any psychotherapy increased from 17% to 22% for rural veterans and 24% to 28% for urban veterans. Rural veterans were less likely to receive psychotherapy across both fiscal years; however, the magnitude of this disparity decreased significantly from 2007 (odds ratio [OR] = 1.51) to 2010 (OR = 1.41). Similarly, although urban veterans received more psychotherapy sessions, urban-rural disparities in the receipt of 8 or more psychotherapy sessions decreased over the study period (2007: OR = 2.32; 2010: OR = 1.69). Rural and urban veterans are increasingly making use of psychotherapy, and rural-urban gaps in psychotherapy use are shrinking. These improvements suggest that recent VHA efforts to engage rural veterans in care have been successful at reducing differences between rural and urban veterans with respect to access and engagement in psychotherapy. © 2014 National Rural Health Association.

  17. 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

  18. 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)

  19. Review of SKB's interim report of SR-Can: SKI's and SSI's evaluation of SKB's up-dated methodology for safety assessment

    International Nuclear Information System (INIS)

    Dverstorp, Bjoern; Moberg, Leif; Wiebert, Anders; Xu Shulan; Stroemberg, Bo; Kautsky, Fritz; Lilja, Christina; Simic, Eva; Sundstroem, Benny; Toverud, Oeivind

    2005-07-01

    This report presents the findings of a review of the Swedish Nuclear Fuel and Waste Management Co.'s (SKB) interim report of the safety assessment SR-Can (SKB TR 04-11), conducted by the Swedish Radiation Protection Authority (SSI) and the Swedish Nuclear Power Inspectorate (SKI). SKB's interim report describes and exemplifies the safety assessment methodology that SKB plans to use in the oncoming licence applications for an encapsulation plant and a final repository for spent nuclear fuel. The authorities' review takes into account the findings of an international peer review of SKB's interim report. The authorities conclude that SKB has improved its safety assessment methodology in several aspects compared to earlier safety reports. Among other things the authorities commend SKB for giving a comprehensive account of relevant regulations and guidance, and for the systematic approach to identification and documentation of features, events and processes that need to be considered in the safety assessment. However, the authorities also conclude that important parts of SKB's method need to be further developed before they are mature enough to be used as a basis for a license application. The authorities' overall assessment is summarised in chapter 8 of this report

  20. 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.

  1. Interim main report of the safety assessment SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, Allan [and others

    2004-08-01

    This document is an interim report on the safety assessment SR-Can (SR in the acronym stands for Safety Report and Can is short for canister). The final SR-Can report will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of the present interim report is to demonstrate the methodology for safety assessment so that it can be reviewed before it is used in a license application. The assessment relates to the KBS-3 disposal concept in which copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. Preliminary data from the Forsmark site, presently being investigated by SKB as one of the candidate for a KBS-3 repository are used to some extent as examples. However, the collected data are yet too sparse to allow an evaluation of safety for this site. An important aim of this report is to demonstrate the proper handling of requirements on the safety assessment in applicable regulations. Therefore, regulations issued by the Swedish Nuclear Power Inspectorate and the Swedish Radiation Protection Authority are duplicated in an Appendix. The principal acceptance criterion requires that 'the annual risk of harmful effects after closure does not exceed 10{sup -6} for a representative individual in the group exposed to the greatest risk'. 'Harmful effects' refer to cancer and hereditary effects. Following the introductory chapter 1, this report outlines the methodology for the SR-Can assessment in chapter 2, and presents in chapters 3, 4 and 5 the initial state of the system and the plans and methods for handling external influences and internal processes, respectively. Function indicators are introduced in chapter 6 and a preliminary evaluation of these is given in chapter 7. The material presented in the first seven chapters is utilised in the scenario selection in chapter 8

  2. Interim main report of the safety assessment SR-Can

    International Nuclear Information System (INIS)

    Hedin, Allan

    2004-08-01

    This document is an interim report on the safety assessment SR-Can (SR in the acronym stands for Safety Report and Can is short for canister). The final SR-Can report will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of the present interim report is to demonstrate the methodology for safety assessment so that it can be reviewed before it is used in a license application. The assessment relates to the KBS-3 disposal concept in which copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. Preliminary data from the Forsmark site, presently being investigated by SKB as one of the candidate for a KBS-3 repository are used to some extent as examples. However, the collected data are yet too sparse to allow an evaluation of safety for this site. An important aim of this report is to demonstrate the proper handling of requirements on the safety assessment in applicable regulations. Therefore, regulations issued by the Swedish Nuclear Power Inspectorate and the Swedish Radiation Protection Authority are duplicated in an Appendix. The principal acceptance criterion requires that 'the annual risk of harmful effects after closure does not exceed 10 -6 for a representative individual in the group exposed to the greatest risk'. 'Harmful effects' refer to cancer and hereditary effects. Following the introductory chapter 1, this report outlines the methodology for the SR-Can assessment in chapter 2, and presents in chapters 3, 4 and 5 the initial state of the system and the plans and methods for handling external influences and internal processes, respectively. Function indicators are introduced in chapter 6 and a preliminary evaluation of these is given in chapter 7. The material presented in the first seven chapters is utilised in the scenario selection in chapter 8. Hydrogeological

  3. Interim FEP report for the safety assessment SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Skagius, Kristina (ed.) [Kemakta Konsult AB, Stockholm (Sweden)

    2004-08-01

    This report describes the work with identification and structuring of features, events and processes (FEPs) that has been carried out within the scope of the SR-Can safety assessment up to the time of the interim reporting of the project. The overall objective of the work is to develop a database of features, events and processes in a format that would facilitate both a systematic analysis of FEPs and documentation of the FEP analysis as well as facilitate revisions and updates to be made in connection with new safety assessments. This overall objective also includes the development of procedures for a systematic FEP analysis as well as to apply these procedures in order to arrive at an SR-Can version of the FEP database. The work started by implementing the content of the SR 97 Process report into a database format suitable for import and processing of FEP information from other sources. The SR 97 version of the database was systematically audited against the NEA database with Project FEPs, version 1.2. In addition, an earlier audit of the SR 97 process report against the interaction matrices developed for a deep repository of the KBS-3 type was revisited and updated. Relevant FEPs from the audit were sorted into three main categories in the SR-Can database i) FEPs related to the initial states of the repository system, ii) FEPs related to internal processes of the repository system, and iii) FEPs related to external impacts on the repository system. These groups of FEPs were further processed for making decisions on how to handle these FEPs in the assessment. Biosphere processes were not included in the SR 97 Process report and there is thus not the same basis for updating these descriptions as for the engineered barriers and the geosphere. All biosphere FEPs from the audit have therefore been compiled in a single category in the database, but remain to be further handled. FEPs were also categorised as irrelevant or as being related to methodology on a general

  4. Interim FEP report for the safety assessment SR-Can

    International Nuclear Information System (INIS)

    Skagius, Kristina

    2004-08-01

    This report describes the work with identification and structuring of features, events and processes (FEPs) that has been carried out within the scope of the SR-Can safety assessment up to the time of the interim reporting of the project. The overall objective of the work is to develop a database of features, events and processes in a format that would facilitate both a systematic analysis of FEPs and documentation of the FEP analysis as well as facilitate revisions and updates to be made in connection with new safety assessments. This overall objective also includes the development of procedures for a systematic FEP analysis as well as to apply these procedures in order to arrive at an SR-Can version of the FEP database. The work started by implementing the content of the SR 97 Process report into a database format suitable for import and processing of FEP information from other sources. The SR 97 version of the database was systematically audited against the NEA database with Project FEPs, version 1.2. In addition, an earlier audit of the SR 97 process report against the interaction matrices developed for a deep repository of the KBS-3 type was revisited and updated. Relevant FEPs from the audit were sorted into three main categories in the SR-Can database i) FEPs related to the initial states of the repository system, ii) FEPs related to internal processes of the repository system, and iii) FEPs related to external impacts on the repository system. These groups of FEPs were further processed for making decisions on how to handle these FEPs in the assessment. Biosphere processes were not included in the SR 97 Process report and there is thus not the same basis for updating these descriptions as for the engineered barriers and the geosphere. All biosphere FEPs from the audit have therefore been compiled in a single category in the database, but remain to be further handled. FEPs were also categorised as irrelevant or as being related to methodology on a general

  5. Nuclear power and nuclear safety 2007; Kernekraft og nuklear sikkerhed 2007

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, B.; OElgaard, P.L. (eds.); Kampmann, D.; Majborn, B.; Nonboel, E.; Nystrup, P.E.

    2008-05-15

    The report is the fifth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2007 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events of nuclear power, and international relations and conflicts. (LN)

  6. Interim main report of the safety assessment SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, Allan (ed.) [and others

    2004-08-01

    This document is an interim report on the safety assessment SR-Can (SR in the acronym stands for Safety Report and Can is short for canister). The final SR-Can report will support SKB's application to build an Encapsulation plant for spent nuclear fuel and is to be produced in 2006. The purpose of the present interim report is to demonstrate the methodology for safety assessment so that it can be reviewed before it is used in a license application. The assessment relates to the KBS-3 disposal concept in which copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. Preliminary data from the Forsmark site, presently being investigated by SKB as one of the candidate for a KBS-3 repository are used to some extent as examples. However, the collected data are yet too sparse to allow an evaluation of safety for this site. An important aim of this report is to demonstrate the proper handling of requirements on the safety assessment in applicable regulations. Therefore, regulations issued by the Swedish Nuclear Power Inspectorate and the Swedish Radiation Protection Authority are duplicated in an Appendix. The principal acceptance criterion requires that 'the annual risk of harmful effects after closure does not exceed 10{sup -6} for a representative individual in the group exposed to the greatest risk'. 'Harmful effects' refer to cancer and hereditary effects. Following the introductory chapter 1, this report outlines the methodology for the SR-Can assessment in chapter 2, and presents in chapters 3, 4 and 5 the initial state of the system and the plans and methods for handling external influences and internal processes, respectively. Function indicators are introduced in chapter 6 and a preliminary evaluation of these is given in chapter 7. The material presented in the first seven chapters is utilised in the scenario selection

  7. Criticality safety evaluation for long term storage of FFTF fuel in interim storage casks

    International Nuclear Information System (INIS)

    Richard, R.F.

    1995-01-01

    It has been postulated that a degradation phenomenon, referred to as ''hot cell rot'', may affect irradiated FFTF mixed plutonium-uranium oxide (MOX) fuel during dry interim storage. ''Hot cell rot'' refers to a variety of phenomena that degrade fuel pin cladding during exposure to air and inert gas environments. It is thought to be a form of caustic stress corrosion cracking or environmentally assisted cracking. Here, a criticality safety analysis was performed to address the effect of the ''hot cell rot'' phenomenon on the long term storage of irradiated FFTF fuel in core component containers. The results show that seven FFTF fuel assemblies or six Ident-69 pin containers stored in core component containers within interim storage casks will remain safely subcritical

  8. 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...

  9. 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...

  10. 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.

  11. Status of safety at Areva group facilities. 2007 annual report

    International Nuclear Information System (INIS)

    2007-01-01

    This report describes the status of nuclear safety and radiation protection in the facilities of the AREVA group and gives information on radiation protection in the service operations, as observed through the inspection programs and analyses carried out by the General Inspectorate in 2007. Having been submitted to the group's Supervisory Board, this report is sent to the bodies representing the personnel. Content: 1 - A look back at 2007 by the AREVA General Inspector: Visible progress in 2007, Implementation of the Nuclear Safety Charter, Notable events; 2 - Status of nuclear safety and radiation protection in the nuclear facilities and service operations: Personnel radiation protection, Event tracking, Service operations, Criticality control, Radioactive waste and effluent management; 3 - Performance improvement actions; 4 - Description of the General Inspectorate; 5 - Glossary

  12. 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...

  13. Pre-conceptual study on the review framework for the radiation shielding safety of the PWR spent fuel cask interim storage in Korea

    International Nuclear Information System (INIS)

    Kim, Byeong-Soo; Jeong, Jae-Hak; Jeong, Chan-Woo

    2006-01-01

    In Korea, 20 nuclear power plants are in operation and lots of spent fuels are on the onsite storage. The onsite storage capacity in Korea is supposed to be full around at the year of 2016 and interim storage facilities could be considered to be constructed before 2016. A review framework to evaluate the radiation shielding safety of the interim storage facilities is developed in this study. It includes acceptance criteria, review procedures and activities of independent analyses. A case study is performed to apply the review framework. Modeling the review reference storage, evaluating the source terms and calculating the photon fluxes are performed. It is shown that the application of the review framework could satisfy the regulatory demand that would arise in the near future in the review area of the radiation shielding safety of the interim storage in Korea. (author)

  14. 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...

  15. 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

  16. Annual safety research report, JFY 2010

    International Nuclear Information System (INIS)

    2011-09-01

    In the safety infrastructure research working group report, 'the effective conducting of nuclear safety infrastructure research', published by METI in March 2010, the roles of regulatory agencies and JNES and their cooperation, and the research road map for nuclear safety regulation researches were summarized. As for the regulatory issues the governments or JNES considered necessary, JNES had compiled' safety research plan' in respective research areas necessary for solving the regulatory issues (safety research needs) and was conducting safety research to obtain the results, etc. Safety research areas, subjects and research projects were as follows: design review of nuclear power plant (4 subjects and each subject having several research projects totaled 19), control management of nuclear power plant (3 subjects and each subject having several research projects totaled 11), nuclear fuel cycle (2 subjects and each subject having several research projects totaled 5), nuclear fuel cycle backend (2 subjects and each subject having several research projects totaled 6), nuclear emergency preparedness and response (3 subjects and each subject having several research projects totaled 5) and bases of nuclear safety technology (3 subjects and each subject having several research projects totaled 7). In JFY 2010, JNES worked on the 53 research projects of 17 subjects in 6 areas as safety researches. This annual safety research report summarized respective achievements and stage of regulatory tools necessary for solving regulatory issues according to the safety research plan, JFY 2010 Edition as well as the situation of the reflection for the safety regulations. (T. Tanaka)

  17. An Assessment of SKB's Performance Assessment Calculations in the Interim Main Report for the Safety Assessment SR-Can

    International Nuclear Information System (INIS)

    Maul, Philip; Robinson, Peter

    2005-03-01

    SKB have published their Interim Main Report of the safety assessment SR-Can, which is intended to establish the framework for what will be submitted in 2006 in support of a licence application for construction of the spent fuel encapsulation plant. This follows on from the SR-Can Planning Document published in 2003. The purpose of the Interim Report is stated to be to demonstrate the methodology that will be used for safety assessment. The present report evaluates the information provided in the Interim SR-Can Report that is relevant to the Performance Assessment (PA) calculations that SKB intend to undertake, using independent calculations to facilitate this process. SKB consider that the primary safety function is to isolate completely the fuel within the canisters over the entire assessment period. Should a canister be damaged, the secondary safety function is to ensure that any release is retarded and dispersed sufficiently to ensure that concentrations levels in the accessible environment cannot cause unacceptable consequences. In this report PA calculations are considered to include both a high-level representation of the evolution of the system (relevant to the primary safety function), and any subsequent radionuclide transport (relevant to the secondary safety function). The main conclusions drawn are: 1. The effects of climate evolution on engineered barriers have not been analysed in detail in the Interim Report, and this limits the usefulness of the preliminary calculations that have been undertaken. 2. A key aspect of SKB's approach is the use of an integrated near-field evolution model. The information provided on this model demonstrates its capability efficiently to reproduce calculations from individual process models, but insufficient information is given at the present time to justify statements about interactions between processes. In particular it is assumed that relatively short term thermal and resaturation processes do not affect the

  18. Regulatory oversight report 2010 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    2011-06-01

    Acting as the regulatory body of the Swiss Confederation, the Swiss Federal Nuclear Safety Inspectorate, ENSI, assesses and monitors nuclear facilities in Switzerland. This includes the five nuclear power plants (NPPs), the plant-based interim storage facilities, the Central Interim Storage Facility (ZWILAG) at Wuerenlingen, the nuclear facilities at the Paul Scherrer Institute (PSI), the two universities of Basel and Lausanne, the transport of radioactive materials from and to nuclear facilities and the preparation for a deep geologic repository for radioactive waste. Using inspections, surveillance meetings, reviews and analyses as well as reports from plant licensees, ENSI obtains the required overview of the safety of the nuclear facilities. It maintains its own emergency organisation, which is an integral part of the national emergency structure. The legislative framework at the basis of the activity of ENSI specifies the criteria by which it evaluates the activities and plans of the operators of nuclear facilities. ENSI provides the public with information on particular events and observations relating to nuclear facilities. The five nuclear power plants in Switzerland (Beznau Units 1 und 2, Muehleberg, Goesgen and Leibstadt) were all operated safely in 2010. Last year, there were 39 notifiable events in Switzerland: 4 events affected both Beznau Units, 10 events the Goesgen NPP, 6 the Leibstadt NPP and 13 the Muehleberg NPP and 6 in other facilities. Based on the International Nuclear Event Scale (INES) of 0-7, ENSI rated 38 events as Level 0, and as INES Level 2 the event on 31 August 2010 during maintenance work at the Leibstadt NPP, where a diver was exposed to radiation in excess of the maximum annual exposure rate of 20 mSv. The ZWILAG at Wuerenlingen consists of several interim storage halls, a conditioning plant and the plasma plant (incineration/melting plant). At the end of 2010, the cask storage hall contained 34 transport/storage casks with spent

  19. 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...

  20. Interim Storage of Spent Nuclear Fuel before Final Disposal in Germany - Regulator's view

    International Nuclear Information System (INIS)

    Arens, G.; Goetz, Ch.; Geupel, Sandra; Gmal, B.; Mester, W.

    2014-01-01

    For spent nuclear fuel management in Germany the concept of dry interim storage in dual purpose casks before direct disposal is applied. The Federal Office for Radiation Protection (BfS) is the competent authority for licensing of interim storage facilities. The competent authority for surveillance of operation is the responsible authority of the respective federal state (Land). Currently operation licenses for storage facilities have been granted for a storage time of 40 years and are based on safety demonstrations for all safety issues as safe enclosure, shielding, sub-criticality and decay heat removal under consideration of operation conditions. In addition, transportability of the casks for the whole storage period has to be provided. Due to current delay in site selection and exploration of a disposal site, an extension of the storage time beyond 40 years could be needed. This will cause appropriate actions by the licensee and the competent authorities as well. A brief description of the regulatory base of licensing and surveillance of interim storage is given from the regulators view. Furthermore the current planning for final disposal of spent nuclear fuel and high level waste and its interconnections between storage and disposal concepts are shortly explained. Finally the relevant aspects for licensing of extended storage time beyond 40 years will be discussed. Current activities on this issue, which have been initiated by the Federal Government, will be addressed. On the regulatory side a review and amendment of the safety guideline for interim storage of spent fuel has been performed and the procedure of periodic safety review is being implemented. A guideline for implementing an ageing management programme is available in a draft version. Regarding safety of long term storage a study focussing on the identification and evaluation of long term effects as well as gaps of knowledge has been finished in 2010. A continuation and update is currently underway

  1. 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

  2. Reference values on safety regulation of land disposal of low level radioactive solid waste (the second interim report) and its incorporation into legal regulations

    International Nuclear Information System (INIS)

    Aoki, Terumi

    1994-01-01

    Safety regulation of land disposal of low level radioactive solid waste in Japan is based on 'the basic philosophy on the safety regulation of land disposal of low level radioactive solid waste' determined by the Nuclear safety Committee (October 1985). The basic philosophy on the upper limit of radioactivity of disposed wastes was published as the reference values in the interim report (February 1987) and in the second interim report (June 1992). In the second interim report, the upper limits of radioactivity are established for three types of solid radioactive wastes: 1) metals, incombustible or flame resistant wastes generated nuclear reactor facilities and solidified in vessels, 2) large metallic structures generated from decommissioning of reactor facilities and difficult to solidify in vessels, and 3) radioactive concrete waste generated from decommissioning of reactor facilities. The upper limits of radioactivity are presented for C-14, Co-60, Ni-63, Sr-90, Cs-137, alfa-emmitters, Ca-41 (for concrete) and Eu-152 (for concrete). Related laws and regulations in Japan on safe disposal of low level wastes are explained. (T.H.)

  3. Antihypertensive medication classes used among medicare beneficiaries initiating treatment in 2007-2010.

    Science.gov (United States)

    Kent, Shia T; Shimbo, Daichi; Huang, Lei; Diaz, Keith M; Kilgore, Meredith L; Oparil, Suzanne; Muntner, Paul

    2014-01-01

    After the 2003 publication of the Seventh Report of the Joint National Committee on Prevention, Detection, Evaluation, and Treatment of High Blood Pressure (JNC 7) guidelines, there was a 5-10% increase in patients initiating antihypertensive medication with a thiazide-type diuretic, but most patients still did not initiate treatment with this class. There are few contemporary published data on antihypertensive medication classes filled by patients initiating treatment. We used the 5% random Medicare sample to study the initiation of antihypertensive medication between 2007 and 2010. Initiation was defined by the first antihypertensive medication fill preceded by 365 days with no antihypertensive medication fills. We restricted our analysis to beneficiaries ≥ 65 years who had two or more outpatient visits with a hypertension diagnosis and full Medicare fee-for-service coverage for the 365 days prior to initiation of antihypertensive medication. Between 2007 and 2010, 32,142 beneficiaries in the 5% Medicare sample initiated antihypertensive medication. Initiation with a thiazide-type diuretic decreased from 19.2% in 2007 to 17.9% in 2010. No other changes in medication classes initiated occurred over this period. Among those initiating antihypertensive medication in 2010, 31.3% filled angiotensin-converting enzyme inhibitors (ACE-Is), 26.9% filled beta blockers, 17.2% filled calcium channel blockers, and 14.4% filled angiotensin receptor blockers (ARBs). Initiation with >1 antihypertensive medication class decreased from 25.6% in 2007 to 24.1% in 2010. Patients initiated >1 antihypertensive medication class most commonly with a thiazide-type diuretic and either an ACE-I or ARB. These results suggest that JNC 7 had a limited long-term impact on the choice of antihypertensive medication class and provide baseline data prior to the publication of the 2014 Evidence-Based Guideline for the Management of High Blood Pressure in Adults from the Panel Members Appointed to

  4. The Use of Ambulatory Blood Pressure Monitoring Among Medicare Beneficiaries in 2007-2010

    OpenAIRE

    Shimbo, Daichi; Kent, Shia T; Diaz, Keith M; Huang, Lei; Viera, Anthony J; Kilgore, Meredith; Oparil, Suzanne; Muntner, Paul

    2014-01-01

    The US Centers for Medicaid and Medicare Services reimburses ambulatory blood pressure monitoring (ABPM) for suspected white coat hypertension. We estimated ABPM use between 2007 and 2010 among a 5% random sample of Medicare beneficiaries (≥ 65 years). In 2007, 2008, 2009 and 2010, the percentage of beneficiaries with ABPM claims was 0.10%, 0.11%, 0.10%, and 0.09% respectively. A prior diagnosis of hypertension was more common among those with versus without an ABPM claim (77.7% versus 47.0%)...

  5. Diseño del Monitoreo Nacional de Indicadores Nutricionales (MONIN, Perú 2007-2010 Design of the National Surveillance of Nutritional Indicators (MONIN, Peru 2007-2010

    Directory of Open Access Journals (Sweden)

    Miguel Campos-Sánchez

    2011-06-01

    Full Text Available Objetivos. Describir el diseño y los métodos del monitoreo nacional de indicadores nutricionales (MONIN 2007-2010 conducido por INS/CENAN. Materiales y métodos. El MONIN fue diseñado como una encuesta continua (transversal repetida, por muestreo aleatorio estratificado y multietápico, del universo de niños menores de cinco años y gestantes residentes en el Perú, dividido en cinco estratos geográficos y seis trimestres (semanas permutadas aleatoriamente que fueron 78% del tiempo entre el 19 de noviembre de 2007 y el 2 de abril de 2010. Resultados. La muestra total ha obtenido 3 827 niños en 361 conglomerados terminados. La pérdida ha sido 8,4% en los conglomerados, 1,8% de viviendas, 13,2% de hogares, 4,2% en antropometría, 13,3% en hemoglobina, 21,2% en consumo de alimentos; 55,0% en retinol y 29,9% en yoduria. Conclusiones. El diseño del MONIN es factible y su implementación resulta útil para la estimación de los indicadores de desnutrición infantil.Objectives. To describe the design and methods of the national surveillance of nutritional indicators (MONIN 2007-2010, carried out by INS/CENAN. Materials and methods. MONIN was designed as a continuous (repeated cross-sectional survey, with stratified multi-stage random sampling, considering the universe as all under five children and pregnant women residing in Peru, divided into 5 geographical strata and 6 trimesters (randomly permuted weeks, about 78% of the time between November 19, 2007 and April 2, 2010. Results. The total sample was 3,827 children in 361 completed clusters. The dropout rate was 8.4% in clusters, 1.8% in houses, and 13.2% in households. Dropout was also 4.2, 13.3, 21.2, 55% and 29% in anthropometry, hemoglobin, food intake, retinol and ioduria measurements, respectively. Conclusions. The MONIN design is feasible and useful for the estimation of indicators of childhood malnutrition.

  6. 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...

  7. 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.

  8. 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...

  9. 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...

  10. National spatial and temporal patterns of notified dengue cases, Colombia 2007-2010.

    Science.gov (United States)

    Restrepo, Angela Cadavid; Baker, Peter; Clements, Archie C A

    2014-07-01

    To explore the variation in the spatial distribution of notified dengue cases in Colombia from January 2007 to December 2010 and examine associations between the disease and selected environmental risk factors. Data on the number of notified dengue cases in Colombia were obtained from the National Institute of Health (Instituto Nacional de Salud - INS) for the period 1 January 2007 through 31 December 2010. Data on environmental factors were collected from the Worldclim website. A Bayesian spatio-temporal conditional autoregressive model was used to quantify the relationship between monthly dengue cases and temperature, precipitation and elevation. Monthly dengue counts decreased by 18% (95% credible interval (CrI): 17-19%) in 2008 and increased by 30% (95% CrI: 28-31%) and 326% (95% CrI: 322-331%) in 2009 and 2010, respectively, compared to 2007. Additionally, there was a significant, nonlinear effect of monthly average precipitation. The results highlight the role of environmental risk factors in determining the spatial of dengue and show how these factors can be used to develop and refine preventive approaches for dengue in Colombia. © 2014 John Wiley & Sons Ltd.

  11. Regulatory oversight report 2010 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2010 zur nuklearen Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-06-15

    Acting as the regulatory body of the Swiss Confederation, the Swiss Federal Nuclear Safety Inspectorate, ENSI, assesses and monitors nuclear facilities in Switzerland. This includes the five nuclear power plants (NPPs), the plant-based interim storage facilities, the Central Interim Storage Facility (ZWILAG) at Wuerenlingen, the nuclear facilities at the Paul Scherrer Institute (PSI), the two universities of Basel and Lausanne, the transport of radioactive materials from and to nuclear facilities and the preparation for a deep geologic repository for radioactive waste. Using inspections, surveillance meetings, reviews and analyses as well as reports from plant licensees, ENSI obtains the required overview of the safety of the nuclear facilities. It maintains its own emergency organisation, which is an integral part of the national emergency structure. The legislative framework at the basis of the activity of ENSI specifies the criteria by which it evaluates the activities and plans of the operators of nuclear facilities. ENSI provides the public with information on particular events and observations relating to nuclear facilities. The five nuclear power plants in Switzerland (Beznau Units 1 und 2, Muehleberg, Goesgen and Leibstadt) were all operated safely in 2010. Last year, there were 39 notifiable events in Switzerland: 4 events affected both Beznau Units, 10 events the Goesgen NPP, 6 the Leibstadt NPP and 13 the Muehleberg NPP and 6 in other facilities. Based on the International Nuclear Event Scale (INES) of 0-7, ENSI rated 38 events as Level 0, and as INES Level 2 the event on 31 August 2010 during maintenance work at the Leibstadt NPP, where a diver was exposed to radiation in excess of the maximum annual exposure rate of 20 mSv. The ZWILAG at Wuerenlingen consists of several interim storage halls, a conditioning plant and the plasma plant (incineration/melting plant). At the end of 2010, the cask storage hall contained 34 transport/storage casks with spent

  12. Status of safety at Areva group facilities. 2007 annual report; Areva, etat de surete des installations nucleaires. Rapport annuel 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This report describes the status of nuclear safety and radiation protection in the facilities of the AREVA group and gives information on radiation protection in the service operations, as observed through the inspection programs and analyses carried out by the General Inspectorate in 2007. Having been submitted to the group's Supervisory Board, this report is sent to the bodies representing the personnel. Content: 1 - A look back at 2007 by the AREVA General Inspector: Visible progress in 2007, Implementation of the Nuclear Safety Charter, Notable events; 2 - Status of nuclear safety and radiation protection in the nuclear facilities and service operations: Personnel radiation protection, Event tracking, Service operations, Criticality control, Radioactive waste and effluent management; 3 - Performance improvement actions; 4 - Description of the General Inspectorate; 5 - Glossary.

  13. Safety research activities for Japanese regulations of spent fuel interim storage facilities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-08-15

    Japan Nuclear Energy Safety Organization (JNES) carries out (a) preparation of technical documents, (b) technical evaluations of standards (prepared by academic societies), etc. and (c) other R and D activities, to support Nuclear Regulation Authority (NRA: which controls the regulations for Spent Fuel Interim Storage Facilities). In 2012 fiscal year, JNES carried out dynamic test of spent fuel to examine the integrity of spent fuel under cask drop accidents, and preparation for PWR spent fuel storage test to prove long term integrity of spent fuel and cask itself. Some of these tests will be also carried out in 2013 fiscal year and after. (author)

  14. Antihypertensive medication classes used among medicare beneficiaries initiating treatment in 2007-2010.

    Directory of Open Access Journals (Sweden)

    Shia T Kent

    Full Text Available After the 2003 publication of the Seventh Report of the Joint National Committee on Prevention, Detection, Evaluation, and Treatment of High Blood Pressure (JNC 7 guidelines, there was a 5-10% increase in patients initiating antihypertensive medication with a thiazide-type diuretic, but most patients still did not initiate treatment with this class. There are few contemporary published data on antihypertensive medication classes filled by patients initiating treatment.We used the 5% random Medicare sample to study the initiation of antihypertensive medication between 2007 and 2010. Initiation was defined by the first antihypertensive medication fill preceded by 365 days with no antihypertensive medication fills. We restricted our analysis to beneficiaries ≥ 65 years who had two or more outpatient visits with a hypertension diagnosis and full Medicare fee-for-service coverage for the 365 days prior to initiation of antihypertensive medication. Between 2007 and 2010, 32,142 beneficiaries in the 5% Medicare sample initiated antihypertensive medication. Initiation with a thiazide-type diuretic decreased from 19.2% in 2007 to 17.9% in 2010. No other changes in medication classes initiated occurred over this period. Among those initiating antihypertensive medication in 2010, 31.3% filled angiotensin-converting enzyme inhibitors (ACE-Is, 26.9% filled beta blockers, 17.2% filled calcium channel blockers, and 14.4% filled angiotensin receptor blockers (ARBs. Initiation with >1 antihypertensive medication class decreased from 25.6% in 2007 to 24.1% in 2010. Patients initiated >1 antihypertensive medication class most commonly with a thiazide-type diuretic and either an ACE-I or ARB.These results suggest that JNC 7 had a limited long-term impact on the choice of antihypertensive medication class and provide baseline data prior to the publication of the 2014 Evidence-Based Guideline for the Management of High Blood Pressure in Adults from the Panel

  15. 2007 motor vehicle occupant safety survey. Volume 3, air bags report

    Science.gov (United States)

    2008-11-01

    The 2007 Motor Vehicle Occupant Safety Survey was the sixth in a series of periodic national telephone surveys on occupant : protection issues conducted for the National Highway Traffic Safety Administration (NHTSA). Data collection was conducted : b...

  16. Annex D-200 Area Interim Storage Area Final Safety Analysis Report [FSAR] [Section 1 & 2

    Energy Technology Data Exchange (ETDEWEB)

    CARRELL, R D

    2002-07-16

    The 200 Area Interim Storage Area (200 Area ISA) at the Hanford Site provides for the interim storage of non-defense reactor spent nuclear fuel (SNF) housed in aboveground dry cask storage systems. The 200 Area ISA is a relatively simple facility consisting of a boundary fence with gates, perimeter lighting, and concrete and gravel pads on which to place the dry storage casks. The fence supports safeguards and security and establishes a radiation protection buffer zone. The 200 Area ISA is nominally 200,000 ft{sup 2} and is located west of the Canister Storage Building (CSB). Interim storage at the 200 Area ISA is intended for a period of up to 40 years until the materials are shipped off-site to a disposal facility. This Final Safety Analysis Report (FSAR) does not address removal from storage or shipment from the 200 Area ISA. Three different SNF types contained in three different dry cask storage systems are to be stored at the 200 Area ISA, as follows: (1) Fast Flux Test Facility Fuel--Fifty-three interim storage casks (ISC), each holding a core component container (CCC), will be used to store the Fast Flux Test Facility (FFTF) SNF currently in the 400 Area. (2) Neutron Radiography Facility (NRF) TRIGA'--One Rad-Vault' container will store two DOT-6M3 containers and six NRF TRIGA casks currently stored in the 400 Area. (3) Commercial Light Water Reactor Fuel--Six International Standards Organization (ISO) containers, each holding a NAC-I cask4 with an inner commercial light water reactor (LWR) canister, will be used for commercial LWR SNF from the 300 Area. An aboveground dry cask storage location is necessary for the spent fuel because the current storage facilities are being shut down and deactivated. The spent fuel is being transferred to interim storage because there is no permanent repository storage currently available.

  17. Interim summary report of the safety case 2009

    International Nuclear Information System (INIS)

    2010-03-01

    Following the guidelines set forth by the Ministry of Trade and Industry (now Ministry of Employment and Economy), Posiva is preparing to submit a construction license application for the final disposal spent nuclear fuel at the Olkiluoto site, Finland, by the end of the year 2012. Disposal will take place in a geological repository implemented according to the KBS-3 method. The long-term safety section supporting the license application will be based on a safety case that, according to the internationally adopted definition, will be a compilation of the evidence, analyses and arguments that quantify and substantiate the safety and the level of expert confidence in the safety of the planned repository. The present Interim Summary Report represents a major contribution to the development of this safety case. The report has been compiled in accordance with Posiva's current plan for preparing this safety case. A full safety case for the KBS-3V variant will be developed to support the Preliminary Safety Assessment Report (PSAR) in 2012. The report outlines the current design and safety concept for the planned repository. It summarises the approach used to formulate scenarios for the evolution of the disposal system over time, describes these scenarios and presents the main models and computer codes used to analyse them. It also discusses compliance with Finnish regulatory requirements for long-term safety of a geological repository and gives the main evidence, arguments and analyses that lead to confidence, on the part of Posiva, in the long-term safety of the planned repository. Current understanding of the evolution of the disposal system indicates that, except a few unlikely circumstances affecting a small number of canisters, spent fuel will remain isolated, and the radionuclides contained within the canisters, for hundreds of thousands of years or more, in accordance with the base scenario. Confidence in this base scenario derives, in the first place, from the

  18. report transparency and nuclear safety 2007- CISBIO

    International Nuclear Information System (INIS)

    2007-01-01

    This report presents the activities of CISBIO, nuclear base installation, for the year 2007. CISBIO realizes at Saclay most of the radiopharmaceuticals and drugs distributed in France for the nuclear medicine. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. (A.L.B.)

  19. 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

  20. 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

  1. Review of SKB's interim report of SR-Can: SKI's and SSI's evaluation of SKB's up-dated methodology for safety assessment

    Energy Technology Data Exchange (ETDEWEB)

    Dverstorp, Bjoern; Moberg, Leif; Wiebert, Anders; Xu Shulan [Swedish Radiation Protection Authority, Stockholm (Sweden); Stroemberg, Bo; Kautsky, Fritz; Lilja, Christina; Simic, Eva; Sundstroem, Benny; Toverud, Oeivind [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)

    2005-07-01

    This report presents the findings of a review of the Swedish Nuclear Fuel and Waste Management Co.'s (SKB) interim report of the safety assessment SR-Can (SKB TR 04-11), conducted by the Swedish Radiation Protection Authority (SSI) and the Swedish Nuclear Power Inspectorate (SKI). SKB's interim report describes and exemplifies the safety assessment methodology that SKB plans to use in the oncoming licence applications for an encapsulation plant and a final repository for spent nuclear fuel. The authorities' review takes into account the findings of an international peer review of SKB's interim report. The authorities conclude that SKB has improved its safety assessment methodology in several aspects compared to earlier safety reports. Among other things the authorities commend SKB for giving a comprehensive account of relevant regulations and guidance, and for the systematic approach to identification and documentation of features, events and processes that need to be considered in the safety assessment. However, the authorities also conclude that important parts of SKB's method need to be further developed before they are mature enough to be used as a basis for a license application. The authorities' overall assessment is summarised in chapter 8 of this report.

  2. 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...

  3. Annex D-200 Area Interim Storage Area Final Safety Analysis Report [FSAR] [Section 1 and 2

    International Nuclear Information System (INIS)

    CARRELL, R.D.

    2002-01-01

    The 200 Area Interim Storage Area (200 Area ISA) at the Hanford Site provides for the interim storage of non-defense reactor spent nuclear fuel (SNF) housed in aboveground dry cask storage systems. The 200 Area ISA is a relatively simple facility consisting of a boundary fence with gates, perimeter lighting, and concrete and gravel pads on which to place the dry storage casks. The fence supports safeguards and security and establishes a radiation protection buffer zone. The 200 Area ISA is nominally 200,000 ft 2 and is located west of the Canister Storage Building (CSB). Interim storage at the 200 Area ISA is intended for a period of up to 40 years until the materials are shipped off-site to a disposal facility. This Final Safety Analysis Report (FSAR) does not address removal from storage or shipment from the 200 Area ISA. Three different SNF types contained in three different dry cask storage systems are to be stored at the 200 Area ISA, as follows: (1) Fast Flux Test Facility Fuel--Fifty-three interim storage casks (ISC), each holding a core component container (CCC), will be used to store the Fast Flux Test Facility (FFTF) SNF currently in the 400 Area. (2) Neutron Radiography Facility (NRF) TRIGA'--One Rad-Vault' container will store two DOT-6M3 containers and six NRF TRIGA casks currently stored in the 400 Area. (3) Commercial Light Water Reactor Fuel--Six International Standards Organization (ISO) containers, each holding a NAC-I cask4 with an inner commercial light water reactor (LWR) canister, will be used for commercial LWR SNF from the 300 Area. An aboveground dry cask storage location is necessary for the spent fuel because the current storage facilities are being shut down and deactivated. The spent fuel is being transferred to interim storage because there is no permanent repository storage currently available

  4. Report transparency and nuclear safety 2007 - CISBIO; Rapport transparence et securite nucleaire 2007 - CISBIO

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This report presents the activities of CISBIO, nuclear base installation, for the year 2007. CISBIO realizes at Saclay most of the radiopharmaceuticals and drugs distributed in France for the nuclear medicine. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. (A.L.B.)

  5. Report transparency and nuclear safety 2007 CEA Grenoble; Rapport transparence et securite nucleaire 2007 CEA Grenoble

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This report presents the activities of the CEA Center of Grenoble for the year 2007. Since 2002 the Passage project aims to realize the decontamination and the dismantling of old nuclear installations of the CEA Grenoble. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially the year 2007 saw two main steps of the Passage project: the decommissioning of the Siloette reactor, a public consultation about the Lama laboratory dismantling. (A.L.B.)

  6. Dengue surveillance in Veterans Affairs healthcare facilities, 2007-2010.

    Directory of Open Access Journals (Sweden)

    Patricia L Schirmer

    Full Text Available BACKGROUND: Although dengue is endemic in Puerto Rico (PR, 2007 and 2010 were recognized as epidemic years. In the continental United States (US, outside of the Texas-Mexico border, there had not been a dengue outbreak since 1946 until dengue re-emerged in Key West, Florida (FL, in 2009-2010. The objective of this study was to use electronic and manual surveillance systems to identify dengue cases in Veterans Affairs (VA healthcare facilities and then to clinically compare dengue cases in Veterans presenting for care in PR and in FL. METHODOLOGY: Outpatient encounters from 1/2007-12/2010 and inpatient admissions (only available from 10/2009-12/2010 with dengue diagnostic codes at all VA facilities were identified using VA's Electronic Surveillance System for Early Notification of Community-based Epidemics (ESSENCE. Additional case sources included VA data from Centers for Disease Control and Prevention BioSense and VA infection preventionists. Case reviews were performed. Categorical data was compared using Mantel-Haenszel or Fisher Exact tests and continuous variables using t-tests. Dengue case residence was mapped. FINDINGS: Two hundred eighty-eight and 21 PR and FL dengue cases respectively were identified. Of 21 FL cases, 12 were exposed in Key West and 9 were imported. During epidemic years, FL cases had significantly increased dengue testing and intensive care admissions, but lower hospitalization rates and headache or eye pain symptoms compared to PR cases. There were no significant differences in clinical symptoms, laboratory abnormalities or outcomes between epidemic and non-epidemic year cases in FL and PR. Confirmed/probable cases were significantly more likely to be hospitalized and have thrombocytopenia or leukopenia compared to suspected cases. CONCLUSIONS: Dengue re-introduction in the continental US warrants increased dengue surveillance and education in VA. Throughout VA, under-testing of suspected cases highlights the need to

  7. Annex D 200 Area Interim Storage Area Final Safety Analysis Report Volume 5 (FSAR) (Section 1 and 2)

    International Nuclear Information System (INIS)

    CARRELL, R.D.

    2003-01-01

    The 200 Area Interim Storage Area (200 Area ISA) at the Hanford Site provides for the interim storage of non-defense reactor spent nuclear fuel (SNF) housed in aboveground dry cask storage systems. The 200 Area ISA is a relatively simple facility consisting of a boundary fence with gates, perimeter lighting, and concrete and gravel pads on which to place the dry storage casks. The fence supports safeguards and security and establishes a radiation protection buffer zone. The 200 Area ISA is nominally 200,000 ft 2 and is located west of the Canister Storage Building (CSB). Interim storage at the 200 Area ISA is intended for a period of up to 40 years until the materials are shipped offsite to a disposal facility. This Final Safety Analysis Report (FSAR) does not address removal from storage or shipment from the 200 Area ISA. Three different SNF types contained in three different dry cask storage systems are to be stored at the 200 Area ISA, as follows: (1) Fast Flux Test Facility (FFTF) Fuel--Fifty-three interim storage casks (ISC), each holding a core component container (CCC), will be used to store the FFTF SNF currently in the 400 Area. (2) Neutron Radiography Facility (NRF)TRIGA--One Rad-Vault container stores two DOT-6M 3 containers and six NRF TRIGA casks. (3) Commercial Light Water Reactor Fuel--Six International Standards Organization (ISO) containers, each holding a NAC-1 cask with an inner commercial light water reactor (LWR) canister, are used for storing commercial LWR SNF from the 300 Area. An aboveground dry cask storage location is necessary for the spent fuel because the current storage facilities are being shut down and deactivated. The spent fuel is being transferred to interim storage because there is no permanent repository storage currently available

  8. 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…

  9. IEA SHC Task 38 'Solar air-conditioning and refrigeration'. Danish participation 2007-2010. Appendix; IEA SHC Task 38 'Solar air-conditioning and refrigeration'. Dansk deltagelse 2007-2010. Bilag

    Energy Technology Data Exchange (ETDEWEB)

    Ellehauge, K [Ellehauge og Kildemoes, Aarhus (Denmark); Muenster, E [PlanEnergi, Skoerping (Denmark); Reinholdt, L [Teknologisk Institut, Aarhus (Denmark); Munds, S [AC-Sun Aps, Horsens (Denmark)

    2011-03-15

    IEA SHC Task 38 'Solar Air-Conditioning and Refrigeration' ran from October 2006 to December 2010. Denmark was represented in the task from January 2007 to December 2010. The aim of the task was to encourage use of solar powered refrigeration and air conditioning systems in particular at residential, commercial and industrial sectors. Furthermore, the aim was to contribute to new research and development activities on new systems and concepts. The appendix contains the publications prepared by the Danish project group.(LN)

  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. Behavioral safety and OHSAS 18001:2007

    International Nuclear Information System (INIS)

    Rama Rao, B.S.; Hemantha Rao, G.V.S.

    2009-01-01

    Analysis of industrial accidents reveals that majority of them are due to human errors. And human errors can be due to lack of knowledge/awareness or inherent behavior of the person(s) involved in the accident. While the former can be tackled through training, the latter requires interventions aimed at behavior modification. Realizing the importance of behavioral aspect of safety, Revised Version of Occupational Health and Safety Management System standard - OHSAS 18001:2007 has incorporated 'behavior' in the planning clause 'Hazard identification, risk assessment and determining controls -4.3.1. (c)'. It reads The organization shall establish, implement and maintain a procedure for the ongoing hazard identification, risk assessment and determination of necessary controls. The procedure for hazard identification and risk assessment shall take into account HUMAN BEHAVIOR, CAPABILITIES and other HUMAN FACTORS. Planning and Control are the mantra. Thus, Risk Management and Mitigation strategies should factor in 'behavioral aspect' so as to be effective. In the absence of this, any amount of focus on safety will be incomplete and does not yield desired results. Best stage to take care of the behavioral safety is during the design of Plant and Machinery. Regular monitoring and periodical inspections will ensure early detection of unsafe behavior/practices and renders preventive measures possible. This paper discusses some of the behavioral patterns of industrial workforce, their ramifications for safety and possible remedies to minimize risk and save human capital for the overall well being of the organization, family and ultimately, the society. (author)

  12. 49 CFR 238.230 - Safety appliances-new equipment.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 4 2010-10-01 2010-10-01 false Safety appliances-new equipment. 238.230 Section... I Passenger Equipment § 238.230 Safety appliances—new equipment. (a) Applicability. This section..., 2007, that is equipped with a safety appliance, required by the “manner of application” provisions in...

  13. 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

  14. 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...

  15. IAEA safety glossary. Terminology used in nuclear safety and radiation protection. 2007 ed

    International Nuclear Information System (INIS)

    2007-01-01

    legislation, should be aware that the terms included have been chosen and the definitions and explanations given have been drafted for the purpose mentioned above. Terminology and usage may differ in other contexts, such as in binding international legal instruments and in the publications of other organizations. It is recognized that the Safety Glossary will be of wider interest, and it is therefore now issued as an IAEA publication. It is intended to issue a CD-ROM that will include this Safety Glossary (2007 Edition) and versions of the publication in the other five official languages of the IAEA: Arabic, Chinese, French, Russian and Spanish. These other five versions will also be made available for downloading from the Safety Glossary web site. It is intended to revise and update the Safety Glossary periodically in the light of changes in terminology and usage in the safety standards due to developments in technology and changes in regulatory approaches in Member States. The IAEA Secretariat invites the submission of feedback concerning the definitions of technical terms and the explanations of their usage given in the Safety Glossary from users of the IAEA safety standards (in English and in translation) and other safety related publications. A change form is provided on the Safety Glossary web site - http://www-ns.iaea.org/standards/safetyglossary.htm - for the submission of information or suggestions for consideration in a revision of the Safety Glossary. The first version of the Safety Glossary was compiled and issued in 2000. The Safety Glossary, 2007 Edition, is a revised and updated version. In revising the Safety Glossary, account has been taken of safety standards issued since 2000 and of the comments and suggestions submitted in the revision process and in the course of its translation

  16. IAEA safety glossary. Terminology used in nuclear safety and radiation protection. 2007 ed

    International Nuclear Information System (INIS)

    2007-06-01

    legislation, should be aware that the terms included have been chosen and the definitions and explanations given have been drafted for the purpose mentioned above. Terminology and usage may differ in other contexts, such as in binding international legal instruments and in the publications of other organizations. It is recognized that the Safety Glossary will be of wider interest, and it is therefore now issued as an IAEA publication. It is intended to issue a CD-ROM that will include this Safety Glossary (2007 Edition) and versions of the publication in the other five official languages of the IAEA: Arabic, Chinese, French, Russian and Spanish. These other five versions will also be made available for downloading from the Safety Glossary web site. It is intended to revise and update the Safety Glossary periodically in the light of changes in terminology and usage in the safety standards due to developments in technology and changes in regulatory approaches in Member States. The IAEA Secretariat invites the submission of feedback concerning the definitions of technical terms and the explanations of their usage given in the Safety Glossary from users of the IAEA safety standards (in English and in translation) and other safety related publications. A change form is provided on the Safety Glossary web site - http://www-ns.iaea.org/standards/safetyglossary.htm - for the submission of information or suggestions for consideration in a revision of the Safety Glossary. The first version of the Safety Glossary was compiled and issued in 2000. The Safety Glossary, 2007 Edition, is a revised and updated version. In revising the Safety Glossary, account has been taken of safety standards issued since 2000 and of the comments and suggestions submitted in the revision process and in the course of its translation

  17. IAEA safety glossary. Terminology used in nuclear safety and radiation protection. 2007 ed

    International Nuclear Information System (INIS)

    2007-01-01

    legislation, should be aware that the terms included have been chosen and the definitions and explanations given have been drafted for the purpose mentioned above. Terminology and usage may differ in other contexts, such as in binding international legal instruments and in the publications of other organizations. It is recognized that the Safety Glossary will be of wider interest, and it is therefore now issued as an IAEA publication. It is intended to issue a CD-ROM that will include this Safety Glossary (2007 Edition) and versions of the publication in the other five official languages of the IAEA: Arabic, Chinese, French, Russian and Spanish. These other five versions will also be made available for downloading from the Safety Glossary web site. It is intended to revise and update the Safety Glossary periodically in the light of changes in terminology and usage in the safety standards due to developments in technology and changes in regulatory approaches in Member States. The IAEA Secretariat invites the submission of feedback concerning the definitions of technical terms and the explanations of their usage given in the Safety Glossary from users of the IAEA safety standards (in English and in translation) and other safety related publications. A change form is provided on the Safety Glossary web site - http://www-ns.iaea.org/standards/safetyglossary.htm - for the submission of information or suggestions for consideration in a revision of the Safety Glossary. The first version of the Safety Glossary was compiled and issued in 2000. The Safety Glossary, 2007 Edition, is a revised and updated version. In revising the Safety Glossary, account has been taken of safety standards issued since 2000 and of the comments and suggestions submitted in the revision process and in the course of its translation

  18. 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...

  19. Firearm homicides and suicides in major metropolitan areas - United States, 2006-2007 and 2009-2010.

    Science.gov (United States)

    2013-08-02

    Firearm homicides and suicides are a continuing public health concern in the United States. During 2009-2010, a total of 22,571 firearm homicides and 38,126 firearm suicides occurred among U.S. residents. This includes 3,397 firearm homicides and 1,548 firearm suicides among persons aged 10-19 years; the firearm homicide rate for this age group was slightly above the all-ages rate. This report updates an earlier report that provided statistics on firearm homicides and suicides in major metropolitan areas for 2006-2007, with special emphasis on persons aged 10-19 years in recognition of the importance of early prevention efforts. Firearm homicide and suicide rates were calculated for the 50 most populous U.S. metropolitan statistical areas (MSAs) for 2009-2010 using mortality data from the National Vital Statistics System (NVSS) and population data from the U.S. Census Bureau. Comparison statistics were recalculated for 2006-2007 to reflect revisions to MSA delineations and population estimates subsequent to the earlier report. Although the firearm homicide rate for large MSAs collectively remained above the national rate during 2009-2010, more than 75% of these MSAs showed a decreased rate from 2006-2007, largely accounting for a national decrease. The firearm homicide rate for persons aged 10-19 years exceeded the all-ages rate in many of these MSAs during 2009-2010, similar to the earlier reporting period. Conversely, although the firearm suicide rate for large MSAs collectively remained below the national rate during 2009-2010, nearly 75% of these MSAs showed an increased rate from 2006-2007, paralleling the national trend. Firearm suicide rates among persons aged 10-19 years were low compared with all-ages rates during both periods. These patterns can inform the development and monitoring of strategies directed at reducing firearm-related violence.

  20. Nuclear Safety Review for the Year 2010

    International Nuclear Information System (INIS)

    2011-07-01

    The Agency, as a leading organization for promoting international cooperation among its Member States, is in a unique position to observe global trends, issues and challenges in nuclear safety and security through a wide variety of activities related to the establishment of safety standards and security guidelines and their application. The contents of this Nuclear Safety Review reflect the emerging nuclear safety trends, issues and challenges for 2010, as well as recapitulate the Agency's activities intended to further strengthen the global nuclear safety and security framework in all areas of nuclear, radiation, waste and transport safety. The accident at the Fukushima Daiichi Nuclear Power Plant, caused by the extraordinary disasters of the earthquake and tsunamis that struck Japan on 11 March 2011, continues to be assessed. As this report focuses on developments in 2010, the accident and its implications are not addressed here, but will be addressed in future reports of the Agency. The international nuclear community maintained a high level of safety performance in 2010. Nuclear power plant safety performance remained high, and indicated an improved trend in the number of emergency shutdowns as well in the level of energy available during these shutdowns. In addition, more States explored or expanded their interests in nuclear power programmes, and more faced the challenge of establishing the required regulatory infrastructure, regulatory supervision and safety management over nuclear installations and the use of ionizing radiation. Issues surrounding radiation protection and radioecology continued as trends in 2010. For example, increased public awareness of exposure to and environmental impacts of naturally occurring radioactive material (NORM) as well as nuclear legacy sites has led to increased public concern. In addition, human resources in radiation protection and radioecology have been lost as a result of retirement and of the migration of experts to

  1. ASN annual report 2007 - ASN report abstracts on the state of Nuclear Safety and Radiation Protection in France in 2007; ASN rapport annuel 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    The 2007 annual report of the French nuclear safety authority (ASN) presents the highlights of the year in the domain of nuclear safety and radiation protection in France. The year 2007 was marked by the implementation of a new legislative and regulatory framework created by the 13 June 2006 Act on transparency and security in the nuclear field (TSN) and the 28 June Act on the sustainable management of radioactive materials and wastes. As in the previous two years, the year was relatively satisfactory from the nuclear safety viewpoint and slightly less so with regard to small-scale nuclear activities. For two years now, the medical field has been marked by the declaration to ASN of a number of serious radiotherapy accidents which have led to several deaths or the need for extensive surgery. The following main topics are reviewed in the document: 1 - the decrees implementing the 'TSN' act and the 'Waste' act; 2 - the new ASN, one year on; 3 - ASN regulatory actions in the field of radiotherapy; 4 - regulation of new installations; 5 - the key issues for regulation of existing installations; 6 - nuclear safety and radiation protection research; 7 - policy for management of the post-accident phase of a radiological emergency; 8 - sites and soils polluted by radioactive materials; 9 - international harmonization of nuclear safety and radiation protection.

  2. ASN annual report 2007 - ASN report abstracts on the state of Nuclear Safety and Radiation Protection in France in 2007; ASN rapport annuel 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    The 2007 annual report of the French nuclear safety authority (ASN) presents the highlights of the year in the domain of nuclear safety and radiation protection in France. The year 2007 was marked by the implementation of a new legislative and regulatory framework created by the 13 June 2006 Act on transparency and security in the nuclear field (TSN) and the 28 June Act on the sustainable management of radioactive materials and wastes. As in the previous two years, the year was relatively satisfactory from the nuclear safety viewpoint and slightly less so with regard to small-scale nuclear activities. For two years now, the medical field has been marked by the declaration to ASN of a number of serious radiotherapy accidents which have led to several deaths or the need for extensive surgery. The following main topics are reviewed in the document: 1 - the decrees implementing the 'TSN' act and the 'Waste' act; 2 - the new ASN, one year on; 3 - ASN regulatory actions in the field of radiotherapy; 4 - regulation of new installations; 5 - the key issues for regulation of existing installations; 6 - nuclear safety and radiation protection research; 7 - policy for management of the post-accident phase of a radiological emergency; 8 - sites and soils polluted by radioactive materials; 9 - international harmonization of nuclear safety and radiation protection.

  3. Site safety progress review of spent fuel central interim storage facility. Final report

    International Nuclear Information System (INIS)

    Gurpinar, A.; Serva, L.; Giuliani

    1995-01-01

    Following the request of the Czech Power Board (CEZ) and within the scope of the Technical Cooperation Project CZR/9/003, a progress review of the site safety of the Spent Fuel Central Interim Storage Facility (SFCISF) was performed. The review involved the first two stages of the works comprising the regional survey and identification of candidate sites for the underground and surface storage options. Five sites have been identified as a result of the previous works. The following two stages will involved the identification of the preferred candidate sites for the two options and the final site qualification. The present review had the purpose of assessing the work already performed and making recommendations for the next two stages of works

  4. 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

  5. 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

  6. Nuclear power and nuclear safety 2010; Kernekraft og nuklear sikkerhed 2010

    Energy Technology Data Exchange (ETDEWEB)

    Lauritzen, B.; OElgaard, P.L. (eds.); Nonboel, E. (Risoe DTU, Roskilde (Denmark)); Kampmann, D.; Nystrup, P.E. (Beredskabsstyrelsen, Birkeroed (Denmark))

    2011-07-15

    The report is the eighth report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2010 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations, and conflicts and the Fukushima accident. (LN)

  7. Sweden's Cooperation with Eastern Europe in Radiation Safety 2010

    International Nuclear Information System (INIS)

    Van Dassen, Lars; Andersson, Sarmite; Bejarano, Gabriela

    2011-09-01

    The Swedish Radiation Safety Authority implemented in 2010 cooperation projects in Russia, Ukraine, Georgia, Armenia, Lithuania and Moldova based on instructions from the Swedish Government and agreements with the European Union and the Swedish International Development Cooperation Agency, SIDA. The projects aim at achieving a net contribution to radiation safety (including nuclear safety, nuclear security and non-proliferation as well as radiation protection and emergency preparedness) for the benefit of the host country as well as Sweden. This report gives an overview of all the projects implemented in 2010

  8. Report transparency and nuclear safety 2007 CEA Saclay

    International Nuclear Information System (INIS)

    2007-01-01

    This report presents the activities of the CEA Center of Saclay for the year 2007. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially two public consultation on release authorizations and the Neurospin installations, the dismantling of the 49 nuclear installation, the shutdown of the learning reactor ULYSSE are detailed. (A.L.B.)

  9. German Approach for the Transport of Spent Fuel Packages after Interim Storage

    International Nuclear Information System (INIS)

    Wille, Frank; Wolff, Dietmar; Droste, Bernhard; Voelzke, Holger

    2014-01-01

    In Germany the concept of dry interim storage of spent nuclear fuel in dual purpose metal casks is implemented, currently for periods of up to 40 years. The casks being used have an approved package design in accordance with the international transport regulations. The license for dry storage is granted on the German Atomic Energy Act with respect to the recently (in 2012) revised 'Guidelines for dry cask storage of spent nuclear fuel and heat-generating waste' by the German Waste management Commission (ESK) which are very similar to the former RSK (reactor safety commission) guidelines. For transport on public routes between or after long term interim storage periods, it has to be ensured that the transport and storage casks fulfil the specifications of the transport approval or other sufficient properties which satisfy the proofs for the compliance of the safety objectives at that time. In recent years the validation period of transport approval certificates for manufactured, loaded and stored packages were discussed among authorities and applicants. A case dependent system of 3, 5 and 10 years was established. There are consequences for the safety cases in the Package Design Safety Report including evaluation of long term behavior of components and specific operating procedures of the package. Present research and knowledge concerning the long term behavior of transport and storage cask components have to be consulted as well as experiences from interim cask storage operations. Challenges in the safety assessment are e.g. the behavior of aged metal and elastomeric seals under IAEA test conditions to ensure that the results of drop tests can be transferred to the compliance of the safety objectives at the time of transport after the interim storage period (aged package). Assessment methods for the material compatibility, the behavior of fuel assemblies and the aging behavior of shielding parts are issues as well. This paper describes the state

  10. Nuclear Safety Review for the Year 2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-15

    The contents of this Nuclear Safety Review reflect the emerging nuclear safety trends, issues and challenges for 2010, as well as recapitulate the Agency's activities intended to further strengthen the global nuclear safety and security framework in all areas of nuclear, radiation, waste and transport safety. Nuclear power plant safety performance remained high, and indicated an improved trend in the number of emergency shutdowns as well in the level of energy available during these shutdowns. In addition, more States explored or expanded their interests in nuclear power programmes, and more faced the challenge of establishing the required regulatory infrastructure, regulatory supervision and safety management over nuclear installations and the use of ionizing radiation. Issues surrounding radiation protection and radioecology continued as trends in 2010. For example, increased public awareness of exposure to and environmental impacts of naturally occurring radioactive material (NORM) as well as nuclear legacy sites has led to increased public concern. In addition, human resources in radiation protection and radioecology have been lost as a result of retirement and of the migration of experts to other fields. It is clear that safety continues to be a work in progress. The global nuclear power industry continued to require substantial efforts by designers, manufacturers, operators, regulators and other stakeholders to satisfy diverse quality and safety requirements and licensing processes, along with the recognized need in industry and among regulators to standardize and harmonize these requirements and processes. In some cases, plans for nuclear power programme development moved faster than the establishment of the necessary regulatory and safety infrastructure and capacity. To assist Member States in this effort, the Regulatory Cooperation Forum (RCF) was formed in June 2010. The RCF is a regulator-to-regulator forum that optimizes regulatory support from Member

  11. 49 CFR 37.169 - Interim requirements for over-the-road bus service operated by private entities.

    Science.gov (United States)

    2010-10-01

    ... of such devices, shall be permitted in the passenger compartment. When the bus is at rest at a stop... 49 Transportation 1 2010-10-01 2010-10-01 false Interim requirements for over-the-road bus service... Interim requirements for over-the-road bus service operated by private entities. (a) Private entities...

  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. Report transparency and nuclear safety 2007 CEA Marcoule

    International Nuclear Information System (INIS)

    2007-01-01

    This report presents the activities of the CEA Center of Marcoule for the year 2007. Since its creation in 1955 the center realizes industrial and scientific activities relative to the civil and military applications of the radioactivity. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially the following two base activities are detailed: Atalante and Phenix. (A.L.B.)

  14. Report transparency and nuclear safety 2007 CEA Cadarache

    International Nuclear Information System (INIS)

    2007-01-01

    This report presents the activities of the CEA Center of Cadarache for the year 2007. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially the report discusses the beginning of the RJH reactor construction, the fourth generation reactors research programs, the implementing of la Rotonde the new radioactive wastes management installation, the renovation of the LECA. (A.L.B.)

  15. Improvement in Outcomes of Clinical Islet Transplantation: 1999–2010

    Science.gov (United States)

    Barton, Franca B.; Rickels, Michael R.; Alejandro, Rodolfo; Hering, Bernhard J.; Wease, Stephen; Naziruddin, Bashoo; Oberholzer, Jose; Odorico, Jon S.; Garfinkel, Marc R.; Levy, Marlon; Pattou, Francois; Berney, Thierry; Secchi, Antonio; Messinger, Shari; Senior, Peter A.; Maffi, Paola; Posselt, Andrew; Stock, Peter G.; Kaufman, Dixon B.; Luo, Xunrong; Kandeel, Fouad; Cagliero, Enrico; Turgeon, Nicole A.; Witkowski, Piotr; Naji, Ali; O’Connell, Philip J.; Greenbaum, Carla; Kudva, Yogish C.; Brayman, Kenneth L.; Aull, Meredith J.; Larsen, Christian; Kay, Tom W.H.; Fernandez, Luis A.; Vantyghem, Marie-Christine; Bellin, Melena; Shapiro, A.M. James

    2012-01-01

    OBJECTIVE To describe trends of primary efficacy and safety outcomes of islet transplantation in type 1 diabetes recipients with severe hypoglycemia from the Collaborative Islet Transplant Registry (CITR) from 1999 to 2010. RESEARCH DESIGN AND METHODS A total of 677 islet transplant-alone or islet-after-kidney recipients with type 1 diabetes in the CITR were analyzed for five primary efficacy outcomes and overall safety to identify any differences by early (1999–2002), mid (2003–2006), or recent (20072010) transplant era based on annual follow-up to 5 years. RESULTS Insulin independence at 3 years after transplant improved from 27% in the early era (1999–2002, n = 214) to 37% in the mid (2003–2006, n = 255) and to 44% in the most recent era (20072010, n = 208; P = 0.006 for years-by-era; P = 0.01 for era alone). C-peptide ≥0.3 ng/mL, indicative of islet graft function, was retained longer in the most recent era (P islet reinfusion rate was lower: 48% by 1 year in 20072010 vs. 60–65% in 1999–2006 (P islet graft function (P islet transplantation in recipients who received transplants in 20072010 compared with those in 1999–2006, with fewer islet infusions and adverse events per recipient. PMID:22723582

  16. T-TY Tank Farm Interim Surface Barrier Demonstration - Vadose Zone Monitoring Plan

    International Nuclear Information System (INIS)

    Zhang, Z.F.; Strickland, Christopher E.; Field, Jim G.; Parker, Danny L.

    2010-01-01

    The Hanford Site has 149 underground single-shell tanks that store hazardous radioactive waste. Many of these tanks and their associated infrastructure (e.g., pipelines, diversion boxes) have leaked. Some of the leaked waste has entered the groundwater. The largest known leak occurred from the T-106 Tank of the 241-T Tank Farm in 1973. Five tanks are assumed to have leaked in the TY Farm. Many of the contaminants from those leaks still reside within the vadose zone within the T and TY Tank Farms. The Department of Energy's Office of River Protection seeks to minimize the movement of these contaminant plumes by placing interim barriers on the ground surface. Such barriers are expected to prevent infiltrating water from reaching the plumes and moving them further. The soil water regime is monitored to determine the effectiveness of the interim surface barriers. Soil-water content and water pressure are monitored using off-the-shelf equipment that can be installed by the hydraulic hammer technique. Four instrument nests were installed in the T Farm in fiscal year (FY) 2006 and FY2007; two nests were installed in the TY Farm in FY2010. Each instrument nest contains a neutron probe access tube, a capacitance probe, and four heat-dissipation units. A meteorological station has been installed at the north side of the fence of the T Farm. This document summarizes the monitoring methods, the instrument calibration and installation, and the vadose zone monitoring plan for interim barriers in T farm and TY Farm.

  17. Insights from the interim reliability evaluation program pertinent to reactor safety issues

    International Nuclear Information System (INIS)

    Carlson, D.D.

    1983-01-01

    The Interim Reliability Evaluation Program (IREP) consisted of concurrent probabilistic analyses of four operating nuclear power plants. This paper presents and integrated view of the results of the analyses drawing insights pertinent to reactor safety. The importance to risk of accident sequences initiated by transients and small loss-of-coolant accidents was confirmed. Support systems were found to contribute significantly to the sets of dominant accident sequences, either due to single failures which could disable one or more mitigating systems or due to their initiating plant transients. Human errors in response to accidents also were important risk contributors. Consideration of operator recovery actions influences accident sequence frequency estimates, the list of accident sequences dominating core melt, and the set of dominant risk contributors. Accidents involving station blackout, reactor coolant pump seal leaks and ruptures, and loss-of-coolant accidents requiring manual initiation of coolant injection were found to be risk significant

  18. Economic and public health impact of 2007-2010 tobacco tax increases in Ukraine.

    Science.gov (United States)

    Ross, Hana; Stoklosa, Michal; Krasovsky, Konstantin

    2012-07-01

    To evaluate the impact of the dynamic 2007-2010 tobacco tax policy in Ukraine on cigarette prices, cigarette consumption, tobacco tax revenue and the tobacco industry's price strategy. Using data on cigarette sales, cigarette prices, income and tobacco control policies, price elasticities of cigarette demand in Ukraine were estimated using two methods. Annual data were used to generate point price elasticity estimates, while monthly data were used in a two-step Engle-Granger procedure. The point price elasticity estimate is data sensitive and ranges from -0.11 to -0.62, centring around -0.32. The regression model estimates a long-run price elasticity of -0.28. Cigarette consumption fell by 13% in 2009 and 15% in 2010 while the tax revenue increased by US$700 million and by US$500 million in 2009 and 2010, respectively, compared to the previous year. Tax increases have changed the tobacco industry's price strategy from one of shielding consumers from the impact of smaller tax hikes in 2007-2008, to one of increasing industry net-of-tax prices, after recent, larger tax increases. The higher real tobacco excise taxes of 2009 and 2010 have significantly reduced tobacco consumption in Ukraine, resulting in encouraging public health and fiscal gains. It will be important for cigarette prices/taxes to keep pace with inflation and income growth for this impact to be sustained.

  19. The Use of Ambulatory Blood Pressure Monitoring Among Medicare Beneficiaries in 2007-2010

    Science.gov (United States)

    Shimbo, Daichi; Kent, Shia T; Diaz, Keith M; Huang, Lei; Viera, Anthony J; Kilgore, Meredith; Oparil, Suzanne; Muntner, Paul

    2014-01-01

    The US Centers for Medicaid and Medicare Services reimburses ambulatory blood pressure monitoring (ABPM) for suspected white coat hypertension. We estimated ABPM use between 2007 and 2010 among a 5% random sample of Medicare beneficiaries (≥ 65 years). In 2007, 2008, 2009 and 2010, the percentage of beneficiaries with ABPM claims was 0.10%, 0.11%, 0.10%, and 0.09% respectively. A prior diagnosis of hypertension was more common among those with versus without an ABPM claim (77.7% versus 47.0%). Among hypertensive beneficiaries, 95.2% of those with an ABPM claim were taking antihypertensive medication. Age 75-84 versus 65-74 years, having coronary heart disease, chronic kidney disease, multiple prior hypertension diagnoses, and having filled multiple classes of antihypertensive medication were associated with an increased odds for an ABPM claim among hypertensive beneficiaries. ABPM use was very low among Medicare beneficiaries and was not primarily used for diagnosing white coat hypertension in untreated individuals. PMID:25492832

  20. Surveillance on The Safety and Efficacy of Ambrisentan (Volibris Tablet 2.5 mg) in Patients with Pulmonary Arterial Hypertension in Real Clinical Practice: Post-marketing Surveillance (Interim Analysis Report).

    Science.gov (United States)

    Takahashi, Tomohiko; Hayata, Satoru; Kobayashi, Akihiro; Onaka, Yuna; Ebihara, Takeshi; Hara, Terufumi

    2018-03-01

    Pulmonary arterial hypertension (PAH) is an intractable and rare disease and the accumulation of clinical evidence under real-world setting is needed. A post-marketing surveillance for the endothelin receptor antagonist ambrisentan (Volibris tablet) has been conducted by all-case investigation since September 2010. This paper is an interim report on the safety and efficacy of ambrisentan in 702 patients with PAH. PAH patients aged 15 years or older were subjected to the analysis. The safety analysis by overall cases or stratification of patient backgrounds and the efficacy analysis were investigated. Regarding patient characteristics, the 702 patients subjected to safety analysis included 543 (77.4%) women and 546 (77.8%) patients at WHO functional class II/III. The mean observational time was 392.7 days. A total of 324 adverse drug reaction (ADR) occurred in 204 (29.1%) patients. Common ADRs (≥ 2%) included anemia (4.6%), peripheral edema (4.1%), headache (3.6%), edema and face edema (2.6% each), abnormal hepatic function (2.3%), and epistaxis (2.1%). There were 82 serious ADRs occurring in 44 (6.3%) patients (385 serious adverse events in 184 (26.2%) patients). Although 11 (1.6%) interstitial lung disease (ILD) cases were reported, all were observed in patients with disease that may contribute to ILD and therefore it is difficult to assess if ambrisentan was associated with these events. There was no difference in safety in relation to the presence/absence of connective tissue disease-related PAH (CTD-PAH) or combination therapy. Among 677 patients subjected to efficacy analysis, those in whom hemodynamic status was determined before and after treatment showed improvement in the mean pulmonary arterial pressure and pulmonary vascular resistance after treatment. The interim results showed safety consistent with the known profile of ambrisentan in terms of the types and frequencies of ADRs in patients with PAH in real clinical practice, in comparison with

  1. The Safety Assessment of Long term Interim Storage at Sellafield

    International Nuclear Information System (INIS)

    Buchan, Andrew B.

    2014-01-01

    that are most significant in terms of frequency and unmitigated potential consequences PSA looks at the full range of fault sequences and allows full incorporation of the reliability and failure probability of the safety measures and other features of the design and operations SAA considers significant but unlikely accidents where off-site consequences are likely to significantly affect the critical group and provides information on their progression, within the facility and also beyond the site boundary. The paper will illustrate how these techniques have been utilised to facilitate design, operation, resilience evaluation and accident management of facilities supporting long term interim storage at Sellafield. (author)

  2. The nuclear law: safety. 2006-2010

    International Nuclear Information System (INIS)

    Bringuier, P.

    2010-01-01

    The author discusses the legal evolutions related to nuclear safety between 2006 and 2010. He identifies three main topics of unequal importance. Firstly, he comments the implementation of an international reference framework which has been completed at the European level and which aims at the harmonization of safety and security rules. Secondly, he comments the creation of the French Nuclear Safety Authority (ASN, Autorite de Surete Nucleaire). Thirdly, he comments the recast of the standard framework in order to update the French law with respect to the international reference framework. This leaded to a new distribution of power and authority, to more complete and constraining procedures, and to the definition of procedures for each step of an installation life cycle

  3. ASN annual report 2007 - ASN report abstracts on the state of Nuclear Safety and Radiation Protection in France in 2007

    International Nuclear Information System (INIS)

    2008-01-01

    The 2007 annual report of the French nuclear safety authority (ASN) presents the highlights of the year in the domain of nuclear safety and radiation protection in France. The year 2007 was marked by the implementation of a new legislative and regulatory framework created by the 13 June 2006 Act on transparency and security in the nuclear field (TSN) and the 28 June Act on the sustainable management of radioactive materials and wastes. As in the previous two years, the year was relatively satisfactory from the nuclear safety viewpoint and slightly less so with regard to small-scale nuclear activities. For two years now, the medical field has been marked by the declaration to ASN of a number of serious radiotherapy accidents which have led to several deaths or the need for extensive surgery. The following main topics are reviewed in the document: 1 - the decrees implementing the 'TSN' act and the 'Waste' act; 2 - the new ASN, one year on; 3 - ASN regulatory actions in the field of radiotherapy; 4 - regulation of new installations; 5 - the key issues for regulation of existing installations; 6 - nuclear safety and radiation protection research; 7 - policy for management of the post-accident phase of a radiological emergency; 8 - sites and soils polluted by radioactive materials; 9 - international harmonization of nuclear safety and radiation protection

  4. Relation between diet cost and Healthy Eating Index 2010 scores among adults in the United States 2007-2010.

    Science.gov (United States)

    Rehm, Colin D; Monsivais, Pablo; Drewnowski, Adam

    2015-04-01

    Food prices may be one reason for the growing socioeconomic disparities in diet quality. To evaluate the association between diet costs and the Healthy Eating Index-2010 (HEI-2010). Cross-sectional study based on 11,181 adults from the 2007-2010 National Health and Nutrition Examination Survey, analyzed in spring 2014. Diet cost was estimated by linking dietary data with a national food price database. The HEI-2010, a measure of adherence to the dietary guidelines, was the outcome. The population ratio method was used to estimate the average HEI-2010 scores by quintile of energy-adjusted diet cost. Additional analyses evaluated the association between cost and HEI-2010 components. There was a strong positive association between lower energy-adjusted diet costs and lower HEI-2010 scores. The association was stronger among women (p-interaction=0.003). Lower diet costs were associated with lower consumption of vegetables, fruits, whole grains, and seafood, and higher consumption of refined grains and solid fat, alcohol and added sugars. Lower energy-adjusted diet costs were associated with lower-quality diets. Future efforts to improve the nutritional status of the US public should take food prices and diet costs into account. Copyright © 2015. Published by Elsevier Inc.

  5. Relation between diet cost and Healthy Eating Index 2010 scores among adults in the United States 2007-2010

    Science.gov (United States)

    Rehm, Colin D.; Monsivais, Pablo; Drewnowski, Adam

    2016-01-01

    Background Food prices may be one reason for the growing socioeconomic disparities in diet quality. Objective To evaluate the association between diet costs and the Healthy Eating Index-2010 (HEI-2010). Methods Cross-sectional study based on 11,181 adults from the 2007-2010 National Health and Nutrition Examination Survey, analyzed in spring 2014. Diet cost was estimated by linking dietary data with a national food price database. The HEI-2010, a measure of adherence to the Dietary Guidelines, was the outcome. The population ratio method was used to estimate the average HEI-2010 scores by quintile of energy-adjusted diet cost. Additional analyses evaluated the association between cost and HEI-2010 components. Results There was a strong positive association between lower energy-adjusted diet costs and lower HEI-2010 scores. The association was stronger among women (p-interaction=0.003). Lower diet costs were associated with lower consumption of vegetables, fruit, whole grains, and seafood, and higher consumption of refined grains and solid fat, alcohol and added sugars. Conclusions Lower energy-adjusted diet costs were associated with lower-quality diets. Future efforts to improve the nutritional status of the US public should take food prices and diet costs into account. PMID:25625693

  6. IAEA safety glossary. Terminology used in nuclear safety and radiation protection, multilingual 2007 edition, including the IAEA safety fundamentals [no. SF-1

    International Nuclear Information System (INIS)

    2008-10-01

    The IAEA Safety Glossary defines and explains technical terms used in the IAEA Safety Standards and other safety related IAEA publications, and provides information on their usage.The publication is multilingual and covers the six official IAEA languages,, Arabic, Chinese, English, French, Russian and Spanish. It has been in use since April 2000. The 2007 Edition is a revised and updated version. The primary purpose of the publication is to harmonize terminology and usage in the IAEA Safety Standards. It is a source of information for users of the IAEA Safety Standards and other safety related IAEA publications and provides guidance for the drafters and reviewers of publications, including IAEA technical officers and consultants, and members of technical committees, advisory groups, working groups and bodies for the endorsement of safety standards

  7. Plan for safety case of spent fuel repository at Olkiluoto

    International Nuclear Information System (INIS)

    Vieno, T.; Ikonen, A.T.K.

    2005-02-01

    analyse the evolution of the disposal system from the emplacement of the first canisters in the repository over the various transient phases into the far future. Radiation safety and fulfilment of regulatory requirements will mainly be dealt with in the Biosphere assessment, Radionuclide transport (safety assessment) and Complementary evaluations of safety (e.g. natural analogues) reports. The Summary report draws together the key findings and arguments. According to the outlined overall schedule, new reports on Site, Characteristics of spent fuel, Canister design, Repository design, and Evolution of site and repository should be available by 2006. The central contents for the Safety Case interim reporting will then be provided by the Process report (published in 2004) and the Evolution report. By 2009, a first or second version of each main report of the Safety Case should already be available. The central contents for the outline and preliminary assessments of the Safety Case will then be provided by the Site, Process, Radionuclide transport and Complementary evaluations reports compiled between 2007 and 2009. The final reports for the Safety Case supporting the construction license application will be compiled in 2010-2012. The Safety Case Plan will be updated along the progress of the Safety Case, for example, in association with the interim reporting of 2006 and 2009. (orig.)

  8. Sodium intake status in United States and potential reduction modeling: an NHANES 2007-2010 analysis.

    Science.gov (United States)

    Agarwal, Sanjiv; Fulgoni, Victor L; Spence, Lisa; Samuel, Priscilla

    2015-11-01

    Limiting dietary sodium intake has been a consistent dietary recommendation. Using NHANES 2007-2010 data, we estimated current sodium intake and modeled the potential impact of a new sodium reduction technology on sodium intake. NHANES 2007-2010 data were used to assess current sodium intake. The National Cancer Institute method was used for usual intake determination. Suggested sodium reductions using SODA-LO (®) Salt Microspheres ranged from 20% to 30% in 953 foods and usual intakes were modeled by using various reduction factors and levels of market penetration. SAS 9.2, SUDAAN 11, and NHANES survey weights were used in all calculations with assessment across gender and age groups. Current (2007-2010) sodium intake (mg/day) exceeds recommendations across all age gender groups and has not changed during the last decade. However, sodium intake measured as a function of food intake (mg/g food) has decreased significantly during the last decade. Two food categories contribute about 2/3rd of total sodium intake: "Grain Products" and "Meat, Poultry, Fish & Mixtures". Sodium reduction, with 100% market penetration of the new technology, was estimated to be 230-300 mg/day or 7-9% of intake depending upon age and gender group. Sodium reduction innovations like SODA-LO (®) Salt Microspheres could contribute to meaningful reductions in sodium intake.

  9. 75 FR 13484 - Foreign-Trade Zone 22; Temporary/Interim Manufacturing Authority; LG Electronics Mobilecomm USA...

    Science.gov (United States)

    2010-03-22

    ... DEPARTMENT OF COMMERCE [Docket T-1-2010] Foreign-Trade Zones Board Foreign-Trade Zone 22; Temporary/Interim Manufacturing Authority; LG Electronics Mobilecomm USA, Inc. (Cell Phones); Notice of.../ interim manufacturing (T/IM) authority, on behalf of LG Electronics Mobilecomm USA, Inc. (LGEMU), to...

  10. Report transparency and nuclear safety 2007 CEA Saclay; Rapport transparence et securite nucleaire 2007 CEA Saclay

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This report presents the activities of the CEA Center of Saclay for the year 2007. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially two public consultation on release authorizations and the Neurospin installations, the dismantling of the 49 nuclear installation, the shutdown of the learning reactor ULYSSE are detailed. (A.L.B.)

  11. IEA SHC Task 38 'Solar air-conditioning and refrigeration'. Danish participation 2007-2010. Appendix; IEA SHC Task 38 'Solar air-conditioning and refrigeration'. Dansk deltagelse 2007-2010. Bilag

    Energy Technology Data Exchange (ETDEWEB)

    Ellehauge, K. (Ellehauge og Kildemoes, Aarhus (Denmark)); Muenster, E. (PlanEnergi, Skoerping (Denmark)); Reinholdt, L. (Teknologisk Institut, Aarhus (Denmark)); Munds, S. (AC-Sun Aps, Horsens (Denmark))

    2011-03-15

    IEA SHC Task 38 'Solar Air-Conditioning and Refrigeration' ran from October 2006 to December 2010. Denmark was represented in the task from January 2007 to December 2010. The aim of the task was to encourage use of solar powered refrigeration and air conditioning systems in particular at residential, commercial and industrial sectors. Furthermore, the aim was to contribute to new research and development activities on new systems and concepts. The appendix contains the publications prepared by the Danish project group.(LN)

  12. 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

  13. 40 CFR 57.302 - Performance level of interim constant controls.

    Science.gov (United States)

    2010-07-01

    ... correction of the effects of any serious deficiencies in the system. For the purpose of this paragraph, at... system if the smelter owner has not upgraded serious deficiencies in the constant control system in... 40 Protection of Environment 5 2010-07-01 2010-07-01 false Performance level of interim constant...

  14. Final Hazard Classification and Auditable Safety Analysis for the 105-F Building Interim Safe Storage Project

    International Nuclear Information System (INIS)

    Rodovsky, T.J.; Bond, S.L.

    1998-07-01

    The auditable safety analysis (ASA) documents the authorization basis for the partial decommissioning and facility modifications to place the 105-F Building into interim safe storage (ISS). Placement into the ISS is consistent with the preferred alternative identified in the Record of Decision (58 FR). Modifications will reduce the potential for release and worker exposure to hazardous and radioactive materials, as well as lower surveillance and maintenance (S ampersand M) costs. This analysis includes the following: A description of the activities to be performed in the course of the 105-F Building ISS Project. An assessment of the inventory of radioactive and other hazardous materials within the 105-F Building. Identification of the hazards associated with the activities of the 105-F Building ISS Project. Identification of internally and externally initiated accident scenarios with the potential to produce significant local or offsite consequences during the 105-F Building ISS Project. Bounding evaluation of the consequences of the potentially significant accident scenarios. Hazard classification based on the bounding consequence evaluation. Associated safety function and controls, including commitments. Radiological and other employee safety and health considerations

  15. 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

  16. 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.

  17. The national plan of radioactive materials and wastes management. 2010-2012 edition

    International Nuclear Information System (INIS)

    2010-01-01

    This short presentation, given by the nuclear safety authority (ASN) at the meeting of January 26, 2010 of the high committee for the nuclear safety transparency and information (HCTISN), describes the different stages of the elaboration of the new edition of the French national plan of radioactive materials and wastes management (PNGMDR). The plan comprises 3 parts: the principles and objectives of the radioactive materials and wastes management, the status of existing procedures and of procedures still under development by the end of 2009, the improvements made. The topics concern: the interim storage, the long-term management and the global consistency of the plan. (J.S.)

  18. Online interactive tutorials for creating graphs with excel 2007 or 2010.

    Science.gov (United States)

    Vanselow, Nicholas R; Bourret, Jason C

    2012-01-01

    Graphic display of clinical data is a useful tool for the behavior-analytic clinician. However, graphs can sometimes be difficult to create. We describe how to access and use an online interactive tutorial that teaches the user to create a variety of graphs often used by behavior analysts. Three tutorials are provided that cover the basics of Microsoft Excel 2007 or 2010, creating graphs for clinical purposes, and creating graphs for research purposes. The uses for this interactive tutorial and other similar programs are discussed.

  19. Report transparency and nuclear safety 2007 CEA Cadarache; Rapport transparence et securite nucleaire 2007 CEA Cadarache

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This report presents the activities of the CEA Center of Cadarache for the year 2007. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially the report discusses the beginning of the RJH reactor construction, the fourth generation reactors research programs, the implementing of la Rotonde the new radioactive wastes management installation, the renovation of the LECA. (A.L.B.)

  20. Report transparency and nuclear safety 2007 CEA Marcoule; Rapport transparence et securite nucleaire 2007 CEA Marcoule

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This report presents the activities of the CEA Center of Marcoule for the year 2007. Since its creation in 1955 the center realizes industrial and scientific activities relative to the civil and military applications of the radioactivity. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially the following two base activities are detailed: Atalante and Phenix. (A.L.B.)

  1. Nuclear criticality safety evaluation of the passage of decontaminated salt solution from the ITP filters into tank 50H for interim storage

    International Nuclear Information System (INIS)

    Hobbs, D.T.; Davis, J.R.

    1994-01-01

    This report assesses the nuclear criticality safety associated with the decontaminated salt solution after passing through the In-Tank Precipitation (ITP) filters, through the stripper columns and into Tank 50H for interim storage until transfer to the Saltstone facility. The criticality safety basis for the ITP process is documented. Criticality safety in the ITP filtrate has been analyzed under normal and process upset conditions. This report evaluates the potential for criticality due to the precipitation or crystallization of fissionable material from solution and an ITP process filter failure in which insoluble material carryover from salt dissolution is present. It is concluded that no single inadvertent error will cause criticality and that the process will remain subcritical under normal and credible abnormal conditions

  2. Safety aspects of spent nuclear fuel interim storage installations

    Energy Technology Data Exchange (ETDEWEB)

    Romanato, Luiz Sergio [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), Sao Paulo, SP (Brazil). Dept. da Qualidade. Div. de Sistemas da Qualidade]. E-mail: romanato@ctmsp.mar.mil.br; Rzyski, Barbara Maria [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil). Div. de Ensino]. E-mail: bmrzyski@ipen.br

    2007-07-01

    Nowadays safety and security of spent nuclear fuel (SNF) interim storage installations are very important, due to a great concentration of fission products, actinides and activation products. In this kind of storage it is necessary to consider the physical security. Nuclear installations have become more vulnerable. New types of accidents must be considered in the design of these installations, which in the early days were not considered like: fissile material stolen, terrorists' acts and war conflicts, and traditional accidents concerning the transport of the spent fuel from the reactor to the storage location, earthquakes occurrence, airplanes crash, etc. Studies related to airplane falling had showed that a collision of big commercials airplanes at velocity of 800 km/h against SNF storage and specially designed concrete casks, do not result in serious structural injury to the casks, and not even radionuclides liberation to the environment. However, it was demonstrated that attacks with modern military ammunitions, against metallic casks, are calamitous. The casks could not support a direct impact of this ammo and the released radioactive materials can expose the workers and public as well the local environment to harmful radiation. This paper deals about the main basic aspects of a dry SNF storage installation, that must be physically well protected, getting barriers that difficult the access of unauthorized persons or vehicles, as well as, must structurally resist to incidents or accidents caused by unauthorized intrusion. (author)

  3. Safety aspects of spent nuclear fuel interim storage installations

    International Nuclear Information System (INIS)

    Romanato, Luiz Sergio

    2007-01-01

    Nowadays safety and security of spent nuclear fuel (SNF) interim storage installations are very important, due to a great concentration of fission products, actinides and activation products. In this kind of storage it is necessary to consider the physical security. Nuclear installations have become more vulnerable. New types of accidents must be considered in the design of these installations, which in the early days were not considered like: fissile material stolen, terrorists' acts and war conflicts, and traditional accidents concerning the transport of the spent fuel from the reactor to the storage location, earthquakes occurrence, airplanes crash, etc. Studies related to airplane falling had showed that a collision of big commercials airplanes at velocity of 800 km/h against SNF storage and specially designed concrete casks, do not result in serious structural injury to the casks, and not even radionuclides liberation to the environment. However, it was demonstrated that attacks with modern military ammunitions, against metallic casks, are calamitous. The casks could not support a direct impact of this ammo and the released radioactive materials can expose the workers and public as well the local environment to harmful radiation. This paper deals about the main basic aspects of a dry SNF storage installation, that must be physically well protected, getting barriers that difficult the access of unauthorized persons or vehicles, as well as, must structurally resist to incidents or accidents caused by unauthorized intrusion. (author)

  4. Plant safety in France 2000 until 2010; Anlagensicherheitspolitik in Frankreich 2000 bis 2010

    Energy Technology Data Exchange (ETDEWEB)

    Vallee, Agnes; Affeltranger, Bastien; Descourriere, Sandrine; Oger, Florence; Duval, Christophe; Gaucher, Rodolphe [Institut National de l' Environnement Industriel et des Risques (INERIS), 60 - Verneuil-en-Halatte (France)

    2013-03-15

    The study on the safety of industrial plants on France covers the following issues: The explosion in the operational area of AZF (plant Grande Paroisse) and the consequences; classified installations; the players of accident risks in France; realization of the accident prevention policy in France from 2000 to 2010; prevention of natural risks and consideration of these risks on the level of classified installations (NATECH accidents) in France from 2000 to 2010; further specific topics; actual activities and developments.

  5. Fourth national report of Brazil for the nuclear safety convention. Sep. 2007

    International Nuclear Information System (INIS)

    2007-09-01

    This Fourth National Report of Brazil is a new update to include relevant information of the period of 2004-2007. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

  6. Fourth national report of Brazil for the nuclear safety convention. Sep. 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-09-15

    This Fourth National Report of Brazil is a new update to include relevant information of the period of 2004-2007. This document represents the national report prepared as a fulfillment of the brazilian obligations related to the Convention on Nuclear Safety. In chapter 2 some details are given about the existing nuclear installations. Chapter 3 provides details about the legislation and regulations, including the regulatory framework and the regulatory body. Chapter 4 covers general safety considerations as described in articles 10 to 16 of the Convention. Chapter 5 addresses to the safety of the installations during siting, design, construction and operation. Chapter 6 describes planned activities to further enhance nuclear safety. Chapter 7 presents the final remarks related to the degree of compliance with the Convention obligations

  7. Socioeconomic burden of influenza in the Republic of Korea, 2007-2010.

    Directory of Open Access Journals (Sweden)

    Mina Suh

    Full Text Available BACKGROUND: Although the socioeconomic burden of 2009 pandemic influenza A (H1N1 was considerable, no reliable estimates have been reported. Our aim was to compared medical costs and socioeconomic burden resulting from pandemic influenza A (H1N1 2009 with that of previous seasonal influenza. METHODS: We estimated the medical costs and socioeconomic burden of influenza from May 2007 to April 2010. We used representative national data sources(data from the Health Insurance Review Agency, the National Health Insurance Corporation, the Korea Centers for Disease Control and Prevention, and the Korean National Statistics Office including medical utilization, prescription of antivirals, and vaccination. Uncertainty of data was explored through sensitivity analysis using Monte Carlo simulation. RESULTS: Compared with the seasonal influenza, total medical costs (US$291.7 million associated with pandemic (H1N1 2009 increased more than 37-fold. Compared with the 2007-2008 season, outpatient diagnostic costs (US$135.3 million were 773 times higher in the 2009-2010 season, and the mean diagnostic cost per outpatient visit was 58.8 times higher. Total socioeconomic burden of pandemic (H1N1 2009 was estimated at US$1581.3 million (10%-90%: US$1436.0-1808.3 million and those of seasonal influenza was estimated at US$44.7 million (10%-90%: US$32.4-57.9 million in 2007-2008 season and US$42.3 million (10%-90%: US$31.5-53.8 million in 2008-2009 season. Indirect costs accounted for 56.0% of total costs in pandemic (H1N1 2009, and 66.48-68.09% in seasonal influenza. The largest contributors to total burden were productivity losses of caregiver in pandemic (H1N1 2009, and productivity losses due to morbidity of outpatient in seasonal influenza. CONCLUSIONS: In the Republic of Korea, socioeconomic burden of pandemic (H1N1 2009 were considerably higher than burden of the previous two influenza seasons, primarily because of high diagnostic costs and longer sick leave.

  8. Changes in the sodium content of bread in Australia and New Zealand between 2007 and 2010: implications for policy.

    Science.gov (United States)

    Dunford, Elizabeth K; Eyles, Helen; Mhurchu, Cliona Ni; Webster, Jacqui L; Neal, Bruce C

    2011-09-19

    To define the effectiveness of recent efforts by the Australian Division of World Action on Salt and Health, and the Heart Foundation in New Zealand to reduce sodium levels in breads in Australia and New Zealand. Data on the sodium contents of packaged sliced bread products sold in Australian and New Zealand supermarkets were collected from the product labels of 157 breads in 2007 and 167 breads in 2010, and were compared overall, by bread type, by manufacturer, and between nations. Mean sodium values in bread and proportions of breads meeting the targets of 400 mg/100 g in Australia and 450 mg/100 g in New Zealand. Overall mean sodium content in bread in Australia was 434 mg/100 g in 2007 and 435 mg/100 g in 2010; corresponding values for New Zealand were 469 mg/100 g and 439 mg/100 g. The proportion of Australian breads meeting the national target increased from 29% in 2007 to 50% in 2010; the proportion of New Zealand breads meeting the national target increased from 49% in 2007 to 90% in 2010. There were clear differences between the results achieved by different companies. Voluntary efforts by non-governmental organisations have had some impact on sodium levels in bread, particularly in New Zealand. However, substantial room for further improvement remains. If additional reductions are not achieved under the current voluntary arrangements, legislated approaches may be required.

  9. National report of the Slovak Republic. Compiled in terms of the convention on nuclear safety. May 2007

    International Nuclear Information System (INIS)

    Balaj, J.; Konecny, L.; Rovny, J.; Metke, E.; Zemanova, D.; Turner, M.; Pospisil, M.; Jurina, V.; Rivny, I.; Soltes, L.; Petrik, T.; Petrovic, J.; Fazekasova, H.; Kobzova, D.; Trcka, T.; Maudry, J.; Betak, A.; Capkovic, J.

    2007-05-01

    A brief national safety report of the Slovak Republic compiled in terms of the joint convention on nuclear safety in 2007 is presented. This safety report consists of following chapters: (1) Introduction; (2) Nuclear installations in the Slovak Republic in terms of the Convention; (C) Scope of application; (3) Legislation and regulation; (4) General safety aspects; (5) Safety of nuclear installations in Slovakia; (6) Annexes

  10. 75 FR 29385 - Safety Advisory 2010-01

    Science.gov (United States)

    2010-05-25

    .... Conduct a visual inspection of the vertical hand brake supports for cracks or evidence of a stanchion that... Supports on FTTX Flatcars. SUMMARY: FRA is issuing Safety Advisory 2010-01 in order to provide guidance to... hand brake supports that have been modified to accommodate a 10-inch wide hand brake step. FRA's Office...

  11. Safety and Radiation Protection at Swedish Nuclear Power Plants 2007

    Energy Technology Data Exchange (ETDEWEB)

    2008-07-01

    transparent basis for making decisions in safety matters. During the year it has however become apparent that further improvement measures are necessary. The plant has had a relatively large number of operational disturbances during 2007 which have been analysed in order to implement suitable measures. Modernisation projects follow the time schedules which were decided earlier for implementation in order to comply with the regulations. Some measures are already completed, others are underway, and the programme will continue until 2013. SKI is supervising the progress of the modernisation and the improvements to the physical protection of the plants. Forsmark Kraftgrupp AB has applied for permission to increase the thermal power in reactors Forsmark 1-3. The government hasn't yet granted permission for these power increases. SKI has approved trial operation for Ringhals 1 and Ringhals 3 at the increased power levels during the year. For Ringhals 3 this is the first stage of the planned power increases. Ringhals has also applied to increase the thermal power in Ringhals 4. The government has granted permission for the thermal power increase in Oskarshamn 3. SKI is currently performing a safety review of this application. Oskarshamn have made an application to increase the thermal power in Oskarshamn 2. During 2007 SKI has performed inspections to control how nuclear safeguards are managed by the nuclear power stations. In all 80 inspections have been carried out. Nothing has been found during these inspections to indicate that there are any deficiencies in the nuclear safeguard activities. No serious incidents or accidents have occurred resulting in abnormal radiation exposure of personnel. Radioactive releases from the plants have resulted in calculated doses to the most exposed person in the critical group that are well below the environmental impact goal of 10 microsievert. Forsmark, which in recent years has had recurrent problems with the measurement of airborne

  12. Ex-ante assessment of the Spanish Occupational Health and Safety Strategy (2007–2012) using a State Space framework

    International Nuclear Information System (INIS)

    Carnero, María del Carmen; Pedregal, Diego José

    2013-01-01

    Spain is above the EU-27, EU-25 and EU-15 average in the number of serious work accidents, and it is estimated that Spain is five years behind the rest of Europe in reducing such accidents. To address the problem of the high number of occupational accidents, in 2007 the Spanish Occupational Health and Safety Strategy (SOHSS, 2007–2012) was launched, with the general aim of achieving a continuous and significant reduction in work accidents, approaching the EU average in occupational accidents and illness. This article is an attempt to assess the extent to which the aims of the SOHSS have been satisfied by predicting incidence rates for different levels of accident severity (slight, serious and fatal), accidents that do not require sick leave, and commuting accidents (slight, serious and fatal). With these objectives in mind, both Univariate and Multivariate Unobserved Components models are used in an enhanced State Space framework in order to deal with the irregular sampling interval of the data from 1998 to 2010.

  13. 76 FR 31350 - Cruise Vessel Safety and Security Act of 2010, Available Technology

    Science.gov (United States)

    2011-05-31

    ... DEPARTMENT OF HOMELAND SECURITY Coast Guard [Docket No. USCG-2011-0357] Cruise Vessel Safety and Security Act of 2010, Available Technology AGENCY: Coast Guard, DHS. ACTION: Notice of request for comments... Security and Safety Act of 2010(CVSSA), specifically related to video recording and overboard detection...

  14. Safety critical systems handbook a straightforward guide to functional safety : IEC 61508 (2010 edition) and related standards

    CERN Document Server

    Smith, David J

    2010-01-01

    Electrical, electronic and programmable electronic systems increasingly carry out safety functions to guard workers and the public against injury or death and the environment against pollution. The international functional safety standard IEC 61508 was revised in 2010, and this is the first comprehensive guide available to the revised standard. As functional safety is applicable to many industries, this book will have a wide readership beyond the chemical and process sector, including oil and gas, power generation, nuclear, aircraft, and automotive industries, plus project, instrumentation, design, and control engineers. * The only comprehensive guide to IEC 61508, updated to cover the 2010 amendments, that will ensure engineers are compliant with the latest process safety systems design and operation standards* Helps readers understand the process required to apply safety critical systems standards* Real-world approach helps users to interpret the standard, with case studies and best practice design examples...

  15. Sickness presence in the Swedish Police in 2007 and in 2010: Associations with demographic factors, job characteristics, and health.

    Science.gov (United States)

    Taloyan, Marina; Kecklund, Göran; Thörn, Licia; Kjeldgård, Linnea; Westerlund, Hugo; Svedberg, Pia; Alexanderson, Kristina

    2016-06-23

    Sickness presence (SP) is a complex phenomenon that has been shown to predict sickness absence, poor work performance, and suboptimal self-rated health. However, more research is needed to increase the understanding of how SP relates to occupational factors, demographic variables, and self-rated health. The aims of this study were to investigate (1) the prevalence of SP among the Police employees in Sweden in 2007 and in 2010; (2) the association between demographics, seniority, occupational group (police officer vs civil servant), and self-reported health on the one hand and SP on the other hand for both years separately. Survey data from Swedish Police employees from 2007 (n = 17,512) and 2010 (n = 18,415) were analyzed using logistic regression to assess odds ratios (OR) and 95% confidence intervals (CI). The prevalence of SP was stable between the years, but the proportion who stated that they had not been ill at all decreased from 2007 to 2010 (28.0% vs. 23.6%), while the proportion stating always having stayed at home when ill did not differ; 45.0% in 2007 to 45.8% in 2010. The ORs of SP were higher among those with suboptimal self-rated health compared to those with optimal self-rated health (4.38 (95% CI 4.02- 4.78) and 4.31 (3.96- 4.70) in 2007 and 2010, respectively) and among police officers compared with civilians (1.26 (1.17-1.36) and 1.19 (1.10-1.28)), whereas no clear patterns were found for age, gender, and seniority. The prevalences of SP were about the same in 2007 and 2010 and were slightly lower compared to in previous studies. The strong association between SP and suboptimal self-rated health suggests that high levels of SP may be an early marker of future illness and sickness absence. In future studies of SP it is important to account for having been ill, that is, at risk of SP.

  16. Pre- and post-construction studies of conflicts between birds and wind turbines in coastal Norway (BirdWind). Report on findings 2007-2010

    OpenAIRE

    Bevanger, Kjetil Modolv; Berntsen, Finn Erik Harald; Clausen, Stig Morten; Dahl, Espen Lie; Flagstad, Øystein; Follestad, Arne; Halley, Duncan John; Hanssen, Frank Ole; Johnsen, Lars; Kvaløy, Pål; Lund-Hoel, Pernille*; May, Roelof Frans; Nygård, Torgeir; Pedersen, Hans-Christian; Reitan, Ole

    2011-01-01

    Bevanger, K., Berntsen, F., Clausen, S., Dahl, E.L., Flagstad, Ø. Follestad, A., Halley, D., Hanssen, F., Johnsen, L., Kvaløy, P., Lund-Hoel, P., May, R., Nygård, T., Pedersen, H.C., Reitan, O., Røskaft, E., Steinheim, Y., Stokke, B. & Vang, R. 2010. Pre- and post-construction studies of conflicts between birds and wind turbines in coastal Norway (BirdWind). Report on findings 2007-2010. – NINA Report 620. 152 pp. The BirdWind project (2007-2010) is now concluded. This report summarises th...

  17. System and safety studies of accelerator driven systems for transmutation. Annual report 2007

    International Nuclear Information System (INIS)

    Arzhanov, Vasily; Fokau, Andrei; Persson, Calle; Runevall, Odd; Sandberg, Nils; Tesinsky, Milan; Wallenius, Janne; Youpeng Zhang

    2008-05-01

    Within the project 'System and safety studies of accelerator driven systems for transmutation', research on design and safety of sub-critical reactors for recycling of minor actinides is performed. During 2007, the reactor physics division at KTH has calculated safety parameters for EFIT-400 with cermet fuel, permitting to start the transient safety analysis. The accuracy of different reactivity meters applied to the YALINA facility was assessed and neutron detection studies were performed. A model to address deviations from point kinetic behaviour was developed. Studies of basic radiation damage physics included calculations of vacancy formation and activation enthalpies in bcc niobium. In order to predict the oxygen potential of inert matrix fuels, a thermo-chemical model for mixed actinide oxides was implemented in a phase equilibrium code

  18. IRSN's viewpoint on the safety and radiation protection of French nuclear power plants in 2007

    International Nuclear Information System (INIS)

    2009-01-01

    This report presents the viewpoint of the IRSN on the safety and radiation protection of EDF's nuclear power plants (NPPs) in operation during 2007. It does not aim to be exhaustive but rather to highlight the points the IRSN considers important for safety. Contributing to maintaining a high level of safety and radiation protection in nuclear facilities in service is one of the seven challenges of the objectives contract signed between the French Government and the IRSN. Safety demands constant vigilance on the part of all the players involved. It is never definitively acquired and must remain a priority and continuously progress, with the plant operator remaining the first entity responsible for the safety of its facility. For the IRSN, part of this mission firstly involves carefully examining and taking into consideration national and international experience feedback, and new scientific knowledge resulting from research. The implementation of improvements, whether technical or organizational or relating to human skills, then comes secondly. This report comprises four sections. In the first section, the IRSN presents the main trends that emerged from its overall review of the safety of the in-service nuclear power plants. The second section addresses the events that have marked the year due to their impact on safety. It also presents a synthesis of the radiation protection events. The third section is devoted to anomalies displaying a generic nature for several power plants. The last section covers the significant changes implemented or scheduled. These are generally modifications or plans of action intended to improve safety performance in the operation or design of the facilities. In spite of sometimes significant disparities in the results between power plants, the IRSN draws the following conclusions from its global review of the year 2007. First of all, no event had serious consequences in the fields of either safety or radioprotection. This good result must

  19. Skin Infections and Antibiotic Stewardship: Analysis of Emergency Department Prescribing Practices, 2007-2010

    Directory of Open Access Journals (Sweden)

    Daniel J. Pallin

    2014-05-01

    Full Text Available Introduction: National guidelines suggest that most skin abscesses do not require antibiotics, and that cellulitis antibiotics should target streptococci, not community-associated MRSA (CA-MRSA. The objective of this study is to describe antimicrobial treatment of skin infections in U.S. emergency departments (EDs and analyze potential quality measures. Methods: The National Hospital Ambulatory Medical Care Survey (NHAMCS is a 4-stage probability sample of all non-federal U.S. ED visits. In 2007 NHAMCS started recording whether incision and drainage was performed at ED visits. We conducted a retrospective analysis, pooling 2007-2010 data, identified skin infections using diagnostic codes, and identified abscesses by performance of incision and drainage. We generated national estimates and 95% confidence intervals using weighted analyses; quantified frequencies and proportions; and evaluated antibiotic prescribing practices. We evaluated 4 parameters that might serve as quality measures of antibiotic stewardship, and present 2 of them as potentially robust enough for implementation. Results: Of all ED visits, 3.2% (95% confidence interval 3.1-3.4% were for skin infection, and 2.7% (2.6-2.9% were first visits for skin infection, with no increase over time (p=0.80. However, anti-CA-MRSA antibiotic use increased, from 61% (56-66% to 74% (71-78% of antibiotic regimens (p<0.001. Twenty-two percent of visits were for abscess, with a non-significant increase (p=0.06. Potential quality measures: Among discharged abscess patients, 87% were prescribed antibiotics (84-90%, overuse. Among antibiotic regimens for abscess patients, 84% included anti-CA-MRSA agents (81-89%, underuse. Conclusion: From 2007-2010, use of anti-CA-MRSA agents for skin infections increased significantly, despite stable visit frequencies. Antibiotics were over-used for discharged abscess cases, and CA-MRSA-active antibiotics were underused among regimens when antibiotics were used for

  20. Practices and opinions regarding HPV vaccination among French general practitioners: evaluation through two cross-sectional studies in 2007 and 2010.

    Science.gov (United States)

    Lasset, Christine; Kalecinski, Julie; Régnier, Véronique; Barone, Giovanna; Leocmach, Yann; Vanhems, Philippe; Chauvin, Franck; Lutringer-Magnin, Delphine

    2014-06-01

    To use both quantitative and qualitative methods to investigate the evolution of practices and opinions regarding human papillomavirus (HPV) vaccination among French general practitioners. A cross-sectional study (self-questionnaires) was performed in 2007 and repeated in 2010 among 271 general practitioners. Semi-structured interviews were conducted on 27 voluntary participants by a sociologist and analyzed according to content analysis. Acceptability of HPV vaccination had increased from 2007 to 2010 (79.9 vs. 87.1%, respectively), just as the practice of HPV vaccination among 14-year-old girls (19.0 vs. 49.1%, respectively). Though about 60% reported complications associated with HPV vaccination, irrespective of year, the types of difficulties have varied: difficulties related to "questions asked by patients" had decreased, though concerns about side effects had remained stable. During interviews, difficulties related to "the reason for medical consultation" and "the target age" were often associated with addressing the issue of sexuality, especially when the parents were present. Although the high level of acceptability of HPV vaccination among general practitioners, which increased from 2007 to 2010, there remain difficulties in addressing this practice.

  1. Nuclear Safety Review for the Year 2007

    International Nuclear Information System (INIS)

    2008-07-01

    In 2007, the 50th anniversary year of the Agency, the safety performance of the nuclear industry, on the whole, remained high, although incidents and accidents with no significant impact on public health and safety continue to make news headlines and challenge operators and regulators. It is therefore essential to maintain vigilance, continuously improve safety culture and enhance the international sharing and utilization of operating and other safety experience, including that resulting from natural events. The establishment and sustainability of infrastructures for all aspects of nuclear, radiation, transport and waste safety will remain a high priority. Member States embarking on nuclear power programmes will need to be active participants in the global nuclear safety regime. Harmonized safety standards, the peer review mechanism among contracting parties of the safety conventions, and sharing safety knowledge and best practices through networking are key elements for the continuous strengthening of the global nuclear safety regime. Technical and scientific support organizations (TSOs), whether part of the regulatory body or a separate organization, are gaining increased importance by providing the technical and scientific basis for safety related decisions and activities. There is a need for enhanced interaction and cooperation between TSOs. Academic and industrial expert communities also play a vital role in improving safety cooperation and capacity building. Countries embarking on nuclear power programmes, as well as countries expanding existing programmes, have to meet the challenge of building a technically qualified workforce. A vigorous knowledge transfer programme is key to capacity building - particularly in view of the ageing of experienced professionals in the nuclear field. National and regional safety networks, and ultimately a global safety network will greatly help these efforts. Changes in world markets and technology are having an impact on both

  2. Safety evaluation for the interim stabilization of Tank 241-C-103

    Energy Technology Data Exchange (ETDEWEB)

    Geschke, G.R.

    1995-03-01

    This document provides the basis for interim stabilization of tank 241-C-103. The document covers the removal of the organic liquid layer and the aqueous supernatant from tank 241-C-103. Hazards are identified, consequences are calculated and controls to mitigate or prevent potential accidents are developed.

  3. Safety evaluation for the interim stabilization of Tank 241-C-103

    International Nuclear Information System (INIS)

    Geschke, G.R.

    1995-03-01

    This document provides the basis for interim stabilization of tank 241-C-103. The document covers the removal of the organic liquid layer and the aqueous supernatant from tank 241-C-103. Hazards are identified, consequences are calculated and controls to mitigate or prevent potential accidents are developed

  4. System and safety studies of accelerator driven systems for transmutation. Annual report 2007

    Energy Technology Data Exchange (ETDEWEB)

    Arzhanov, Vasily; Fokau, Andrei; Persson, Calle; Runevall, Odd; Sandberg, Nils; Tesinsky, Milan; Wallenius, Janne; Youpeng Zhang (Div. of Reactor Physics, Royal Institute of Technology, Stockholm (Sweden))

    2008-05-15

    Within the project 'System and safety studies of accelerator driven systems for transmutation', research on design and safety of sub-critical reactors for recycling of minor actinides is performed. During 2007, the reactor physics division at KTH has calculated safety parameters for EFIT-400 with cermet fuel, permitting to start the transient safety analysis. The accuracy of different reactivity meters applied to the YALINA facility was assessed and neutron detection studies were performed. A model to address deviations from point kinetic behaviour was developed. Studies of basic radiation damage physics included calculations of vacancy formation and activation enthalpies in bcc niobium. In order to predict the oxygen potential of inert matrix fuels, a thermo-chemical model for mixed actinide oxides was implemented in a phase equilibrium code

  5. Genotypic diversity of Coxiella burnetii in the 2007-2010 Q fever outbreak episodes in The Netherlands

    NARCIS (Netherlands)

    Tilburg, Jeroen J. H. C.; Rossen, John W. A.; van Hannen, Erik J.; Melchers, Willem J. G.; Hermans, Mirjam H. A.; van de Bovenkamp, Jeroen; Roest, Hendrik Jan I. J.; de Bruin, Arnout; Nabuurs-Franssen, Marrigje H.; Horrevorts, Alphons M.; Klaassen, Corne H. W.

    The genotypic diversity of Coxiella burnetii in clinical samples obtained from the Dutch Q fever outbreak episodes of 2007-2010 was determined by using a 6-locus variable-number tandem repeat analysis panel. The results are consistent with the introduction of one founder genotype that is gradually

  6. Report of transparency and nuclear safety 2007 CEA Fontenay aux Roses

    International Nuclear Information System (INIS)

    2007-01-01

    This report presents the activities of the CEA Center of Fontenay aux roses for the year 2007. After many years of decommissioning and dismantling of nuclear installations, the Center is now devoted (since 2005) to the development of research programmes on biology and biomedical technologies. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. (A.L.B.)

  7. ANALISIS SPASIAL TERHADAP PERUBAHAN STATUS GIZI ANAK BALITA DI INDONESIA (RISKESDAS 2007 2010

    Directory of Open Access Journals (Sweden)

    Noviati Fuada

    2016-05-01

    Full Text Available Transitions nutritional status is a reflection of the general transition, such as demographics, food, education and health. Demographic Transition reciprocally affects the transition in nutrition/health. This analysis was aimed to identify the distribution of the area and the differentiating factor of the double burden malnutrition on the children under five. Analysis was performed using aggregated National Data from Susenas 2007-2010 and Riskesdas 2007-2010. Unit analysis is the province. Spatial analysis was done with overlay method. The Analysis showed that high levels of potentially affected areas with double burden malnutrition were all of province in Kalimantan, Sulawesi and Maluku. Additionally was DKI province, Central Java, North Sumatra, South Sumatra, Riau Islands, Bangka Belitung and Lampung. Those situation is need to be concerned especially with demographic bonus phenomena. Demographic Bonus becomes a problem, if it is not accompanied by an increment in education, skills, health. When assuming other factor remain, it is predicted that in the event of the demographic bonus, there will be also a double burden malnutrition problems. Distribution of areas that experience with double burden malnutrition, clustered in regions outside Java, it shows social disparities still exist among Indonesian, community. Susceptible areas of double burden malnutrition was spread outside Java. Namely, Kalimantan, Sulawesi, Maluku. Sumatra, Riau Islands, Bangka Belitung.

  8. Safety and Radiation Protection at Swedish Nuclear Power Plants 2007

    International Nuclear Information System (INIS)

    2008-01-01

    transparent basis for making decisions in safety matters. During the year it has however become apparent that further improvement measures are necessary. The plant has had a relatively large number of operational disturbances during 2007 which have been analysed in order to implement suitable measures. Modernisation projects follow the time schedules which were decided earlier for implementation in order to comply with the regulations. Some measures are already completed, others are underway, and the programme will continue until 2013. SKI is supervising the progress of the modernisation and the improvements to the physical protection of the plants. Forsmark Kraftgrupp AB has applied for permission to increase the thermal power in reactors Forsmark 1 - 3. The government has not as yet granted permission for these power increases. SKI has approved trial operation for Ringhals 1 and Ringhals 3 at the increased power levels during the year. For Ringhals 3 this is the first stage of the planned power increases. Ringhals has also applied to increase the thermal power in Ringhals 4. The government has granted permission for the thermal power increase in Oskarshamn 3. SKI is currently performing a safety review of this application. Oskarshamn have made an application to increase the thermal power in Oskarshamn 2. During 2007 SKI has performed inspections to control how nuclear safeguards are managed by the nuclear power stations. In all 80 inspections have been carried out. Nothing has been found during these inspections to indicate that there are any deficiencies in the nuclear safeguard activities. No serious incidents or accidents have occurred resulting in abnormal radiation exposure of personnel. Radioactive releases from the plants have resulted in calculated doses to the most exposed person in the critical group that are well below the environmental impact goal of 10 microsievert. Forsmark, which in recent years has had recurrent problems with the measurement of airborne

  9. Regulatory oversight report 2007 concerning nuclear safety in Swiss nuclear installations

    International Nuclear Information System (INIS)

    2008-04-01

    This annual report issued by the Swiss Federal Nuclear Inspectorate (HSK) reports on the work carried out by the Inspectorate in 2007. This report reviews the regulatory activities in the four Swiss nuclear power stations and in four further nuclear installations in various Swiss research facilities. It deals with topics such as operational details, technologies in use, radiation protection, radioactive wastes, emergency dispositions and personnel and provides an assessment of operations from the point of view of safety. Also, the transportation of nuclear materials - both nuclear fuels and nuclear wastes - is reported on. General topics discussed include probabilistic safety analyses and accident management. Finally, the disposal of nuclear wastes and work done in the rock laboratories in Switzerland is commented on

  10. International Peer Review of Swedish Nuclear Fuel and Waste Management Company's SR-Can interim report

    International Nuclear Information System (INIS)

    Sagar, Budhi; Bailey, Lucy; Bennett, David G.; Egan, Mike; Roehlig, Klaus

    2004-12-01

    SKB has produced an interim safety assessment report as part of its work to develop a licence application for the construction of a spent nuclear fuel encapsulation plant. The purpose of the interim report is to set out and demonstrate SKB's proposed methodology for long-term safety assessment. The aim of producing an interim report is to allow the Swedish regulatory authorities (SKI and SSI) to review and comment on SKB's proposed methodology before it is used in support of a formal licence application. To help inform their review of SKB's proposed methodology, the authorities appointed an international review team (IRT) to carry out a review of SKB's interim safety assessment report. Comments from the IRT are presented in this document and will be considered by the regulatory authorities in developing their own view of SKB's proposed methodology. The IRT's review included examination of SKB's documentation (the 'Interim Main Report of the Safety Assessment SR-Can' and four supporting documents) and hearings with SKB staff and contractors. The hearings provided an opportunity for the IRT to discuss the SR-Can safety assessment with the authors and contributors to SKB's work. As directed by SKI and SSI, the IRT's review focused on methodological aspects and sought to determine whether SKB's proposed safety assessment methodology: (i) is fit for the purpose of supporting a licence application; (ii) has a reasonable prospect of leading to a safety assessment that is sufficiently comprehensive, reproducible, traceable and transparent; (iii) is compatible with the authorities' regulations and guidance. No evaluation of long term safety or site acceptability was attempted by the IRT. At the request of SKI and SSI, the IRT's review considered and made recommendations on the following issues: Description of the initial state of the repository and its components; Description of features, events and processes (FEPs) relevant to repository evolution; Strategy for safety

  11. Review of Doctoral Research in English Language Education in the Philippines, Singapore and Malaysia (2007-2010)

    Science.gov (United States)

    Rubdy, Rani; Tupas, T. Ruanni F.; Villareal, Corazon D.; David, Maya Khemlani; Dumanig, Francisco Perlas

    2012-01-01

    This review highlights recent doctoral research in English language education and related areas completed between 2007 and 2010 in three countries in Southeast Asia: Singapore, Malaysia and the Philippines. Out of sixty dissertations initially chosen from major universities in these countries, five from the Philippines, four from Malaysia and…

  12. Ecology of Juvenile Salmon in Shallow Tidal Freshwater Habitats of the Lower Columbia River, 20072010

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, Gary E.; Storch, Adam; Skalski, J. R.; Bryson, Amanda J.; Mallette, Christine; Borde, Amy B.; Van Dyke, E.; Sobocinski, Kathryn L.; Sather, Nichole K.; Teel, David; Dawley, Earl M.; Ploskey, Gene R.; Jones, Tucker A.; Zimmerman, Shon A.; Kuligowski, D. R.

    2011-03-01

    The TFM study was designed to investigate the ecology and early life history of juvenile salmonids within shallow (<5 m) tidal freshwater habitats of the LCRE. We started collecting field data in June 2007. Since then, monthly sampling has occurred in the vicinity of the Sandy River delta (rkm 192–208) and at other sites and times in lower river reaches of tidal freshwater (rkm 110 to 141). This report provides a comprehensive synthesis of data covering the field period from June 2007 through April 2010.

  13. 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...

  14. Safety and Effectiveness of Natalizumab: First Report of Interim Results of Post-Marketing Surveillance in Japan.

    Science.gov (United States)

    Saida, Takahiko; Yokoyama, Kazumasa; Sato, Ryusuke; Makioka, Haruki; Iizuka, Yukihiko; Hase, Masakazu; Ling, Yan; Torii, Shinichi

    2017-12-01

    Natalizumab, a humanized anti-α4 integrin monoclonal antibody, received marketing approval in Japan in 2014 for the treatment of multiple sclerosis (MS). Because the previous large-scale clinical trials of natalizumab were mainly conducted in Europe and North American countries, and data in patients with MS from Japan were limited, we conducted an all-case post-marketing surveillance of natalizumab-treated MS patients from Japan to investigate the safety and effectiveness of natalizumab in a real-world clinical setting in Japan. Here, we report the results of an interim analysis. During the observation period of 2 years, all patients who were treated with natalizumab subsequent to its approval in Japan were followed. The effectiveness of natalizumab was assessed by examining the changes in expanded disability status scale (EDSS) score and annualized relapse rate (ARR) from baseline. Safety was assessed by analyzing the incidence of adverse drug reactions (ADRs). The safety analysis included 106 patients (mean age 39.3 years; women 62.3%) whose data were collected until the data lock point (February 7, 2016). The effectiveness analysis included 75 patients. The majority of patients had relapsing-remitting MS (93/106 patients; 87.7%). The mean length of treatment exposure in the present study was 6.6 months. During the 2-year observation period, no significant change in the EDSS was observed, while the ARR decreased significantly from baseline (72.9% reduction, p = 0.001). ADRs and serious ADRs were observed in 11.3% and 3.8% of patients, respectively; however, no new safety concerns were detected. No patient had progressive multifocal leukoencephalopathy (PML) during the present study period. The safety and effectiveness of natalizumab were confirmed in Japanese patients with MS in clinical practice. Nevertheless, potential risks including PML require continuous, careful observation. Biogen Japan Ltd (Tokyo, Japan).

  15. Changes in the utilization of osteoporosis drugs after the 2010 FDA bisphosphonate drug safety communication

    Directory of Open Access Journals (Sweden)

    Bander Balkhi

    2018-02-01

    Conclusions: The 2010 FDA bisphosphonates safety communication appeared to have influenced Osteoporosis utilization in Medicaid recipients. The 2010 FDA bisphosphonates safety communication was associated with a significant reduction in the utilization of bisphosphonates in the Medicaid program.

  16. Hanford Generic Interim Safety Basis

    International Nuclear Information System (INIS)

    Lavender, J.C.

    1994-01-01

    The purpose of this document is to identify WHC programs and requirements that are an integral part of the authorization basis for nuclear facilities that are generic to all WHC-managed facilities. The purpose of these programs is to implement the DOE Orders, as WHC becomes contractually obligated to implement them. The Hanford Generic ISB focuses on the institutional controls and safety requirements identified in DOE Order 5480.23, Nuclear Safety Analysis Reports

  17. Hanford Generic Interim Safety Basis

    Energy Technology Data Exchange (ETDEWEB)

    Lavender, J.C.

    1994-09-09

    The purpose of this document is to identify WHC programs and requirements that are an integral part of the authorization basis for nuclear facilities that are generic to all WHC-managed facilities. The purpose of these programs is to implement the DOE Orders, as WHC becomes contractually obligated to implement them. The Hanford Generic ISB focuses on the institutional controls and safety requirements identified in DOE Order 5480.23, Nuclear Safety Analysis Reports.

  18. Independent Technical Review of the C-400 Interim Remedial Project Phase I Results, Paducah, Kentucky

    International Nuclear Information System (INIS)

    Looney, B.; Rossabi, J.; Stewart, L.; Richards, W.

    2010-01-01

    The groundwater and soil in the vicinity of the C-400 Building at the Paducah Gaseous Diffusion Plant (PGDP), is contaminated with substantial quantities of industrial solvents, primarily trichoroethene (TCE). This solvent 'source' is recognized as a significant challenge and an important remediation target in the overall environmental cleanup strategy for PGDP. Thus, the cleanup of the C-400 TCE Source is a principal focus for the Department of Energy (DOE) and its contractors, and for PGDP regulators and stakeholders. Using a formal investigation, feasibility study and decision process, Electrical Resistance Heating (ERH) was selected for the treatment of the soil and groundwater in the vicinity of C-400. ERH was selected as an interim action to remove 'a significant portion of the contaminant mass of TCE at the C-400 Cleaning Building area through treatment' with the longer term goal of reducing 'the period the TCE concentration in groundwater remains above its Maximum Contaminant Level (MCL).' ERH is a thermal treatment that enhances the removal of TCE and related solvents from soil and groundwater. The heterogeneous conditions at PGDP, particularly the high permeability regional gravel aquifer (RGA), are challenging to ERH. Thus, a phased approach is being followed to implement this relatively expensive and complex remediation technology. Conceptually, the phased approach encourages safety and efficiency by providing a 'lessons learned' process and allowing appropriate adjustments to be identified and implemented prior to follow-on phase(s) of treatment. More specifically, early deployment targeted portions of the challenging RGA treatment zone with relatively little contamination reducing the risk of adverse collateral impacts from underperformance in terms of heating and capture. Because of the importance and scope of the C-400 TCE source remediation activities, DOE chartered an Independent Technical Review (ITR) in 2007 to assess the C-400 ERH plans prior

  19. INDEPENDENT TECHNICAL REVIEW OF THE C-400 INTERIM REMEDIAL PROJECT PHASE I RESULTS, PADUCAH, KENTUCKY

    Energy Technology Data Exchange (ETDEWEB)

    Looney, B.; Rossabi, J.; Stewart,L.; Richards, W.

    2010-10-29

    The groundwater and soil in the vicinity of the C-400 Building at the Paducah Gaseous Diffusion Plant (PGDP), is contaminated with substantial quantities of industrial solvents, primarily trichoroethene (TCE). This solvent 'source' is recognized as a significant challenge and an important remediation target in the overall environmental cleanup strategy for PGDP. Thus, the cleanup of the C-400 TCE Source is a principal focus for the Department of Energy (DOE) and its contractors, and for PGDP regulators and stakeholders. Using a formal investigation, feasibility study and decision process, Electrical Resistance Heating (ERH) was selected for the treatment of the soil and groundwater in the vicinity of C-400. ERH was selected as an interim action to remove 'a significant portion of the contaminant mass of TCE at the C-400 Cleaning Building area through treatment' with the longer term goal of reducing 'the period the TCE concentration in groundwater remains above its Maximum Contaminant Level (MCL).' ERH is a thermal treatment that enhances the removal of TCE and related solvents from soil and groundwater. The heterogeneous conditions at PGDP, particularly the high permeability regional gravel aquifer (RGA), are challenging to ERH. Thus, a phased approach is being followed to implement this relatively expensive and complex remediation technology. Conceptually, the phased approach encourages safety and efficiency by providing a 'lessons learned' process and allowing appropriate adjustments to be identified and implemented prior to follow-on phase(s) of treatment. More specifically, early deployment targeted portions of the challenging RGA treatment zone with relatively little contamination reducing the risk of adverse collateral impacts from underperformance in terms of heating and capture. Because of the importance and scope of the C-400 TCE source remediation activities, DOE chartered an Independent Technical Review (ITR) in

  20. Vital signs: Repeat births among teens - United States, 2007-2010.

    Science.gov (United States)

    2013-04-05

    Teen childbearing has potential negative health, economic, and social consequences for mother and child. Repeat teen childbearing further constrains the mother's education and employment possibilities. Rates of preterm and low birth weight are higher in teens with a repeat birth, compared with first births. To assess patterns of repeat childbearing and postpartum contraceptive use among teens, CDC analyzed natality data from the National Vital Statistics System (NVSS) and the Pregnancy Risk Assessment Monitoring System (PRAMS) from 2007-2010. Based on 2010 NVSS data from all 50 states and the District of Columbia, of more than 367,000 births to teens aged 15-19 years, 18.3% were repeat births. The percentage of teen births that represented repeat births decreased by 6.2% between 2007 and 2010. Disparities in repeat teen births exist by race/ethnicity, with the highest percentages found among American Indian/Alaska Natives (21.6%), Hispanics (20.9%), and non-Hispanic blacks (20.4%) and lowest among non-Hispanic whites (14.8%). Wide geographic disparities in the percentage of teen births that were repeat births also exist, ranging from 22% in Texas to 10% in New Hampshire. PRAMS data from 16 reporting areas (15 states and New York City) indicate that 91.2% of teen mothers used a contraceptive method 2-6 months after giving birth, but only 22.4% of teen mothers used the most effective methods. Teens with a previous live birth were significantly more likely to use the most effective methods postpartum compared with those with no prior live birth (29.6% versus 20.9%, respectively). Non-Hispanic white and Hispanic teens were significantly more likely to use the most effective methods than non-Hispanic black teens (24.6% and 27.9% versus 14.3%, respectively). The percentage of teens reporting postpartum use of the most effective methods varied greatly geographically across the PRAMS reporting areas, ranging from 50.3% in Colorado to 7.2% in New York State. Although the

  1. Seismic safety margin assessment program (Annual safety research report, JFY 2010)

    International Nuclear Information System (INIS)

    Suzuki, Kenichi; Iijima, Toru; Inagaki, Masakatsu; Taoka, Hideto; Hidaka, Shinjiro

    2011-01-01

    Seismic capacity test data, analysis method and evaluation code provided by Seismic Safety Margin Assessment Program have been utilized for the support of seismic back-check evaluation of existing plants. The summary of the program in 2010 is as follows. 1. Component seismic capacity test and quantitative seismic capacity evaluation. Many seismic capacity tests of various snubbers were conducted and quantitative seismic capacities were evaluated. One of the emergency diesel generator partial-model seismic capacity tests was conducted and quantitative seismic capacity was evaluated. Some of the analytical evaluations of piping-system seismic capacities were conducted. 2. Analysis method for minute evaluation of component seismic response. The difference of seismic response of large components such as primary containment vessel and reactor pressure vessel when they were coupled with 3-dimensional FEM building model or 1-dimensional lumped mass building model, was quantitatively evaluated. 3. Evaluation code for quantitative evaluation of seismic safety margin of systems, structures and components. As the example, quantitative evaluation of seismic safety margin of systems, structures and components were conducted for the reference plant. (author)

  2. Safety and Efficacy of Teneligliptin in Patients with Type 2 Diabetes Mellitus and Impaired Renal Function: Interim Report from Post-marketing Surveillance.

    Science.gov (United States)

    Haneda, Masakazu; Kadowaki, Takashi; Ito, Hiroshi; Sasaki, Kazuyo; Hiraide, Sonoe; Ishii, Manabu; Matsukawa, Miyuki; Ueno, Makoto

    2018-06-01

    Teneligliptin is a novel oral dipeptidyl peptidase-4 inhibitor for the treatment of type 2 diabetes mellitus (T2DM). Safety and efficacy of teneligliptin have been demonstrated in clinical studies; however, data supporting its use in patients with moderate or severe renal impairment are limited. This interim analysis of a post-marketing surveillance of teneligliptin, exploRing the long-term efficacy and safety included cardiovascUlar events in patients with type 2 diaBetes treated bY teneligliptin in the real-world (RUBY), aims to verify the long-term safety and efficacy of teneligliptin in Japanese patients with T2DM and impaired renal function. For this analysis, we used the data from case report forms of the RUBY surveillance between May 2013 and June 2017. The patients were classified into G1-G5 stages of chronic kidney disease according to estimated glomerular filtration rate (eGFR) at initiation of teneligliptin treatment. Safety and efficacy were evaluated in these subgroups. Patients on dialysis were also assessed. Safety was assessed from adverse drug reactions (ADRs). Glycemic control was evaluated up to 2 years after teneligliptin initiation. A total of 11,677 patients were enrolled in the surveillance and 11,425 patient case-report forms were collected for the interim analysis. The incidence of ADRs in each subgroup was 2.98-6.98% of patients, with no differences in the ADR profile (including hypoglycemia and renal function ADRs) between subgroups. At 1 and 2 years after starting teneligliptin, the least-squares mean change in HbA1c adjusted to the baseline was - 0.68 to - 0.85% and - 0.71 to - 0.85% across the eGFR groups, respectively. Treatment with teneligliptin in patients on dialysis reduced or tended to reduce glycated albumin levels [- 2.29%, (p < 0.001) after 1 year; - 1.64%, (p = 0.064) after 2 years]. During long-term treatment, teneligliptin was generally well tolerated in patients with any stage of renal impairment from

  3. 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

  4. Determinants of the European Union rural population change in 2007-2010

    Directory of Open Access Journals (Sweden)

    Michał Dudek

    2013-06-01

    Full Text Available Natural change and migration are important determinants of the economy and environment. In the EU strategic documents the socio-economic developmental priorities have a territorial aspect, referring to all the regions of the member states. Achievement of the Union’s sustainable growth policy objectives could be limited due to unfavourable demographic trends in rural areas. The paper, using the Eurostat data and selected measures of population reproduction, describes the changes in number of rural inhabitants in 2007-2010 and their main determinants. In the analysed period the rural population size increased. However, contrary to the urban and intermediate regions, since 2009 as a result of a surplus number of deaths over births, in the rural areas the negative values of population increase were observed.

  5. Relative risk measure suitable for comparison of design alternatives of interim spent nuclear fuel storage facility

    International Nuclear Information System (INIS)

    Ferjencik, M.

    1997-01-01

    Accessible reports on risk assessment of interim spent nuclear fuel storage facilities presume that only releases of radioactive substances represent undesired consequences. However, only certain part of the undesired consequences is represented by them. Many other events are connected with safety and are able to cause losses to the operating company. The following two presumptions are pronounced based on this. 1. Any event causing a disturbance of a safety function of the storage facility is an incident event. 2. Any disturbance of a safety function is an undesired consequence. If the facility safety functions are identified and if the severity of their disturbances is quantified, then it is possible to combine consequence severity quantifications and event frequencies into a risk measure. Construction and application of such a risk measure is described in this paper. The measure is shown to be a tool suitable for comparison of interim storage technology design alternatives. (author)

  6. IRSN's viewpoint on the safety and radiation protection of French nuclear power plants in 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2009-07-01

    This report presents the viewpoint of the IRSN on the safety and radiation protection of EDF's nuclear power plants (NPPs) in operation during 2007. It does not aim to be exhaustive but rather to highlight the points the IRSN considers important for safety. Contributing to maintaining a high level of safety and radiation protection in nuclear facilities in service is one of the seven challenges of the objectives contract signed between the French Government and the IRSN. Safety demands constant vigilance on the part of all the players involved. It is never definitively acquired and must remain a priority and continuously progress, with the plant operator remaining the first entity responsible for the safety of its facility. For the IRSN, part of this mission firstly involves carefully examining and taking into consideration national and international experience feedback, and new scientific knowledge resulting from research. The implementation of improvements, whether technical or organizational or relating to human skills, then comes secondly. This report comprises four sections. In the first section, the IRSN presents the main trends that emerged from its overall review of the safety of the in-service nuclear power plants. The second section addresses the events that have marked the year due to their impact on safety. It also presents a synthesis of the radiation protection events. The third section is devoted to anomalies displaying a generic nature for several power plants. The last section covers the significant changes implemented or scheduled. These are generally modifications or plans of action intended to improve safety performance in the operation or design of the facilities. In spite of sometimes significant disparities in the results between power plants, the IRSN draws the following conclusions from its global review of the year 2007. First of all, no event had serious consequences in the fields of either safety or radioprotection. This good result

  7. Sífilis congênita no Rio Grande do Norte: estudo descritivo do período 2007-2010

    Directory of Open Access Journals (Sweden)

    Isaiane da Silva Carvalho

    Full Text Available OBJETIVO: Descrever a ocorrência e o perfil dos casos notificados de sífilis congênita no estado do Rio Grande do Norte, Brasil, no período de 2007 a 2010. MÉTODOS: Estudo descritivo, com dados do Sistema de Informações sobre Nascidos Vivos (Sinasc e do Sistema de Informação de Agravos de Notificação (Sinan. RESULTADOS: No período avaliado, verificou-se 598 casos notificados de sífilis congênita e taxas de incidência de 2,7 e 0,9 por 1.000 nascidos vivos, respectivamente nos anos de 2007 e 2010; o município de Natal-RN concentrou 74,6% das notificações; a maioria das notificações foi de nascidos vivos cujas mães tinham até 8 anos de estudo (65,0%, haviam realizado pré-natal (72,2% e com diagnóstico de sífilis no momento do parto/curetagem (41,0%. CONCLUSÃO: Apesar da diminuição da taxa de incidência no período investigado, em 2010, ela ainda era superior ao valor de 0,5/1.000 nascidos vivos, meta estabelecida para eliminação da doença.

  8. Finnish research programmes on nuclear power plant safety

    International Nuclear Information System (INIS)

    Puska, E. K.

    2010-01-01

    The current Finnish national research programme on nuclear power plant safety SAFIR2010 for the years 2007-2010 as well as the coming SAFIR2014 programme for the years 2011-2014 are based on the chapter 7a, 'Ensuring expertise', of the Finnish Nuclear Energy Act. The objective of this chapter is realised in the research work and education of experts in the projects of these research programmes. SAFIR2010 research programme is divided in eight research areas that are Organisation and human, Automation and control room, Fuel and reactor physics, Thermal hydraulics, Severe accidents, Structural safety of reactor circuit, Construction safety, and Probabilistic Safety Analysis (PSA). All the research areas include both projects in their own area and interdisciplinary co-operational projects. Research projects of the programme are chosen on the basis of annual call for proposals. In 2010 research is carried out in 33 projects in SAFIR2010. VTT is the responsible research organisation in 26 of these projects and VTT is also the coordination unit of SAFIR2010 and SAFIR2014. In 2007-2009 SAFIR2010 produced 497 Specified research results (Deliverables), 618 Publications, and 33 Academic degrees. SAFIR2010 programme covers approximately half of the reactor safety research volume in Finland currently. In 2010 the programme volume is EUR 7.1 million and 47 person years. The major funding partners are VYR with EUR 2.96 million, VTT with EUR 2.66 million, Fortum with EUR 0.28 million, TVO with EUR 0.19 million, NKS with EUR 0.15 million, EU with only EUR 0.03 million and other partners with EUR 0.85 million. The new decisions-in-principle on Olkiluoto unit 4 for Teollisuuden Voima and new nuclear power plant for Fennovoima ratified by the Finnish Parliament on 1 July 2010 increase the annual funding collected according to the Finnish Nuclear Energy Act from Fennovoima, Fortum and Teollisuuden Voima for the SAFIR2014 programme to EUR 5.2 million from the current level of EUR 3

  9. Observations of runoff and sediment and dissolved loads from the Greenland Ice Sheet at Kangerlussuaq, West Greenland, 2007 to 2010

    DEFF Research Database (Denmark)

    Hasholt, Bent; Mikkelsen, Andreas Peter Bech; Nielsen, Morten Holtegaard

    2012-01-01

    Observations from 2007 to 2010 of runoff, sediment and solute delivery from a segment of the Greenland Ice Sheet (GrIS) and the proglacial landscape draining into the fjord at Kangerlussuaq are presented. The observations include at least three jökulhlaups and extreme recordings from 2010...... previously published for 2007 and 2008. The average effective erosion from the catchment was 0.28 mm (min. 0.18 and max. 0.45 mm). The erosion is larger than indicated from most other locations along the GrIS, but in the same order of magnitude as erosion in other glaciated areas at the same latitude, e.......g. Norway. The sandur in the proglacial area acts as a sediment sink for a lot of the sediments from the GrIS....

  10. Report of transparency and nuclear safety 2007 CEA Fontenay aux Roses; Rapport transparence et securite nucleaire 2007 CEA Fontenay aux Roses

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This report presents the activities of the CEA Center of Fontenay aux roses for the year 2007. After many years of decommissioning and dismantling of nuclear installations, the Center is now devoted (since 2005) to the development of research programmes on biology and biomedical technologies. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. (A.L.B.)

  11. Regulatory oversight report 2007 concerning nuclear safety in Swiss nuclear installations; Aufsichtsbericht 2007 ueber die nukleare Sicherheit in den schweizerischen Kernanlagen

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-04-15

    This annual report issued by the Swiss Federal Nuclear Inspectorate (HSK) reports on the work carried out by the Inspectorate in 2007. This report reviews the regulatory activities in the four Swiss nuclear power stations and in four further nuclear installations in various Swiss research facilities. It deals with topics such as operational details, technologies in use, radiation protection, radioactive wastes, emergency dispositions and personnel and provides an assessment of operations from the point of view of safety. Also, the transportation of nuclear materials - both nuclear fuels and nuclear wastes - is reported on. General topics discussed include probabilistic safety analyses and accident management. Finally, the disposal of nuclear wastes and work done in the rock laboratories in Switzerland is commented on.

  12. 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...

  13. National radiotherapy Observatory. Inquiry report: situation at the end of 2010 and evolution since 2007. Context and method, results of data from 2010, conclusion; Observatoire national de la radiotherapie. Rapport d'enquete: situation fin 2010 et evolution depuis 2007. Contexte et methode, resultats des donnees 2010, conclusion

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-01-15

    Illustrated by data tables and graphs, this document presents and discusses the results of an inquiry made on radiotherapy centres about their equipment (linear accelerators and additional equipment, number of days opened to patients, use, quality control and maintenance duration, treatment preparation, equipment dedicated to quality control), their activities (evolution of the number of treated patients, of treatments, and of treatment sessions between 2007 and 2010, number of sessions per apparatus, dosimetry, techniques), their personnel (evolution of the number of radiotherapists, radio-physicists, operators and dosimetrists, time dedicated to training), and their practices

  14. Foodborne Outbreaks Reported to the U.S. Food Safety and Inspection Service, Fiscal Years 2007 through 2012.

    Science.gov (United States)

    Robertson, Kis; Green, Alice; Allen, Latasha; Ihry, Timothy; White, Patricia; Chen, Wu-San; Douris, Aphrodite; Levine, Jeoffrey

    2016-03-01

    The U.S. Department of Agriculture's Food Safety and Inspection Service (FSIS) works closely with federal, state, and local public health partners to investigate foodborne illness outbreaks associated with its regulated products. To provide insight into outbreaks associated with meat and poultry, outbreaks reported to FSIS during fiscal years 2007 through 2012 were evaluated. Outbreaks were classified according to the strength of evidence linking them to an FSIS-regulated product and by their epidemiological, etiological, and vehicle characteristics. Differences in outbreak characteristics between the period 2007 through 2009 and the period 2010 through 2012 were assessed using a chi-square test or Mann-Whitney U test. Of the 163 reported outbreaks eligible for analysis, 89 (55%) were identified as possibly linked to FSIS-regulated products and 74 (45%) were definitively linked to FSIS-regulated products. Overall, these outbreaks were associated with 4,132 illnesses, 772 hospitalizations, and 19 deaths. Shiga toxin-producing Escherichia coli was associated with the greatest proportion of reported outbreaks (55%), followed by Salmonella enterica (34%) and Listeria monocytogenes (7%). Meat and poultry products commercially sold as raw were linked to 125 (77%) outbreaks, and of these, 105 (80%) involved beef. Over the study period, the number of reported outbreaks definitively linked to FSIS-regulated products (P = 0.03) declined, while the proportion of culture-confirmed cases (P = 0.0001) increased. Our findings provide insight into the characteristics of outbreaks associated with meat and poultry products.

  15. 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.

  16. Helmholtz-Zentrum Dresden-Rossendorf, Institute of Safety Research. Annual report 2010

    International Nuclear Information System (INIS)

    Gerbeth, Gunter; Schaefer, Frank

    2011-01-01

    The Institute of Safety Research (ISR) was over the past 20 years one of the six Research Institutes of Forschungszentrum Dresden-Rossendorf e.V. (FZD), which in 2010 belonged to the Wissenschaftsgemeinschaft Gottfried Wilhelm Leibniz. Together with the Institutes of Radiochemistry and Radiation Physics, ISR implements the research programme ''Nuclear Safety Research'' (NSR), which was during last years one of the three scientific programmes of FZD. NSR involves two main topics, i.e. ''Safety Research for Radioactive Waste Disposal'' and ''Safety Research for Nuclear Reactors''. The research of ISR aims at assessing and enhancing the safety of current and future reactors, the development of advanced simulation tools including their validation against experimental data, and the development of the appropriate measuring techniques for multi-phase flows and liquid metals.

  17. Development of Accident Scenario for Interim Spent Fuel Storage Facility Based on Fukushima Accident

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Dongjin; Choi, Kwangsoon; Yoon, Hyungjoon; Park, Jungsu [KEPCO-E and C, Yongin (Korea, Republic of)

    2014-05-15

    700 MTU of spent nuclear fuel is discharged from nuclear fleet every year and spent fuel storage is currently 70.9% full. The on-site wet type spent fuel storage pool of each NPP(nuclear power plants) in Korea will shortly exceed its storage limit. Backdrop, the Korean government has rolled out a plan to construct an interim spent fuel storage facility by 2024. However, the type of interim spent fuel storage facility has not been decided yet in detail. The Fukushima accident has resulted in more stringent requirements for nuclear facilities in case of beyond design basis accidents. Therefore, there has been growing demand for developing scenario on interim storage facility to prepare for beyond design basis accidents and conducting dose assessment based on the scenario to verify the safety of each type of storage.

  18. Space-time mapping of wasting among children under the age of five years in Somalia from 2007 to 2010.

    Science.gov (United States)

    Kinyoki, Damaris K; Berkley, James A; Moloney, Grainne M; Odundo, Elijah O; Kandala, Ngianga-Bakwin; Noor, Abdisalan M

    2016-02-01

    To determine the sub-national seasonal prevalence and trends in wasting from 2007 to 2010 among children aged 6-59 months in Somalia using remote sensing and household survey data from nutritional surveys. Bayesian hierarchical space-time model was implemented using a stochastic partial differential equation (SPDE) approach in integrated nested Laplace approximations (INLA) to produce risk maps of wasting at 1 × 1 km(2) spatial resolution and predict to seasons in each year of study from 2007 to 2010. The prevalence of wasting was generally at critical levels throughout the country, with most of the areas remaining in the upper classes of critical and very critical levels. There was minimal variation in wasting from year-to-year, but a well-defined seasonal variation was observed. The mean difference of the prevalence of wasting between the dry and wet season ranges from 0% to 5%. The risks of wasting in the South Central zone were highest in the Gedo (37%) and Bay (32%) regions. In North East zone the risk was highest in Nugaal (25%) and in the North West zone the risk was high in Awdal and Woqooyi Galbeed regions with 23%. There was a clear seasonal variation in wasting with minimal year-to-year variability from 2007 to 2010 in Somalia. The prevalence was high during the long dry season, which affects the prevalence in the preceding long rainy season. Understanding the seasonal fluctuations of wasting in different locations and at different times is important to inform timely interventions. Copyright © 2016. Published by Elsevier Ltd.

  19. Space–time mapping of wasting among children under the age of five years in Somalia from 2007 to 2010

    Science.gov (United States)

    Kinyoki, Damaris K; Berkley, James A; Moloney, Grainne M; Odundo, Elijah O; Kandala, Ngianga-Bakwin; Noor, Abdisalan M

    2016-01-01

    Objective To determine the sub-national seasonal prevalence and trends in wasting from 2007 to 2010 among children aged 6–59 months in Somalia using remote sensing and household survey data from nutritional surveys. Methods Bayesian hierarchical space–time model was implemented using a stochastic partial differential equation (SPDE) approach in integrated nested Laplace approximations (INLA) to produce risk maps of wasting at 1 × 1 km2 spatial resolution and predict to seasons in each year of study from 2007 to 2010. Results The prevalence of wasting was generally at critical levels throughout the country, with most of the areas remaining in the upper classes of critical and very critical levels. There was minimal variation in wasting from year-to-year, but a well-defined seasonal variation was observed. The mean difference of the prevalence of wasting between the dry and wet season ranges from 0% to 5%. The risks of wasting in the South Central zone were highest in the Gedo (37%) and Bay (32%) regions. In North East zone the risk was highest in Nugaal (25%) and in the North West zone the risk was high in Awdal and Woqooyi Galbeed regions with 23%. Conclusion There was a clear seasonal variation in wasting with minimal year-to-year variability from 2007 to 2010 in Somalia. The prevalence was high during the long dry season, which affects the prevalence in the preceding long rainy season. Understanding the seasonal fluctuations of wasting in different locations and at different times is important to inform timely interventions. PMID:26919757

  20. 75 FR 18451 - Safety and Security Zones; Tall Ships Challenge 2010, Great Lakes; Cleveland, OH; Bay City, MI...

    Science.gov (United States)

    2010-04-12

    ...-AA87 Safety and Security Zones; Tall Ships Challenge 2010, Great Lakes; Cleveland, OH; Bay City, MI.... SUMMARY: The Coast Guard proposes to establish temporary safety and security zones around each Tall Ship visiting the Great Lakes during the Tall Ships Challenge 2010 race series. These safety and security zones...

  1. Evapotranspiration over spatially extensive plant communities in the Big Cypress National Preserve, southern Florida, 2007-2010

    Science.gov (United States)

    Shoemaker, W. Barclay; Lopez, Christian D.; Duever, Michael J.

    2011-01-01

    Evapotranspiration (ET) was quantified over plant communities within the Big Cypress National Preserve (BCNP) using the eddy covariance method for a period of 3 years from October 2007 to September 2010. Plant communities selected for study included Pine Upland, Wet Prairie, Marsh, Cypress Swamp, and Dwarf Cypress. These plant communities are spatially extensive in southern Florida, and thus, the ET measurements described herein can be applied to other humid subtropical locations such as the Everglades.

  2. Helmholtz-Zentrum Dresden-Rossendorf, Institute of Safety Research. Annual report 2010

    Energy Technology Data Exchange (ETDEWEB)

    Gerbeth, Gunter; Schaefer, Frank (eds.)

    2011-07-01

    The Institute of Safety Research (ISR) was over the past 20 years one of the six Research Institutes of Forschungszentrum Dresden-Rossendorf e.V. (FZD), which in 2010 belonged to the Wissenschaftsgemeinschaft Gottfried Wilhelm Leibniz. Together with the Institutes of Radiochemistry and Radiation Physics, ISR implements the research programme ''Nuclear Safety Research'' (NSR), which was during last years one of the three scientific programmes of FZD. NSR involves two main topics, i.e. ''Safety Research for Radioactive Waste Disposal'' and ''Safety Research for Nuclear Reactors''. The research of ISR aims at assessing and enhancing the safety of current and future reactors, the development of advanced simulation tools including their validation against experimental data, and the development of the appropriate measuring techniques for multi-phase flows and liquid metals.

  3. Ferrocyanide Safety Program rationale for removing six tanks from the safety watch list

    International Nuclear Information System (INIS)

    Borsheim, G.L.

    1993-09-01

    This report documents an in-depth study of single-shell tanks containing ferrocyanide wastes. Topics include: safety assessments, tank histories, supportive documentation about interim stabilization and planned remedial activities

  4. Safety and effectiveness of certolizumab pegol in patients with rheumatoid arthritis: Interim analysis of post-marketing surveillance.

    Science.gov (United States)

    Kameda, Hideto; Nishida, Keiichiro; Nannki, Toshihiro; Watanabe, Akira; Oshima, Yukiya; Momohara, Shigaki

    2017-01-01

    Objective: To evaluate the safety and effectiveness of certolizumab pegol (CZP) in a real-world setting among Japanese patients with rheumatoid arthritis. Post-marketing surveillance data from 2,579 patients treated with CZP were analyzed. Adverse events (AEs) observed during the 24-week CZP treatment period were recorded. Disease activity was evaluated using DAS28-ESR and DAS28-CRP at baseline, Week 12, Week 24, or at withdrawal. The total period of exposure to CZP was 1313.8 patient-years (PY). AEs were reported in 658 (25.5%) patients, at an event rate (ER) of 73.68/100 PY. The most frequent serious AEs were pneumonia, herpes zoster, and interstitial lung disease, at ER per 100 PY of 2.06, 1.29, and 1.22, respectively. Mean disease activity scores at baseline, as measured by DAS28-ESR and DAS28-CRP, were 4.77 ± 1.34 and 4.21 ± 1.27, respectively. Mean changes from baseline at the last observation were -1.29 ± 1.46 and -1.30 ± 1.42, respectively. EULAR good or moderate responses were achieved in 65% of patients. Longer disease duration, prior biologics use, and treatment without MTX co-therapy were associated with EULAR no response. In this interim analysis, no new safety signals were observed. Clinical response to CZP was observed in approximately two thirds of patients.

  5. 75 FR 30372 - Foreign-Trade Zone 196 Temporary/Interim Manufacturing Authority ATC Logistics & Electronics...

    Science.gov (United States)

    2010-06-01

    ... DEPARTMENT OF COMMERCE Foreign-Trade Zones Board [Docket T-2-2010] Foreign-Trade Zone 196 Temporary/Interim Manufacturing Authority ATC Logistics & Electronics (Cell Phone Kitting and Distribution... filed an application submitted by the ATC Logistics & Electronics, operator of Site 2, FTZ 196...

  6. High Committee for transparency and information on nuclear safety: Annual activity report (January 2010 - December 2010)

    International Nuclear Information System (INIS)

    2010-01-01

    After a description of the operation of the French 'High Committee for transparency and information on nuclear safety' (HCTISN), of its missions, its organisation and its means, the progress report presents the High Committee activity for 2010 with summaries of its report on the transparency of nuclear material and waste management, its meetings, its work groups, its visits and participations to other events

  7. 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.)

  8. 33 CFR 165.T09-0073 - Safety and Security Zones; Tall Ships Challenge 2010; Great Lakes; Cleveland, OH; Bay City, MI...

    Science.gov (United States)

    2010-07-01

    ... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Safety and Security Zones; Tall... GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) PORTS AND WATERWAYS SAFETY REGULATED NAVIGATION AREAS... Guard District § 165.T09-0073 Safety and Security Zones; Tall Ships Challenge 2010; Great Lakes...

  9. FMCSA safety program effectiveness measurement : compliance review effectiveness model results for carriers with compliance reviews in FY 2007

    Science.gov (United States)

    2012-09-30

    In FY 2007, Federal and State enforcement personnel conducted more than 15,000 CRs on individual motor carriers. It is intended that through education, heightened safety regulation awareness, and the enforcement effects of the CR, carriers will impro...

  10. 2007 transparency and nuclear safety report. CEA Cadarache. Volumes 1 + 2

    International Nuclear Information System (INIS)

    2007-01-01

    After a general presentation of the Cadarache site and of its nuclear installations, the first volume of this report describes the various measures concerning the site safety: safety organisation, general measures, measures related to various risks, control of emergency situations, inspections, audits and second level control, measures in basic nuclear installations. It describes the measures concerning the radioprotection on this site: organisation, significant facts, and dose measurement results. It describes significant events which occurred in relationship with nuclear safety and radioprotection, presents results of release measurements and of radiological and chemical assessments of the impact these releases on the environment. The report then describes measures implemented to limit the volume of stored radioactive wastes and also their impact on health and on the environment. It provides a series of tables indicating the nature and quantities of wastes which are stored in the different basic nuclear installations of Cadarache. It reports the recommendations expressed by the CHSCT (committee on hygiene, security and working conditions) after the 2006 report. The second volume proposes the same information for two specific nuclear installations belonging to Areva and located in Cadarache, the INB 32 and 54 (INB stands for basic nuclear installation), for which the significant events occurred on the 13. of March and on the 25. of May 2007. For these installations, release measurements concern gaseous and liquid releases

  11. Angra-1 probabilistic safety study-phase B

    International Nuclear Information System (INIS)

    Fernandes Filho, T.L.; Gibelli, S.M.O.

    1988-05-01

    This study represents the Phase B of the Angra-1 Probabilistic Safety Study and is the the final report prepared for the IAEA under Research Contract No. 3423/R2/RB. The three main items covered in this report are the establishment of interim safety goals, analysis of Angra-1 operational experience and development of emergency procedures to address severe accidents. For establishment of interim safety goals a methodology for calculating consequences and risks associated to the Angra-1 operation was developed based on the available data and codes. The proposed safety goals refer to the individual risk of early fatality for people living in the vicinity of the plant, colective risk of cancer fatalities for people living near the plant, the propobability of core melt occurrence and the probability of dominant accident sequences. (author) [pt

  12. Isotopic composition of precipitation at the station Ljubljana (Reaktor, Slovenia – period 20072010

    Directory of Open Access Journals (Sweden)

    Polona Vreča

    2014-12-01

    Full Text Available The stable isotopic composition of hydrogen and oxygen (δ2H and δ18O and the tritium activity (A were monitored in monthly collected precipitation at Ljubljana (Reaktor during the period 20072010. Monthly and yearly isotope variations are discussed and compared with those observed over the period 1981–2006 and with the basic meteorological parameters for Ljubljana (Bežigrad and Ljubljana (Hrastje stations for the period 20072010. The mean values for δ2H and δ18O, weighted by precipitation amount at Ljubljana (Reaktor, are –59.4 ‰ and –8.71 ‰. The reduced major axis local meteoric water line (LMWLRMA is δ2H = (8.19 ± 0.22×δ18O + (11.52 ± 1.97, while the precipitation weighted least square regression results in LMWLPWLSR-Re δ2H = (7.94 ± 0.21×δ18O + (9.76 ± 1.93. The lack of significant difference in the LMWL slopes indicates a relatively homogeneous distribution of monthly precipitation as well as the small number of low-amount monthly precipitation events with low deuterium excess. The deuterium excess weighted mean value is 10.3 ‰ which indicates the prevailing influence of the Atlantic air masses. The temperature coefficient of δ18O is 0.30 ‰/°C. Tritium activity in monthly precipitation shows typical seasonal variations, with a weighted mean tritium activity in this period of 8.5 TU. No decrease of mean annual activity is observed.

  13. Annual report on the activities in Safety Administration Department. Report of the fiscal year 2010

    Energy Technology Data Exchange (ETDEWEB)

    Aoki, Yoshikazu [Japan Atomic Energy Agency, Nuclear Fuel Cycle Engineering Laboratories, Tokai, Ibaraki (Japan)

    2014-01-15

    The activities of Safety Administration Department covers many fields in Nuclear Fuel Cycle Engineering Laboratories such as the management of the occupational safety and health, the crisis management, the security, and the management of a quality assurance. This report is the summary of the activities of Safety Administration Department since April, 2010 until March, 2011. (author)

  14. EUROSAFE Forum 2010. Towards convergence of technical nuclear safety practices in Europe

    International Nuclear Information System (INIS)

    2010-01-01

    The EUROSAFE forum 2010 covered the following technical plenary presentations: the future of innovation in organizations; obstacles to innovative engineering; the challenge of introducing innovation to processes and regulations; TSO's approach to innovation - combining research, operational feedback experience and knowledge management; innovation and safety - necessity or contradiction? safe rail traffic control. Seminars were held on the following topics: Seminar 1: nuclear installation safety; Seminar 2: radiation protection and environment; Seminar 3: waste management; seminar 4: nuclear security.

  15. The Inspector General's report on Nuclear Safety and Radiation Protection 2010

    International Nuclear Information System (INIS)

    2010-01-01

    This document is proposed in French and in English. The author reports, comments and discusses the observations he made during 2010 on different aspects or examples regarding nuclear safety management and radioprotection in the EDF Group, the world's largest nuclear operator with 73 reactors in service: safety management, radioprotection, relationship with the French nuclear safety authority (ASN), skills and training, the implementation and action of an integrated nuclear engineering force, the relationship between safety and business efficiency, actors of the health care sector, the case of the Flamanville EPR reactor, the relationships with contractors, fire hazards, and projects aimed at raising standards. He also addresses observations and information about what is going on in the United Kingdom. He comments a radioprotection incident, the case of an uncontrolled dilution, and a railway accident which occurred in 2006. He gives a brief report of missions in China and in the United States

  16. National radiotherapy Observatory. Inquiry report: situation at the end of 2010 and evolution since 2007. Context and method, results of data from 2010, conclusion

    International Nuclear Information System (INIS)

    2012-01-01

    Illustrated by data tables and graphs, this document presents and discusses the results of an inquiry made on radiotherapy centres about their equipment (linear accelerators and additional equipment, number of days opened to patients, use, quality control and maintenance duration, treatment preparation, equipment dedicated to quality control), their activities (evolution of the number of treated patients, of treatments, and of treatment sessions between 2007 and 2010, number of sessions per apparatus, dosimetry, techniques), their personnel (evolution of the number of radiotherapists, radio-physicists, operators and dosimetrists, time dedicated to training), and their practices

  17. Condições higiênico-sanitárias dos portos de Manaus-AM, 2007-2010 | Sanitary conditions of the ports of Manaus-AM, 2007-2010

    Directory of Open Access Journals (Sweden)

    Jerfeson Nepumuceno Caldas

    2017-08-01

    Full Text Available Introdução: Um porto organizado dispõe de infraestrutura física, serviços e processos e é construído e aparelhado para atender às necessidades da navegação, movimentação e armazenagem de mercadorias e deslocamento de viajantes, sob a responsabilidade de uma autoridade portuária. Objetivo: Analisar os determinantes das condições higiênico-sanitárias dos portos organizados da cidade de Manaus-AM. Método: Estudo transversal e descritivo com base nos dados da Coordenação de Vigilância Sanitária de Portos, Aeroportos, Fronteiras e Recintos Alfandegados do estado do Amazonas. Os dados foram coletados dos termos de inspeção das instalações físicas dos portos emitidos no período de janeiro de 2007 a dezembro de 2010. O processamento e análise dos dados ocorreram através de planilhas do Microsoft Excel e calculadas as distribuições percentuais. A interpretação e análise dos dados ocorreram conforme categorias de análise da RDC nº 72, de 29 de dezembro de 2009, da Agência Nacional de Vigilância Sanitária. Resultados: Observou-se que os processos de higiene e limpeza e os serviços de alimentação apresentaram a maior porcentagem de inspeção e mais da metade se mostrou insatisfatória. Conclusões: Os resultados demonstraram que as autoridades portuárias devem investir no controle das condições higiênico-sanitária das instalações, processos e serviços dos portos organizados, para mitigar potenciais fatores de risco capazes de produzir agravos à saúde. =============================================== Introduction: An organized port has physical infrastructure, services and processes, and is built and equipped to meet the needs of navigation, handling and storage of goods and travelers in general, under the responsibility of a port authority. Objective: The objective of this study was to analyze the determinants of the hygienic-sanitary conditions of the organized ports of the city of Manaus-AM. Method

  18. Climate Change and Development Framings: A Comparative Analysis of the Human Development Report 2007/8 an the World Development Report 2010

    NARCIS (Netherlands)

    D.R. Gasper (Des); A.V. Portocarrero (Ana Victoria); A. Lera St. Clair

    2011-01-01

    textabstractThe Human Development Report 2007/8 (HDR) and the World Development Report 2010 (WDR) are both devoted to the connections between climate change and development. The reports provide very different perspectives on where the key challenges reside. Their policy proposals are also different,

  19. 15 CFR 2007.4 - Publication regarding requests.

    Science.gov (United States)

    2010-01-01

    ... 15 Commerce and Foreign Trade 3 2010-01-01 2010-01-01 false Publication regarding requests. 2007.4...)) § 2007.4 Publication regarding requests. (a) Whenever a request is received which conforms to these... publication of any Presidential action modifying the GSP, a summary of the decisions made will be published in...

  20. 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.

  1. 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...

  2. Safety Culture Activities of HANARO in 2007

    Energy Technology Data Exchange (ETDEWEB)

    Wu, Jong Sup [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2008-05-15

    One of the important aims of a management system for nuclear facilities is to foster a strong safety culture. The safety culture activities in HANARO have been continuously conducted to enhance its safe operation. The following activities and events on a safety culture were performed last year; - Seminars and lectures on safety for the 'Nuclear Safety Check Day' every month - Development of safety culture indicators - Development of operational SPIs (Safety Performance Indicators) - Preparation of an e-Learning program for safety education. In this paper, the safety culture activities in HANARO of KAERI are described, and the efforts necessary for a safety improvement are presented.

  3. Epidemiology of respiratory viral infections in two long-term refugee camps in Kenya, 2007-2010

    Directory of Open Access Journals (Sweden)

    Ahmed Jamal A

    2012-01-01

    Full Text Available Abstract Background Refugees are at risk for poor outcomes from acute respiratory infections (ARI because of overcrowding, suboptimal living conditions, and malnutrition. We implemented surveillance for respiratory viruses in Dadaab and Kakuma refugee camps in Kenya to characterize their role in the epidemiology of ARI among refugees. Methods From 1 September 2007 through 31 August 2010, we obtained nasopharyngeal (NP and oropharyngeal (OP specimens from patients with influenza-like illness (ILI or severe acute respiratory infections (SARI and tested them by RT-PCR for adenovirus (AdV, respiratory syncytial virus (RSV, human metapneumovirus (hMPV, parainfluenza viruses (PIV, and influenza A and B viruses. Definitions for ILI and SARI were adapted from those of the World Health Organization. Proportions of cases associated with viral aetiology were calculated by camp and by clinical case definition. In addition, for children Results We tested specimens from 1815 ILI and 4449 SARI patients (median age = 1 year. Proportion positive for virus were AdV, 21.7%; RSV, 12.5%; hMPV, 5.7%; PIV, 9.4%; influenza A, 9.7%; and influenza B, 2.6%; 49.8% were positive for at least one virus. The annual rate of SARI hospitalisation for 2007-2010 was 57 per 1000 children per year. Virus-positive hospitalisation rates were 14 for AdV; 9 for RSV; 6 for PIV; 4 for hMPV; 5 for influenza A; and 1 for influenza B. The rate of SARI hospitalisation was highest in children Conclusions Respiratory viral infections, particularly RSV and AdV, were associated with high rates of illness and make up a substantial portion of respiratory infection in these two refugee settings.

  4. The challenges facing the long term interim storage

    Energy Technology Data Exchange (ETDEWEB)

    Iracane, D. [CEA Sacaly, Dir. de la Simulation et des Outils Experimentaux-DSOE, 91 - Gif sur Yvette (France); Marvy, A. [CEA Saclay, Dir. du Developpement et de l' Innovation Nucleares-DDIN, 91 - Gif Sur Yvette (France)

    2001-07-01

    In France electricity generation by means of commercial nuclear power plants has come to a point where it contributes to the national demand at a level of 80%. The safety performance of the production system has also reached a high level of both maturity and reliability taking advantage of the cumulative effect of a 30 years long learning experience and ever more stringent safety requirements. The policy to reprocess spent fuel has been overriding but no final decision has yet been made regarding the ultimate disposition of the waste streams. Although studies on deep geological disposal are ongoing, France is also looking at whether and under which conditions a long-term interim storage may provide an effective flexibility to the fuel cycle back-end. We discuss thereafter the needs and the paramount objectives of this latter R and D program. Results are being framed as potential guiding criteria for decision makers and various stakeholders. In first part, we propose a general analysis which emphasises that a long term interim storage is more than a classical nuclear facility because it explicitly requires long-lasting control and creates a burden for Society during many generations. Then, in second part, we offer an overview of the technical results from the R and D program as they stand at the time of writing. As an answer to the Government request, a strong emphasis has been put on this research for three years. Conclusion is an attempt to outline the societal context in which future decisions will have to be made. (author)

  5. The challenges facing the long term interim storage

    International Nuclear Information System (INIS)

    Iracane, D.; Marvy, A.

    2001-01-01

    In France electricity generation by means of commercial nuclear power plants has come to a point where it contributes to the national demand at a level of 80%. The safety performance of the production system has also reached a high level of both maturity and reliability taking advantage of the cumulative effect of a 30 years long learning experience and ever more stringent safety requirements. The policy to reprocess spent fuel has been overriding but no final decision has yet been made regarding the ultimate disposition of the waste streams. Although studies on deep geological disposal are ongoing, France is also looking at whether and under which conditions a long-term interim storage may provide an effective flexibility to the fuel cycle back-end. We discuss thereafter the needs and the paramount objectives of this latter R and D program. Results are being framed as potential guiding criteria for decision makers and various stakeholders. In first part, we propose a general analysis which emphasises that a long term interim storage is more than a classical nuclear facility because it explicitly requires long-lasting control and creates a burden for Society during many generations. Then, in second part, we offer an overview of the technical results from the R and D program as they stand at the time of writing. As an answer to the Government request, a strong emphasis has been put on this research for three years. Conclusion is an attempt to outline the societal context in which future decisions will have to be made. (author)

  6. Progress and future direction for the interim safe storage and disposal of Hanford high level waste (HLW)

    International Nuclear Information System (INIS)

    Wodrich, D.D.

    1996-01-01

    This paper describes the progress made at the largest environmental cleanup program in the United States. Substantial advances in methods to start interim safe storage of Hanford Site high-level wastes, waste characterization to support both safety- and disposal-related information needs, and proceeding with cost-effective disposal by the US DOE and its Hanford Site contractors, have been realized. Challenges facing the Tank Waste Remediation System Program, which is charged with the dual and parallel missions of interim safe storage and disposal of the high-level tank waste stored at the Hanford Site, are described

  7. Report on transparency and nuclear safety. Saclay 2010

    International Nuclear Information System (INIS)

    2010-01-01

    After a presentation of the Saclay site, this report indicates the measures implemented regarding nuclear safety in the different Saclay basic nuclear installations, in terms of organization, general technical aspects, technical aspects associated with the different risks, emergency situation management, inspections, audits, and controls. It indicates the organisation of radiation protection, reports important events which occurred in 2010, and comments dose measurements performed on the different personnel (belonging to the CEA or out-sourced personnel). It reports and comments significant events about nuclear safety and radiation protection, and which occurred in the different installations. It reports and comments results of release measurements and of the impact of the centre on the environment (gas and liquid releases and their impacts on the environment, impacts due to radionuclide gas releases, gas and liquid radiological impact, chemical impact of gas and liquid releases, environment monitoring). It addresses the issue of radioactive wastes which are stored in the Saclay nuclear installations (measures to limit their volume and their impact on health and on the environment, notably soils and waters, nature and quantities of stored wastes)

  8. Failsafe automation of Phase II clinical trial interim monitoring for stopping rules.

    Science.gov (United States)

    Day, Roger S

    2010-02-01

    In Phase II clinical trials in cancer, preventing the treatment of patients on a study when current data demonstrate that the treatment is insufficiently active or too toxic has obvious benefits, both in protecting patients and in reducing sponsor costs. Considerable efforts have gone into experimental designs for Phase II clinical trials with flexible sample size, usually implemented by early stopping rules. The intended benefits will not ensue, however, if the design is not followed. Despite the best intentions, failures can occur for many reasons. The main goal is to develop an automated system for interim monitoring, as a backup system supplementing the protocol team, to ensure that patients are protected. A secondary goal is to stimulate timely recording of patient assessments. We developed key concepts and performance needs, then designed, implemented, and deployed a software solution embedded in the clinical trials database system. The system has been in place since October 2007. One clinical trial tripped the automated monitor, resulting in e-mails that initiated statistician/investigator review in timely fashion. Several essential contributing activities still require human intervention, institutional policy decisions, and institutional commitment of resources. We believe that implementing the concepts presented here will provide greater assurance that interim monitoring plans are followed and that patients are protected from inadequate response or excessive toxicity. This approach may also facilitate wider acceptance and quicker implementation of new interim monitoring algorithms.

  9. Nuclear safety and radiation protection report of the Penly nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Penly nuclear power plant (INB 136 and 140, Seine-Maritime, 76 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  10. Nuclear safety and radiation protection report of the Fessenheim nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Fessenheim nuclear power plant (INB 75, Haut-Rhin, 68 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  11. Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  12. Nuclear safety and radiation protection report of the Blayais nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Blayais nuclear power plant (INB 86 and 110, Gironde (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  13. Nuclear safety and radiation protection report of the Civaux nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Civaux nuclear power plant (INB 158 and 159, Vienne (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  14. A safety equipment list for rotary mode core sampling systems operation in single shell flammable gas tanks

    International Nuclear Information System (INIS)

    SMALLEY, J.L.

    1999-01-01

    This document identifies all interim safety equipment to be used for rotary mode core sampling of single-shell flammable gas tanks utilizing Rotary Mode Core Sampling systems (RMCS). This document provides the safety equipment for RMCS trucks HO-68K-4600, HO-68K-4647, trucks three and four respectively, and associated equipment. It is not intended to replace or supersede WHC-SD-WM-SEL-023, (Kelly 1991), or WHC-SD-WM-SEL-032, (Corbett 1994), which classifies 80-68K-4344 and HO-68K-4345 respectively. The term ''safety equipment'' refers to safety class (SC) and safety significant (SS) equipment, where equipment refers to structures, systems and components (SSC's). The identification of safety equipment in this document is based on the credited design safety features and analysis contained in the Authorization Basis (AB) for rotary mode core sampling operations in single-shell flammable gas tanks. This is an interim safety classification since the AB is interim. This document will be updated to reflect the final RMCS equipment safety classification designations upon completion of a final AB which will be implemented with the release of the Final Safety Analysis Report (FSAR)

  15. Tien jaar Duurzaam Veilig : verkeersveiligheidsbalans 1998-2007.

    NARCIS (Netherlands)

    Weijermars, W.A.M. & Schagen, I.N.L.G. van (red.)

    2009-01-01

    Ten years of Sustainable Safety; Road safety assessment 1998-2007. The road safety vision Sustainable Safety was introduced at the beginning of the Nineties. The concrete implementation of Sustainable Safety began in 1998 after the Covenant for the Start-up Programme had been signed. This road

  16. Development of dual-purpose metal cask for interim storage of spent nuclear fuel (1). Outline of cask structure

    International Nuclear Information System (INIS)

    Shimizu, Masashi; Hayashi, Makoto; Kashiwakura, Jun

    2003-01-01

    Spent fuels discharged from nuclear power plants in Japan are planed to be reprocessed at the nuclear fuel recycle plant under construction at Rokkasho-mura. Since the amount of the spent fuels exceeds that of recycled fuel, the spent fuels have to be properly stored and maintained as recycle fuel resource until the beginning of the reprocessing. For that sake, interim storage installations are being constructed outside the nuclear power plants by 2010. The storage dry casks have been practically used as the interim storage in the nuclear power plants. From this reason, the storage system using the storage dry casks is promising as the interim storage installations away form the reactors, which are under discussion. In the interim storage facilities, the storage using the dry cask of the storage metal cask with business showings, having the function of transportation is now under discussion. By employing transportation and storage dual-purpose cask, the repack equipments can be exhausted, and the reliability of the interim storage installations can be increased. Hitachi, Ltd. has been developing the high reliable and economical transportation and storage dry metal cask. In this report, the outline of our developing transportation and storage dry cask is described. (author)

  17. Temporal changes in the attitude towards smoking bans in public arenas among adults in the Capital Region of Denmark from 2007 to 2010

    DEFF Research Database (Denmark)

    Lykke, Maja; Helbech, Bodil; Glümer, Charlotte

    2014-01-01

    Aim: The population's attitude towards smoking bans in public arenas is important for their passing, implementation and compliance. Smoking bans are believed to reduce the social acceptability of smoking, and once people experience them, public support increases - also among pre-ban sceptics....... This study aimed to examine the temporal changes in public attitude towards smoking bans in public arenas from 2007 to 2010 and whether these changes differed across educational attainment, smoking status and intention to quit among smokers. Methods: Data from two surveys among adults (aged 25-79 years......) in 2007 and 2010 in the Capital Region of Denmark (n=36,472/42,504, response rate = 52.3) was linked with data on sex, age and educational attainment from central registers. Age-standardised prevalence of supportive attitude towards smoking bans was estimated. Temporal changes in supportive attitude were...

  18. Safety evaluation of the Greifswald nuclear power plant, unit 1-4

    International Nuclear Information System (INIS)

    1990-06-01

    The first interim report primarily deals with an evaluation of the pressurized components of the primary loops, especially with the embrittlement of the reactor pressure vessel material. In addition, first estimates concerning the safety design of the plants are made. The second interim report reflects the state of further studies relating to the safety design and the evaluation of operational experiences. The report includes a summarized assessment in which the recommendations cited in the technical chapters are evaluated and subdivided into three categories of backfitting measures. (orig.) [de

  19. A safety equipment list for rotary mode core sampling systems operation in single shell flammable gas tanks; TOPICAL

    International Nuclear Information System (INIS)

    SMALLEY, J.L.

    1999-01-01

    This document identifies all interim safety equipment to be used for rotary mode core sampling of single-shell flammable gas tanks utilizing Rotary Mode Core Sampling systems (RMCS). This document provides the safety equipment for RMCS trucks HO-68K-4600, HO-68K-4647, trucks three and four respectively, and associated equipment. It is not intended to replace or supersede WHC-SD-WM-SEL-023, (Kelly 1991), or WHC-SD-WM-SEL-032, (Corbett 1994), which classifies 80-68K-4344 and HO-68K-4345 respectively. The term ''safety equipment'' refers to safety class (SC) and safety significant (SS) equipment, where equipment refers to structures, systems and components (SSC's). The identification of safety equipment in this document is based on the credited design safety features and analysis contained in the Authorization Basis (AB) for rotary mode core sampling operations in single-shell flammable gas tanks. This is an interim safety classification since the AB is interim. This document will be updated to reflect the final RMCS equipment safety classification designations upon completion of a final AB which will be implemented with the release of the Final Safety Analysis Report (FSAR)

  20. Nuclear safety and radiation protection report of the nuclear facilities of Brennilis - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the partially dismantled facilities of the Monts d'Arree (EL4-D or Brennilis) site (INB 162 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  1. 75 FR 8412 - Office of New Reactors: Interim Staff Guidance on Assessing Ground Water Flow and Transport of...

    Science.gov (United States)

    2010-02-24

    ... NUCLEAR REGULATORY COMMISSION [NRC-2010-0047] Office of New Reactors: Interim Staff Guidance on Assessing Ground Water Flow and Transport of Accidental Radionuclide Releases; Solicitation of Public... ground water flow and transport of accidental radionuclide releases necessary to demonstrate compliance...

  2. Safety assessment for spent fuel storage facilities

    International Nuclear Information System (INIS)

    1994-01-01

    This Safety Practice has been prepared as part of the IAEA's programme on the safety assessment of interim spent fuel storage facilities which are not an integral part of an operating nuclear power plant. This report provides general guidance on the safety assessment process, discussing both deterministic and probabilistic assessment methods. It describes the safety assessment process for normal operation and anticipated operational occurrences and also related to accident conditions. 10 refs, 2 tabs

  3. Hydrographic changes in the Lincoln Sea in the Arctic Ocean with focus on an upper ocean freshwater anomaly between 2007 and 2010

    NARCIS (Netherlands)

    de Steur, L.; Steele, M.; Hansen, E.; Morison, J.; Polyakov, I.; Olsen, S.M.; Melling, H.; McLaughlin, F.A.; Kwok, R.; Smethie Jr., W.M.; Schlosser, P.

    2013-01-01

    Hydrographic data from the Arctic Ocean show that freshwater content in the Lincoln Sea, north of Greenland, increased significantly from 2007 to 2010, slightly lagging changes in the eastern and central Arctic. The anomaly was primarily caused by a decrease in the upper ocean salinity. In 2011

  4. Interim data quality objectives for waste pretreatment and vitrification. Revision 1

    International Nuclear Information System (INIS)

    Kupfer, M.J.; Conner, J.M.; Kirkbride, R.A.; Mobley, J.R.

    1994-01-01

    The Tank Waste Remediation System (TWRS) is responsible for storing, processing, and immobilizing the Hanford Site tank wastes. Characterization information on the tank wastes is needed so that safety concerns can be addressed, and retrieval, pretreatment, and immobilization processes can be designed, permitted, and implemented. This document describes the near-term tank waste sampling and characterization needs of the Pretreatment, High-Level Waste (HLW) Disposal, and Low-Level Waste (LLW) Disposal Programs to support the TWRS disposal mission. The final DQO (Data Quality Objective) will define specific waste tanks to be sampled, sample timing requirements, an appropriate analytical scheme, and a list of required analytes. This interim DQO, however, focuses primarily on the required analytes since the tanks to be sampled in FY 1994 and early FY 1995 are being driven most heavily by other considerations, particularly safety. The major objective of this Interim DQO is to provide guidance for tank waste characterization requirements for samples taken before completion of the final DQO. The characterization data needs defined herein will support the final DQO to help perform the following: Support the TWRS technical strategy by identification of the chemical and physical composition of the waste in the tanks and Guide development efforts to define waste pretreatment processes, which will in turn define HLW and LLW feed to vitrification processes

  5. Nuclear safety and radiation protection report of the Paluel nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-01-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Paluel nuclear power plant (INB no. 103 - Paluel 1, no. 104 - Paluel 2, no. 114 - Paluel 3 and no. 115 - Paluel 4, Cany-Barville - Seine-Maritime (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document ends with a glossary and no recommendation from the Committees for health, safety and working conditions. (J.S.)

  6. Nuclear safety and radiation protection report of the Cattenom nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Cattenom nuclear power plant (INB 124, 125, 126 and 137, Moselle (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  7. Nuclear safety and radiation protection report of the Golfech nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Golfech nuclear power plant (INB 135 and 142, Tarn-et-Garonne (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  8. Erlotinib 150 mg daily plus chemotherapy in advanced pancreatic cancer: an interim safety analysis of a multicenter, randomized, cross-over phase III trial of the 'Arbeitsgemeinschaft Internistische Onkologie'.

    Science.gov (United States)

    Boeck, Stefan; Vehling-Kaiser, Ursula; Waldschmidt, Dirk; Kettner, Erika; Märten, Angela; Winkelmann, Cornelia; Klein, Stefan; Kojouharoff, Georgi; Gauler, Thomas; Fischer von Weikersthal, Ludwig; Clemens, Michael R; Geissler, Michael; Greten, Tim F; Hegewisch-Becker, Susanna; Neugebauer, Sascha; Heinemann, Volker

    2010-01-01

    To date, only limited toxicity data are available for the combination of erlotinib with either capecitabine or gemcitabine as front-line therapy for advanced pancreatic cancer. Within a randomized phase III trial, 281 treatment-naive patients were randomly assigned between capecitabine (2000 mg/m/day, for 14 days, once every 3 weeks) plus erlotinib (150 mg/day, arm A) and gemcitabine (1000 mg/m as a 30-min infusion) plus erlotinib (150 mg/day, arm B). In case of treatment failure, patients were crossed over to a second-line treatment with the comparator cytostatic drug without erlotinib. The primary study endpoint was the time to treatment failure of second-line therapy (TTF2). This interim analysis of toxicity contains safety data from the first 127 randomized patients. During first-line therapy, patients received a median number of three treatment cycles (range 0-13) in both the arms. Regarding chemotherapy, a treatment delay was observed in 12% of the cycles in arm A and in 22% of the cycles in arm B. Dose reductions of the cytostatic drug were performed in 18 and 27% of treatment cycles, respectively. Erlotinib dose reductions were performed in 6 and 11% of all cycles. Grade 3/4 hematological toxicity was arms; major grade 3/4 toxicities in arms A and B were diarrhea (9 vs. 7%), skin rash (4 vs. 12%), and hand-foot syndrome (7 vs. 0%). No treatment-related death was observed. In conclusion, this interim safety analysis suggests that treatment with erlotinib 150 mg/day is feasible in combination with capecitabine or gemcitabine.

  9. ALSNews 2007

    International Nuclear Information System (INIS)

    McCullough, Julie; Tamura, Lori

    2007-01-01

    Compilation of Advanced Light Source newsletter, ALSNews, for 2007, Volumes 272-282. The contents of this issue are: (1) Continuing Resolution Update; (2) The Initiation of Bacterial DNA Replication; (3) Top-Off Upgrade and Operation Status; (4) SAC Reviews the Year and Looks Ahead; (5) UEC Corner: Notes from the Users Executive Committee; (6) Safety First: ALS Radiological Work Authorization Approved; (7) Coherence 2007 Workshop to Take Place in June; (8) Julie McCullough Joins the ALS Editorial Team; (9) Please Report ALS Publications by Friday, February 9; (10) ALS-Related Web News and Links; and (11) Operations Update

  10. Annual Report 2007

    Energy Technology Data Exchange (ETDEWEB)

    Swiboda, G [Institute of Atomic Energy, Otwock-Swierk (Poland)

    2008-07-01

    The Annual Report of the Institute of Atomic Energy describes the results of the research activities carried out in 2007. The document consist of eight parts: General Information; Operation and safety of MARIA reactor; Radiation protection and dosimetry; Nuclear technology in energy generation; Condensed matter physics; Nuclear techniques in health and environment protection management of hazards; Radioisotope center POLATOM and in last section in which the lists of published in 2007 papers, conferences, seminars, workshops, research projects and educational activities are presented.

  11. Annual Report 2007

    International Nuclear Information System (INIS)

    Swiboda, G.

    2008-01-01

    The Annual Report of the Institute of Atomic Energy describes the results of the research activities carried out in 2007. The document consist of eight parts: General Information; Operation and safety of MARIA reactor; Radiation protection and dosimetry; Nuclear technology in energy generation; Condensed matter physics; Nuclear techniques in health and environment protection management of hazards; Radioisotope center POLATOM and in last section in which the lists of published in 2007 papers, conferences, seminars, workshops, research projects and educational activities are presented

  12. ASN report on nuclear safety and radioprotection status in France in 2010

    International Nuclear Information System (INIS)

    2011-01-01

    After a general overview of the activity of the ASN (the French nuclear safety authority), of its missions and organisation, this activity report indicates the main events of 2010 concerning the actions performed by the ASN and the activities controlled by the ASN. These both aspects are then detailed. The actions performed by the ASN are dealing with nuclear activities (ionizing radiations and risks for health and for the environment), principles and actors of nuclear safety control, radioprotection and environment protection, regulation, control of nuclear activities and exposures to ionizing radiations, emergency situations, public information, international relationship, regional overview of nuclear safety and radioprotection. The activities controlled by the ASN are the medical uses of ionizing radiations, their non medical uses, the transport of radioactive materials, electronuclear plants, installations related to nuclear fuel cycle, nuclear research installations and other nuclear installations, the safety of nuclear installation dismantling, radioactive wastes and polluted sites

  13. Engineering and safety features of modular vault dry storage

    International Nuclear Information System (INIS)

    Deacon, D.; Wheeler, D.J.

    1984-01-01

    This paper discusses the need for interim dry storage and reviews detailed features of the Modular Vault Dry storage concept. The concept meets three basic utility requirements. Firstly, the technology and safety features have been demonstrated on existing plant; secondly, it can be built and licensed in an acceptably short timescale; and thirdly, economic analysis shows that a modular vault dry store is often the cheapest option for interim storage

  14. 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

  15. Temporal changes in the attitude towards smoking bans in public arenas among adults in the Capital Region of Denmark from 2007 to 2010.

    Science.gov (United States)

    Lykke, Maja; Helbech, Bodil; Glümer, Charlotte

    2014-07-01

    The population's attitude towards smoking bans in public arenas is important for their passing, implementation and compliance. Smoking bans are believed to reduce the social acceptability of smoking, and once people experience them, public support increases--also among pre-ban sceptics. This study aimed to examine the temporal changes in public attitude towards smoking bans in public arenas from 2007 to 2010 and whether these changes differed across educational attainment, smoking status and intention to quit among smokers. Data from two surveys among adults (aged 25-79 years) in 2007 and 2010 in the Capital Region of Denmark (n=36,472/42,504, response rate = 52.3) was linked with data on sex, age and educational attainment from central registers. Age-standardised prevalence of supportive attitude towards smoking bans was estimated. Temporal changes in supportive attitude were explored in workplaces, restaurants and bars using logistic regression models. The prevalence of supportive attitude towards smoking bans increased significantly in all arenas from 2007 to 2010. Positive temporal changes in supportive attitude towards smoking bans were seen across educational attainment, smoking status and intention to quit smoking in restaurants and across smoking status for smoking bans in workplaces and bars. The results of this study show that the public's attitude towards smoking in public arenas has changed after the implementation of a comprehensive smoking ban. This change in attitude can support implementation of future legislation on smoking and may lead to positive changes in smoking norms. © 2014 the Nordic Societies of Public Health.

  16. 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…

  17. Annual report 2007; Rapport d'activite 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The National Agency for the Radioactive Wastes Management (ANDRA), is public company, with an industrial and commercial status. This document presents the activities of the year 2007. It details the organization, the personnel, the world cooperation, the research programs, the safety, the public information and relation, the financial situation and the different sites. (A.L.B.)

  18. 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

  19. NASA Engineering Safety Center NASA Aerospace Flight Battery Systems Working Group 2007 Proactive Task Status

    Science.gov (United States)

    Manzo, Michelle A.

    2007-01-01

    In 2007, the NASA Engineering Safety Center (NESC) chartered the NASA Aerospace Flight Battery Systems Working Group to bring forth and address critical battery-related performance/manufacturing issues for NASA and the aerospace community. A suite of tasks identifying and addressing issues related to Ni-H2 and Li-ion battery chemistries was submitted and selected for implementation. The current NESC funded are: (1) Wet Life of Ni-H2 Batteries (2) Binding Procurement (3) NASA Lithium-Ion Battery Guidelines (3a) Li-Ion Performance Assessment (3b) Li-Ion Guidelines Document (3b-i) Assessment of Applicability of Pouch Cells for Aerospace Missions (3b-ii) High Voltage Risk Assessment (3b-iii) Safe Charge Rates for Li-Ion Cells (4) Availability of Source Material for Li-Ion Cells (5) NASA Aerospace Battery Workshop This presentation provides a brief overview of the tasks in the 2007 plan and serves as an introduction to more detailed discussions on each of the specific tasks.

  20. JUST Vol. 28 No. 2, August, 2007

    African Journals Online (AJOL)

    2007-08-02

    Aug 2, 2007 ... Journal of Science and Technology, Volume 27 no. 2, August, 2007. Occupational ..... provided with rubber gloves and safety boots they perceived it not to be ..... News Agency (Accra), Handbook on Occu- pational Health ...

  1. Release of radionuclides following severe accident in interim storage facility. Source term determination

    International Nuclear Information System (INIS)

    Morandi, S.; Mariani, M.; Giacobbo, F.; Covini, R.

    2006-01-01

    Among the severe accidents that can cause the release of radionuclides from an interim storage facility, with a consequent relevant radiological impact on the population, there is the impact of an aircraft on the facility. In this work, a safety assessment analysis for the case of an aircraft crash into an interim storage facility is tackled. To this aim a methodology, based upon DOE, IAEA and NUREG standard procedures and upon conservative yet realistic hypothesis, has been developed in order to evaluate the total radioactivity, source term, released to the biosphere in consequence of the impact, without recurring to the use of complicated numerical codes. The procedure consists in the identification of the accidental scenarios, in the evaluation of the consequent damage to the building structures and to the waste packages and in the determination of the total release of radionuclides through the building-atmosphere interface. The methodology here developed has been applied to the case of an aircraft crash into an interim storage facility currently under design. Results show that in case of perforation followed by a fire incident the total released activity would be greater of some orders of magnitude with respect to the case of mere perforation. (author)

  2. Nuclear safety and radiation protection report of the Flamanville nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Flamanville nuclear power plant (Manche (FR)): 2 PWR reactors in operation (INB 108 and 109), and 1 PWR under construction (Flamanville 3, INB 167). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, water consumption and waste management at Flamanville 3 construction site) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  3. Nuclear safety and radiation protection report of the Chooz nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Chooz nuclear power plant (Ardennes (FR)): 2 PWR reactors in operation (Chooz B, INB 139 and 144) and one partially dismantled PWR reactor (Chooz A, INB 163). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  4. T Tank Farm Interim Surface Barrier Demonstration--Vadose Zone Monitoring Plan

    International Nuclear Information System (INIS)

    Zhang, Z. F.; Keller, Jason M.; Strickland, Christopher E.

    2007-01-01

    The Hanford Site has 149 underground single-shell tanks that store hazardous radioactive waste. Many of these tanks and their associated infrastructure (e.g., pipelines, diversion boxes) have leaked. Some of the leaked waste has entered the groundwater. The largest known leak occurred from the T-106 Tank in 1973. Many of the contaminants from that leak still reside within the vadose zone beneath the T Tank Farm. CH2M Hill Hanford Group, Inc. seeks to minimize movement of this residual contaminant plume by placing an interim barrier on the surface. Such a barrier is expected to prevent infiltrating water from reaching the plume and moving it further. A plan has been prepared to monitor and determine the effectiveness of the interim surface barrier. Soil water content and water pressure will be monitored using off-the-shelf equipment that can be installed by the hydraulic hammer technique. In fiscal year 2006, two instrument nests were installed. Each instrument nest contains a neutron probe access tube, a capacitance probe, four heat-dissipation units, and a drain gauge to measure soil water flux. A meteorological station has been installed outside of the fence. In fiscal year 2007, two additional instrument nests are planned to be installed beneath the proposed barrier.

  5. KYT 2010 Review Report

    International Nuclear Information System (INIS)

    Apted, M.; Papp, T.; Salomaa, R.

    2008-01-01

    Public Nuclear Waste Management Program KYT2010 is a research program which is organised according to the Nuclear Energy Act for the period 2006-2010. The research programme is directed by a Steering Group, appointed by the Ministry of Trade and Industry. The Steering Group coordinates the program administration and general trends in research. A Support Group functions as reinforcement for the Steering Group. The KYT2010 research program was established to ensure that the authorities have such sufficient and comprehensive nuclear engineering expertise and other facilities at their disposal that are needed for comparisons of the various ways and methods of carrying out nuclear waste management. The research themes are divided in three areas: strategic studies of nuclear waste management, long-term safety of disposal of spent nuclear fuel, sociological studies. The Ministry of Trade and Industry decided to evaluate the scientific output of the Finnish Nuclear Waste Management Programme KYT in 2007 and asked a panel of three members to carry out the task. The evaluation was based on material supplied by the Ministry and interviews of relevant stakeholders. Those interviewed were members of the Steering Group or of the Support Group or representatives of research projects or financiers. The interviews were carried out 29.10.-2.11.2007. According to the Evaluation Panel, the achieved results are in balance with the funding in general, the expertise covers the field and the programme is balanced to different fields in nuclear waste management. As far as the reorganization of the funding is concerned in general, the research program is in balance but maintaining the balance might require broadening of integration and interaction. In addition to these general remarks, the Evaluation Panel makes several comments and recommendations. (orig.)

  6. 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.

  7. 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)

  8. 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)

  9. Technical memory 2007

    International Nuclear Information System (INIS)

    2009-01-01

    The technical memory 2007 of the Nuclear Regulatory Authority (ARN) of the Argentine Republic, compiles the papers published in the subject on radiation protection and nuclear safety, and presented in journals, technical reports, congress or meetings of these specialities by personnel of the mentioned institution during 2007. In this edition the documents are presented on: environmental protection; transport of radioactive materials; regulations; research reactors and nuclear power plants; biological radiation effects; therapeutic uses of ionizing radiation and radioprotection of patients; internal dosimetry; physical dosimetry; knowledge management; radioactive waste management [es

  10. Interim initial state report for the safety assessment SR-Can

    Energy Technology Data Exchange (ETDEWEB)

    Pers, Karin (ed.) [Kemakta Konsult AB, Stockholm (Sweden)

    2004-07-01

    A thorough description of the initial state of the engineered parts of the repository system is one of the main bases for the SR-Can safety assessment. The initial state refers to the state at the time of deposition for the spent fuel and the engineered barriers and the natural, undisturbed state at the time of beginning of excavation for the repository for the geosphere and the biosphere. The repository system is based on the KBS-3 method, where copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. For the purpose of the safety assessment the engineered portion of the repository system has been divided into a number of consecutive barriers or sub-systems. The importance of a particular feature for safety has influenced the resolution into components. In principle, components close to the source term and those that play an important role for safety are treated in more detail than more peripheral components. For the option with 40 years of reactor operation, the quantity of BWR fuel is estimated at 7200 tonnes and the quantity of PWR fuel at 2300 tonnes. The fuel burn-up may vary from 15 MWd/kgU up to 60 MWd/kg. Geometric aspects of the fuel cladding tubes of importance in the safety assessment are, as a rule, handled sufficiently pessimistically in analyses of radionuclide transport that differences between different fuel types are irrelevant. The relative differences in radionuclide inventory with respect to burn-up are small. Deviations in inventory and deviating or damaged fuel are not considered in the SR-Can interim reporting but will be handled in the final reporting of SR-Can. The canister consists of an inner container, the insert of cast iron and an outer shell of copper. The cast iron insert provides mechanical stability and the copper shell protects against corrosion in the repository environment. The copper shell is 5 cm thick and

  11. Interim initial state report for the safety assessment SR-Can

    International Nuclear Information System (INIS)

    Pers, Karin

    2004-07-01

    A thorough description of the initial state of the engineered parts of the repository system is one of the main bases for the SR-Can safety assessment. The initial state refers to the state at the time of deposition for the spent fuel and the engineered barriers and the natural, undisturbed state at the time of beginning of excavation for the repository for the geosphere and the biosphere. The repository system is based on the KBS-3 method, where copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. For the purpose of the safety assessment the engineered portion of the repository system has been divided into a number of consecutive barriers or sub-systems. The importance of a particular feature for safety has influenced the resolution into components. In principle, components close to the source term and those that play an important role for safety are treated in more detail than more peripheral components. For the option with 40 years of reactor operation, the quantity of BWR fuel is estimated at 7200 tonnes and the quantity of PWR fuel at 2300 tonnes. The fuel burn-up may vary from 15 MWd/kgU up to 60 MWd/kg. Geometric aspects of the fuel cladding tubes of importance in the safety assessment are, as a rule, handled sufficiently pessimistically in analyses of radionuclide transport that differences between different fuel types are irrelevant. The relative differences in radionuclide inventory with respect to burn-up are small. Deviations in inventory and deviating or damaged fuel are not considered in the SR-Can interim reporting but will be handled in the final reporting of SR-Can. The canister consists of an inner container, the insert of cast iron and an outer shell of copper. The cast iron insert provides mechanical stability and the copper shell protects against corrosion in the repository environment. The copper shell is 5 cm thick and

  12. 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.

  13. 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

  14. 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.

  15. 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)

  16. Proceedings of the Topical Meeting on the safety of nuclear fuel cycle intermediate storage facilities

    International Nuclear Information System (INIS)

    1998-01-01

    The CSNI Working Group on Fuel Cycle Safety held an International Topical Meeting on safety aspects of Intermediate Storage Facilities in Newby Bridge, England, from 28 to 30 October 1997. The main purpose of the meeting was to provide a forum for the exchange of information on the technical issues on the safety of nuclear fuel cycle facilities (intermediate storage). Titles of the papers are: An international view on the safety challenges to interim storage of spent fuel. Interim storage of intermediate and high-level waste in Belgium: a description and safety aspects. Encapsulated intermediate level waste product stores at Sellafield. Safety of interim storage facilities of spent fuel: the international dimension and the IAEA's activities. Reprocessing of irradiated fuel and radwaste conditioning at Belgoprocess site: an overview. Retrieval of wastes from interim storage silos at Sellafield. Outline of the fire and explosion of the bituminization facility and the activities of the investigation committee (STAIJAERI). The fire and explosion incident of the bituminization facility and the lessons learned from the incident. Study on the scenario of the fire incident and related analysis. Study on the scenario of the explosion incident and related analysis. Accident investigation board report on the May 14, 1997 chemical explosion at the plutonium reclamation facility, Hanford site, Richland, Washington. Dry interim storage of spent nuclear fuel elements in Germany. Safe and effective system for the bulk receipt and storage of light water reactor fuel prior to reprocessing. Receiving and storage of glass canisters at vitrified waste storage center of Japan Nuclear Fuel Ltd. Design and operational experience of dry cask storage systems. Sellafield MOX plant; Plant safety design (BNFL). The assessment of fault studies for intermediate term waste storage facilities within the UK nuclear regulatory regime. Non-active and active commissioning of the thermal oxide

  17. Trends in World Silk Cocoons and Silk Production and Trade, 2007-2010

    Directory of Open Access Journals (Sweden)

    AGATHA AGATHA POPESCU

    2013-10-01

    Full Text Available The paper aimed to analyze world production and trade for fresh silk cocoons and raw silk using FAO Stat data for  the  period 2007-2010. The use of index, share and comparison methods allowed to identify the major trends in the analyzed period. Silk decline was determined by the increased importance of cotton and artificial fibres in textile and clothing industry. Important changes are taking place on silk cocoons and silk market. While, the European market decreased, the Asian market has mainly developed fresh cocoons and raw silk, while the European market became more interested of clothes. Silk consumption declined because of consumer’s preference for synthetic fibres, except traditional consumers from Asia.  China is the main producer and exporter of fresh and dry cocoons, while raw silk is produced and exported by China, Brazil and Italy and imported by India, Japan and Italy. In Europe, Bulgaria is the top producer of fresh cocoons and raw silk and Italy is the main raw silk importer and the top producer and exporter of textile and fashion clothes. Silk will remain an important raw material for producing high quality and luxury clothes.

  18. The nuclear safety authority (ASN) presents its report on the status of nuclear safety and radiation protection in France in 2010

    International Nuclear Information System (INIS)

    2011-01-01

    After a presentation of the French nuclear safety authority (ASN) and of some events which occurred in 2010, this report present the actions performed by the ASN in different fields: nuclear activities (ionizing radiations and risks for health and for the environment), principles and actors of control of nuclear safety, radiation protection and environment protection, regulation, control of nuclear activities and of exposures to ionizing radiations, emergency situations, public information and transparency, international relationship. It proposes a regional overview of nuclear safety and radiation protection in France. It addresses the activities controlled by the ASN: medical and non medical usages of ionizing radiations, transportation of radioactive materials, electronuclear power stations, installations involved in the nuclear fuel cycle, research nuclear installations and other nuclear installations, safety in basic nuclear installation dismantling, radioactive wastes and polluted sites

  19. Cannabis use and bone mineral density: NHANES 2007-2010.

    Science.gov (United States)

    Bourne, Donald; Plinke, Wesley; Hooker, Elizabeth R; Nielson, Carrie M

    2017-12-01

    Cannabis use is rising in the USA. Its relationship to cannabinoid signaling in bone cells implies its use could affect bone mineral density (BMD) in the population. In a national survey of people ages 20-59, we found no association between self-reported cannabis use and BMD of the hip or spine. Cannabis is the most widely used illegal drug in the USA, and its recreational use has recently been approved in several US states. Cannabinoids play a role in bone homeostasis. We aimed to determine the association between cannabis use and BMD in US adults. In the National Health and Nutrition Examination Survey 2007-2010, 4743 participants between 20 and 59 years old, history of cannabis use was categorized into never, former (previous use, but not in last 30 days), light (1-4 days of use in last 30 days), and heavy (≥5 days of use in last 30 days). Multivariable linear regression was used to test the association between cannabis use and DXA BMD of the proximal femur and lumbar spine with adjustment for age, sex, BMI, and race/ethnicity among other BMD determinants. Sixty percent of the population reported ever using cannabis; 47% were former users, 5% were light users, and 7% were heavy users. Heavy cannabis users were more likely to be male, have a lower BMI, increased daily alcohol intake, increased tobacco pack-years, and were more likely to have used other illegal drugs (cocaine, heroin, or methamphetamines). No association between cannabis and BMD was observed for any level of use (p ≥ 0.28). A history of cannabis use, although highly prevalent and related to other risk factors for low BMD, was not independently associated with BMD in this cross-sectional study of American men and women.

  20. Nuclear safety and radiation protection report of the Cruas-Meysse nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Cruas-Meysse nuclear power plant (INB 111 and 112, Ardeche (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  1. Operations and Maintenance Concept Plan for the Immobilized High Level Waste (IHLW) Interim Storage Facility

    Energy Technology Data Exchange (ETDEWEB)

    JANIN, L.F.

    2000-08-30

    This O&M Concept looks at the future operations and maintenance of the IHLW/CSB interim storage facility. It defines the overall strategy, objectives, and functional requirements for the portion of the building to be utilized by Project W-464. The concept supports the tasks of safety basis planning, risk mitigation, alternative analysis, decision making, etc. and will be updated as required to support the evolving design.

  2. Operations and Maintenance Concept Plan for the Immobilized High-Level Waste (IHLW) Interim Storage Facility

    International Nuclear Information System (INIS)

    JANIN, L.F.

    2000-01-01

    This OandM Concept looks at the future operations and maintenance of the IHLW/CSB interim storage facility. It defines the overall strategy, objectives, and functional requirements for the portion of the building to be utilized by Project W-464. The concept supports the tasks of safety basis planning, risk mitigation, alternative analysis, decision making, etc. and will be updated as required to support the evolving design

  3. Idaho National Laboratory Integrated Safety Management System 2010 Effectiveness Review and Declaration Report

    Energy Technology Data Exchange (ETDEWEB)

    Thomas J. Haney

    2010-12-01

    Idaho National Laboratory completes an annual Integrated Safety Management System effectiveness review per 48 CFR 970.5223-1 “Integration of Environment, Safety and Health into Work Planning and Execution.” The annual review assesses ISMS effectiveness, provides feedback to maintain system integrity, and helps identify target areas for focused improvements and assessments for the following year. Using one of the three Department of Energy (DOE) descriptors in DOE M 450.4-1 regarding the state of ISMS effectiveness during Fiscal Year (FY) 2010, the information presented in this review shows that INL achieved “Effective Performance.”

  4. Nuclear safety and radiation protection report of the Chinon nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Chinon nuclear power plant (Indre-et-Loire, 37 (FR)): 4 PWR reactors in operation (Chinon B, INB 107 and 132), 3 partially dismantled graphite-gas reactors (Chinon A, INB 133, 153 and 161), a workshop for irradiated materials (AMI, INB 94), and an inter-regional fuel storage facility (MIR, INB 99). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  5. Nuclear safety and radiation protection report of the Bugey nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Bugey nuclear power plant (Ain (FR)): 4 PWR reactors in operation (INB 78 and 89), one partially dismantled graphite-gas reactor (INB 45), an inter-regional fuel storage facility (MIR, INB 102), and a radioactive waste storage and conditioning facility under construction (ICEDA, INB 173). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  6. 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)

  7. 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...

  8. Climate data used to study the potential impacts of climate change on future hydrological regimes and water resources (2010-2050) in the Philippines

    NARCIS (Netherlands)

    Tolentino, Pamela Louise M.; Poortinga, A.; Kanamaru, Hideki; Keesstra, S.D.; Maroulis, J.; David, Carlos Primo C.; Ritsema, C.J.

    2016-01-01

    The collection contains downscaled ERA-Interim and climate scenario data, derived from three global climate models (BCM2, CNCM3 and MPEH5), for the Philippines. ERA-Interim (1979-2010) is the reanalysis dataset used to generate climate data in the absence of actual climate observations.

  9. Coccidiodomycosis in Arizona 2007-2008

    Centers for Disease Control (CDC) Podcasts

    2010-10-13

    This podcast looks at the impact of Coccidioidomycosis, or Valley Fever, in Arizona in 2007 and early 2008. CDC epidemiologist Dr. Tom Chiller discusses what researchers learned about this fungal disease.  Created: 10/13/2010 by National Center for Emerging and Zoonotic Infectious Diseases (NCEZID).   Date Released: 10/27/2010.

  10. SAFETY BASIS DESIGN DEVELOPMENT CHALLENGES IMECE2007-42747

    Energy Technology Data Exchange (ETDEWEB)

    RYAN GW

    2007-09-24

    'Designing in Safety' is a desired part of the development of any new potentially hazardous system, process, or facility. It is a required part of nuclear safety activities as specified in the U.S. Department of Energy (DOE) Order 420.B, Facility Safety. This order addresses the design of nuclear related facilities developed under federal regulation IOCFR830, Nuclear Safety Management. IOCFR830 requires that safety basis documentation be provided to identify how nuclear safety is being adequately addressed as a condition for system operation (e.g., the safety basis). To support the development of the safety basis, a safety analysis is performed. Although the concept of developing a design that addresses 'Safety is simple, the execution can be complex and challenging. This paper addresses those complexities and challenges for the design activity of a system to treat sludge, a corrosion product of spent nuclear fuel, at DOE's Hanford Site in Washington State. The system being developed is referred to as the Sludge Treatment Project (STP). This paper describes the portion of the safety analysis that addresses the selection of design basis events using the experience gained from the STP and the development of design requirements for safety features associated with those events. Specifically, the paper describes the safety design process and the application of the process for two types of potential design basis accidents associated with the operation of the system, (1) flashing spray leaks and (2) splash and splatter leaks. Also presented are the technical challenges that are being addressed to develop effective safety features to deal with these design basis accidents.

  11. SAFETY BASIS DESIGN DEVELOPMENT CHALLENGES IMECE2007-42747

    International Nuclear Information System (INIS)

    RYAN GW

    2007-01-01

    'Designing in Safety' is a desired part of the development of any new potentially hazardous system, process, or facility. It is a required part of nuclear safety activities as specified in the U.S. Department of Energy (DOE) Order 420.B, Facility Safety. This order addresses the design of nuclear related facilities developed under federal regulation IOCFR830, Nuclear Safety Management. IOCFR830 requires that safety basis documentation be provided to identify how nuclear safety is being adequately addressed as a condition for system operation (e.g., the safety basis). To support the development of the safety basis, a safety analysis is performed. Although the concept of developing a design that addresses 'Safety is simple, the execution can be complex and challenging. This paper addresses those complexities and challenges for the design activity of a system to treat sludge, a corrosion product of spent nuclear fuel, at DOE's Hanford Site in Washington State. The system being developed is referred to as the Sludge Treatment Project (STP). This paper describes the portion of the safety analysis that addresses the selection of design basis events using the experience gained from the STP and the development of design requirements for safety features associated with those events. Specifically, the paper describes the safety design process and the application of the process for two types of potential design basis accidents associated with the operation of the system, (1) flashing spray leaks and (2) splash and splatter leaks. Also presented are the technical challenges that are being addressed to develop effective safety features to deal with these design basis accidents

  12. Changes in the antibiotic susceptibility of anaerobic bacteria from 2007-2009 to 2010-2012 based on the CLSI methodology.

    Science.gov (United States)

    Hastey, Christine J; Boyd, Halsey; Schuetz, Audrey N; Anderson, Karen; Citron, Diane M; Dzink-Fox, Jody; Hackel, Meredith; Hecht, David W; Jacobus, Nilda V; Jenkins, Stephen G; Karlsson, Maria; Knapp, Cynthia C; Koeth, Laura M; Wexler, Hannah; Roe-Carpenter, Darcie E

    2016-12-01

    Antimicrobial susceptibility testing of anaerobic isolates was conducted at four independent sites from 2010 to 2012 and compared to results from three sites during the period of 2007-2009. This data comparison shows significant changes in antimicrobial resistance in some anaerobic groups. Therefore, we continue to recommend institutions regularly perform susceptibility testing when anaerobes are cultured from pertinent sites. Annual generation of an institutional-specific antibiogram is recommended for tracking of resistance trends over time. Copyright © 2016 Elsevier Ltd. All rights reserved.

  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. 78 FR 42012 - Safety Zone and Regulated Navigation Area; Chicago Sanitary and Ship Canal, Romeoville, IL

    Science.gov (United States)

    2013-07-15

    ... is issuing this Interim Rule to address two omissions from the regulatory text of the Safety zone and... boats, etc.). This revision is intended to make the regulatory text consistent with the discussion of... of Homeland Security IR Interim Rule NPRM Notice of Proposed Rulemaking RNA Regulated Navigation Area...

  15. Safety Aspects for Vertical Wall Breakwaters

    DEFF Research Database (Denmark)

    Sørensen, John Dalsgaard; Burcharth, H. F.; Christiani, E.

    1996-01-01

    In this appendix some safety aspects in relation to vertical wall breakwaters are discussed. Breakwater structures such as vertical wall breakwaters are used under quite different conditions. The expected lifetime can be from 5 years (interim structure) to 100 years (permanent structure) and the ...

  16. [Prevalence of overwight and obesity among children under five years in Peru 2007-2010].

    Science.gov (United States)

    Pajuelo-Ramírez, Jaime; Miranda-Cuadros, Marianella; Campos-Sánchez, Miguel; Sánchez-Abanto, José

    2011-06-01

    To estimate the prevalence of overweight and obesity in children under five in Peru in the years 2007-2010 and to describe according to geographical areas, poverty levels, maternal education, breastfeeding, child age, sex and birth weight. continuous (repeated cross-sectional) multistage, random sampling survey from the universe of children under five-years and pregnant women living in Peru, divided into five geographical areas. Out of 3,669 children, 50.3% were males (Lima N=680, Remaining Coast N=763, Urban Sierra N=719, Rural Sierra N=699, Jungle N=808) having their weight and height measured according to international standards. The national prevalence of overweight and obesity was 6.9%, with Metropolitan Lima (10.1%) as the highest and in the Jungle (2.6%) as the lowest. Age, sex, geographical area and birth weight were identified as risk factors through multiple logistic regression. overweight and obesity are higher in Lima, during the first year of age and when birth weight is more than 2.5 Kg.

  17. 76 FR 17160 - Office of New Reactors; Final Interim Staff Guidance on the Review of Nuclear Power Plant Designs...

    Science.gov (United States)

    2011-03-28

    ... design certification (DC) application for new nuclear power reactors under Title 10 of the Code of... NUCLEAR REGULATORY COMMISSION [NRC-2010-0033; DC/COL-ISG-021] Office of New Reactors; Final Interim Staff Guidance on the Review of Nuclear Power Plant Designs Using a Gas Turbine Driven Standby...

  18. 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

  19. Biosphere analysis for selected cases in TILA-99 and in KBS-3H safety evaluation 2007

    International Nuclear Information System (INIS)

    Broed, R.; Avila, R.; Bergstroem, U.; Hjerpe, T.; Ikonen, A.

    2008-12-01

    The KBS-3 method, based on multiple barriers, is the proposed spent fuel disposal method both in Sweden and Finland. KBS-3H and KBS-3V are the two design alternatives of the KBS-3 spent fuel disposal method. Posiva and SKB have conducted a joint research, demonstration and development (RD and D) programme in 2002-2007 with the overall aim of establishing whether KBS-3H represents a feasible alternative to the reference alternative KBS-3V. The overall objectives of the present phase covering the period 2004-2007 have been to demonstrate that the horizontal deposition alternative is technically feasible and to demonstrate that it fulfils the same long-term safety requirements as KBS-3V. The safety studies conducted as part of this programme include a safety assessment of a preliminary design of a KBS-3H repository for spent nuclear fuel located about 400 m underground at the Olkiluoto site, which is the proposed site for a spent fuel repository in Finland. This report summarises the biosphere analysis conducted in the KBS-3H safety studies. The most important components of the analysis are presented in this report: i) predictions of the physical terrain and the ecosystems possibly receiving contaminant releases from the repository, ii) modelling of the transport of radionuclides in the entire landscape, taking into account that the ecosystems currently present at the site will evolve over time, and, iii) the estimation of potential doses to humans. The main outcome from the present analysis, dealing with radiological safety and compliance with regulatory requirements, is the annual landscape dose, which is related to individuals fully utilising the maximum production of food and water from the potentially contaminated area. In order to facilitate comparisons with earlier assessments, resulting release rates into the biosphere, from both KBS-3H and TILA-99 calculation cases, were used as inputs for the biosphere analysis. The present study shows that none of the

  20. Development of a probabilistic safety assessment framework for an interim dry storage facility subjected to an aircraft crash using best-estimate structural analysis

    International Nuclear Information System (INIS)

    Almomani, Belal; Jang, Dong Chan; Lee, Sang Hoon; Kang, Hyun Gook

    2017-01-01

    Using a probabilistic safety assessment, a risk evaluation framework for an aircraft crash into an interim spent fuel storage facility is presented. Damage evaluation of a detailed generic cask model in a simplified building structure under an aircraft impact is discussed through a numerical structural analysis and an analytical fragility assessment. Sequences of the impact scenario are shown in a developed event tree, with uncertainties considered in the impact analysis and failure probabilities calculated. To evaluate the influence of parameters relevant to design safety, risks are estimated for three specification levels of cask and storage facility structures. The proposed assessment procedure includes the determination of the loading parameters, reference impact scenario, structural response analyses of facility walls, cask containment, and fuel assemblies, and a radiological consequence analysis with dose–risk estimation. The risk results for the proposed scenario in this study are expected to be small relative to those of design basis accidents for best-estimated conservative values. The importance of this framework is seen in its flexibility to evaluate the capability of the facility to withstand an aircraft impact and in its ability to anticipate potential realistic risks; the framework also provides insight into epistemic uncertainty in the available data and into the sensitivity of the design parameters for future research

  1. Development of a Probabilistic Safety Assessment Framework for an Interim Dry Storage Facility Subjected to an Aircraft Crash Using Best-Estimate Structural Analysis

    Directory of Open Access Journals (Sweden)

    Belal Almomani

    2017-03-01

    Full Text Available Using a probabilistic safety assessment, a risk evaluation framework for an aircraft crash into an interim spent fuel storage facility is presented. Damage evaluation of a detailed generic cask model in a simplified building structure under an aircraft impact is discussed through a numerical structural analysis and an analytical fragility assessment. Sequences of the impact scenario are shown in a developed event tree, with uncertainties considered in the impact analysis and failure probabilities calculated. To evaluate the influence of parameters relevant to design safety, risks are estimated for three specification levels of cask and storage facility structures. The proposed assessment procedure includes the determination of the loading parameters, reference impact scenario, structural response analyses of facility walls, cask containment, and fuel assemblies, and a radiological consequence analysis with dose–risk estimation. The risk results for the proposed scenario in this study are expected to be small relative to those of design basis accidents for best-estimated conservative values. The importance of this framework is seen in its flexibility to evaluate the capability of the facility to withstand an aircraft impact and in its ability to anticipate potential realistic risks; the framework also provides insight into epistemic uncertainty in the available data and into the sensitivity of the design parameters for future research.

  2. Development of a probabilistic safety assessment framework for an interim dry storage facility subjected to an aircraft crash using best-estimate structural analysis

    Energy Technology Data Exchange (ETDEWEB)

    Almomani, Belal; Jang, Dong Chan [Dept. of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of); Lee, Sang Hoon [Dept. of Mechanical and Automotive Engineering, Keimyung University, Daegu (Korea, Republic of); Kang, Hyun Gook [Dept. of Mechanical, Aerospace and Nuclear Engineering, Rensselaer Polytechnic Institute, Troy (United States)

    2017-03-15

    Using a probabilistic safety assessment, a risk evaluation framework for an aircraft crash into an interim spent fuel storage facility is presented. Damage evaluation of a detailed generic cask model in a simplified building structure under an aircraft impact is discussed through a numerical structural analysis and an analytical fragility assessment. Sequences of the impact scenario are shown in a developed event tree, with uncertainties considered in the impact analysis and failure probabilities calculated. To evaluate the influence of parameters relevant to design safety, risks are estimated for three specification levels of cask and storage facility structures. The proposed assessment procedure includes the determination of the loading parameters, reference impact scenario, structural response analyses of facility walls, cask containment, and fuel assemblies, and a radiological consequence analysis with dose–risk estimation. The risk results for the proposed scenario in this study are expected to be small relative to those of design basis accidents for best-estimated conservative values. The importance of this framework is seen in its flexibility to evaluate the capability of the facility to withstand an aircraft impact and in its ability to anticipate potential realistic risks; the framework also provides insight into epistemic uncertainty in the available data and into the sensitivity of the design parameters for future research.

  3. 40 CFR 86.1363-2007 - Steady-state testing with a discrete-mode cycle.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 19 2010-07-01 2010-07-01 false Steady-state testing with a discrete-mode cycle. 86.1363-2007 Section 86.1363-2007 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY... Exhaust Test Procedures § 86.1363-2007 Steady-state testing with a discrete-mode cycle. This section...

  4. 2010 International consensus algorithm for the diagnosis, therapy and management of hereditary angioedema

    Directory of Open Access Journals (Sweden)

    Bowen Tom

    2010-07-01

    Full Text Available Abstract Background We published the Canadian 2003 International Consensus Algorithm for the Diagnosis, Therapy, and Management of Hereditary Angioedema (HAE; C1 inhibitor [C1-INH] deficiency and updated this as Hereditary angioedema: a current state-of-the-art review: Canadian Hungarian 2007 International Consensus Algorithm for the Diagnosis, Therapy, and Management of Hereditary Angioedema. Objective To update the International Consensus Algorithm for the Diagnosis, Therapy and Management of Hereditary Angioedema (circa 2010. Methods The Canadian Hereditary Angioedema Network (CHAEN/Réseau Canadien d'angioédème héréditaire (RCAH http://www.haecanada.com and cosponsors University of Calgary and the Canadian Society of Allergy and Clinical Immunology (with an unrestricted educational grant from CSL Behring held our third Conference May 15th to 16th, 2010 in Toronto Canada to update our consensus approach. The Consensus document was reviewed at the meeting and then circulated for review. Results This manuscript is the 2010 International Consensus Algorithm for the Diagnosis, Therapy and Management of Hereditary Angioedema that resulted from that conference. Conclusions Consensus approach is only an interim guide to a complex disorder such as HAE and should be replaced as soon as possible with large phase III and IV clinical trials, meta analyses, and using data base registry validation of approaches including quality of life and cost benefit analyses, followed by large head-to-head clinical trials and then evidence-based guidelines and standards for HAE disease management.

  5. Results report. Sampling and analyses of gases and microorganisms in the water from MINICAN in 2007, 2008 and 2010

    Energy Technology Data Exchange (ETDEWEB)

    Lydmark, Sara; Hallbeck, Lotta (Microbial Analytics Sweden AB (Sweden))

    2011-04-15

    The MINICAN project is located at the depth of 450 m in the Aespoe Hard Rock Laboratory and was initiated to study how corrosion of the cast iron insert inside a perforated copper canister would evolve with time. Miniature canisters with different perforations and with and without bentonite buffer in steel cages were installed and monitored. Samples for microbiological and gas composition together with samples for groundwater chemistry have been analysed at three occasions in 2007, 2008 and 2010. The results show how the microbial populations outside the canisters have evolved from a mixture of microorganism able to grow on organic material, like heterotrophic organisms, and acetogens that grow on hydrogen gas and carbon dioxide in 2007, to populations with a large proportion of sulphate-reducing bacteria in 2010. The highest number of sulphate-reducing bacteria was found in MINICAN experiment A02C, canister with one hole at the top of the copper canister, in 2010 with 2.4 x 104 mL-1 followed by 8 x 103 mL-1 in A03 (hole in the bottom of the canister) and 7 x 103 mL-1 in A06 (two holes at the top and no bentonite). The numbers of culturable heterotrophic bacteria were between 200 and 530 mL-1 in the experiments with bentonite in 2007 but below detection in all experiments in 2010. The same trend was shown for acetogenes. Measurable amounts of hydrogen gas were found in all experiments at all sampling occasions. There was no general trend for the amounts of hydrogen but there was an increase in three of the experiments and in the groundwater outside MINICAN. It was found that the water chemistry differed between A06 and A02-A04 experiment by higher sulphate and chloride concentrations in A06 compared to the others. By plotting the concentrations of chloride, sulphate against time, a decrease in sulphate concentration was found in all canister experiments. The chloride concentrations were stable during the same period. On the other hand, an increase in sulphate

  6. Results report. Sampling and analyses of gases and microorganisms in the water from MINICAN in 2007, 2008 and 2010

    International Nuclear Information System (INIS)

    Lydmark, Sara; Hallbeck, Lotta

    2011-04-01

    The MINICAN project is located at the depth of 450 m in the Aespoe Hard Rock Laboratory and was initiated to study how corrosion of the cast iron insert inside a perforated copper canister would evolve with time. Miniature canisters with different perforations and with and without bentonite buffer in steel cages were installed and monitored. Samples for microbiological and gas composition together with samples for groundwater chemistry have been analysed at three occasions in 2007, 2008 and 2010. The results show how the microbial populations outside the canisters have evolved from a mixture of microorganism able to grow on organic material, like heterotrophic organisms, and acetogens that grow on hydrogen gas and carbon dioxide in 2007, to populations with a large proportion of sulphate-reducing bacteria in 2010. The highest number of sulphate-reducing bacteria was found in MINICAN experiment A02C, canister with one hole at the top of the copper canister, in 2010 with 2.4 x 10 4 mL -1 followed by 8 x 10 3 mL -1 in A03 (hole in the bottom of the canister) and 7 x 10 3 mL -1 in A06 (two holes at the top and no bentonite). The numbers of culturable heterotrophic bacteria were between 200 and 530 mL-1 in the experiments with bentonite in 2007 but below detection in all experiments in 2010. The same trend was shown for acetogenes. Measurable amounts of hydrogen gas were found in all experiments at all sampling occasions. There was no general trend for the amounts of hydrogen but there was an increase in three of the experiments and in the groundwater outside MINICAN. It was found that the water chemistry differed between A06 and A02-A04 experiment by higher sulphate and chloride concentrations in A06 compared to the others. By plotting the concentrations of chloride, sulphate against time, a decrease in sulphate concentration was found in all canister experiments. The chloride concentrations were stable during the same period. On the other hand, an increase in sulphate

  7. Annual report 2007 Manche center; Rapport annuel 2007 Centre Manche

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The National Agency for the Radioactive Wastes Management (ANDRA), is public company, with an industrial and commercial status. This document presents the activities of the year 2007 for the Manche center. It details the installations, the safety and radiation protection policy, the main events of the tear, the radioactive wastes management and the public information mission. (A.L.B.)

  8. Annual report 2007 Aube center; Rapport annuel 2007 Centre Aube

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The National Agency for the Radioactive Wastes Management (ANDRA), is public company, with an industrial and commercial status. This document presents the activities of the year 2007 for the Aube center. It details the installations, the safety and radiation protection policy, the main events of the tear, the radioactive wastes management and the public information mission. (A.L.B.)

  9. Patient Safety Activity Under the Social Insurance Medical Fee Schedule in Japan: An Overview of the 2010 Nationwide Survey.

    Science.gov (United States)

    Hirose, Masahiro; Kawamura, Toshihiko; Igawa, Mikio; Imanaka, Yuichi

    2017-11-16

    Little is known about patient safety performance under the social insurance medical fee schedule in Japan. The Health Ministry in Japan introduced the preferential patient safety countermeasure fee (PPSCF) to promote patient safety in 2006 and revised the PPSCF system in 2010. This study aims to address the patient safety performance status at hospitals implementing the PPSCF. A nationwide questionnaire survey targeting 2674 hospitals with the PPSCF was performed in 2010 to 2011. The 627 participant hospitals were divided into the following three groups: 178 hospitals implementing PPSCF 1 with 400 beds or more (group A), 286 hospitals implementing PPSCF 1 with 399 beds or fewer (group B), and 163 hospitals implementing PPSCF 2 (group C). The mean numbers (standard errors) of patient safety managers were 1.45 (0.07) in group A, 1.12 (0.04) in group B, and 0.37 (0.12) in group C (P fee schedule in Japan.

  10. 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.…

  11. T Tank Farm Interim Cover Test - Design Plan

    International Nuclear Information System (INIS)

    Zhang, Z. F.; Keller, Jason M.

    2006-01-01

    The Hanford Site has 149 underground single-shell tanks that store hazardous radioactive waste. Many of these tanks and their associated infrastructure (e.g., pipelines, diversion boxes) have leaked. Some of the leaked waste has entered the groundwater. The largest known leak occurred from the T-106 Tank in 1973. Many of the contaminants from that leak still reside within the vadose zone beneath the T Tank Farm. CH2M Hill Hanford Group, Inc. seeks to minimize movement of this residual contaminant plume by placing an interim cover on the surface. Such a cover is expected to prevent infiltrating water from reaching the plume and moving it further. Pacific Northwest National Laboratory has prepared a design plan to monitor and determine the effectiveness of the interim cover. A three-dimensional numerical simulation of water movement beneath a cover was conducted to guide the design of the plan. Soil water content, water pressure, and temperature will be monitored using off-the-shelf equipment that can be installed by the hydraulic hammer technique. In fiscal year 2006, two instrument nests will be installed, one inside and one outside of the proposed cover. In fiscal year 2007, two additional instrument nests, both inside the proposed cover, will be installed. Each instrument nest contains a neutron access tube and a capacitance probe (to measure water content), and four heat-dissipation units (to measure pressure head and temperature). A datalogger and a meteorological station will be installed outside of the fence. Two drain gauges will be installed in locations inside and outside the cover for the purpose of measuring soil water flux.

  12. Coalbed natural gas exploration, drilling activities, and geologic test results, 2007-2010

    Science.gov (United States)

    Clark, Arthur C.

    2014-01-01

    The U.S. Geological Survey, in partnership with the U.S. Bureau of Land Management, the North Slope Borough, and the Arctic Slope Regional Corporation conducted a four-year study designed to identify, define, and delineate a shallow coalbed natural gas (CBNG) resource with the potential to provide locally produced, affordable power to the community of Wainwright, Alaska. From 2007 through 2010, drilling and testing activities conducted at three sites in or near Wainwright, identified and evaluated an approximately 7.5-ft-thick, laterally continuous coalbed that contained significant quantities of CBNG. This coalbed, subsequently named the Wainwright coalbed, was penetrated at depths ranging from 1,167 ft to 1,300 ft below land surface. Core samples were collected from the Wainwright coalbed at all three drill locations and desorbed-gas measurements were taken from seventeen 1-ft-thick sections of the core. These measurements indicate that the Wainwright coalbed contains enough CBNG to serve as a long-term energy supply for the community. Although attempts to produce viable quantities of CBNG from the Wainwright coalbed proved unsuccessful, it seems likely that with proper well-field design and by utilizing currently available drilling and reservoir stimulation techniques, this CBNG resource could be developed as a long-term economically viable energy source for Wainwright.

  13. Report on administrative work for radiation safety from April 2010 to March 2011

    International Nuclear Information System (INIS)

    Nishimura, Kiyohiko; Uda, Tatsuhiko; Asakura, Yamato; Kawano, Takao; Yamanishi, Hirokuni; Miyake, Hitoshi; Tanaka, Masahiro

    2011-12-01

    The National Institute for Fusion Science (NIFS) is proceeding with basic research on magnetic nuclear fusion which is expected to be a perpetual energy source for the future. Because the object of research is a hot plasma, high energy particles which are elements of the plasma generate X-rays. Therefore we administrate the devices and their surroundings in conformity with the Industrial Safety and Health Law to maintain workplace safety. We measure the radiation dose levels regularly, register the employees who are engaged in plasma experiments, and educate them. We also control the handling of non-regulated small sealed sources that are used in the detectors in some cases. This report is on administrative work for radiation safety in the last fiscal year 2010. It includes (1) a report on the establishment of a radiation safety management system, (2) results of radiation dose measurement and monitoring in the radiation controlled area and on the site by using Radiation Monitoring System Applicable to Fusion Experiment (RMSAFE), (3) a report on the establishment of an education and registration system for radiation workers. (author)

  14. 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

  15. Road safety development in Europe: a decade of changes (2001-2010).

    Science.gov (United States)

    Shen, Yongjun; Hermans, Elke; Bao, Qiong; Brijs, Tom; Wets, Geert

    2013-11-01

    To evaluate the road safety development of a country over time, the percentage change in the number of road fatalities is traditionally the main indicator. However, simply considering the reduction in the road fatalities may not correctly reflect the real improvement in road safety because the transport circumstances of a country underlying the road fatalities also change every year. In this study, we present a new way for measuring the road safety performance change over time, which is to use the technique of data envelopment analysis (DEA) and the Malmquist productivity index. In doing so, we can not only focus on the evolution of road safety final outcomes within a given period, but also take the changes of different measures of exposure in the same period into account. In the application, the DEA-based Malmquist productivity index (DEA-MI) is used to measure the extent to which the EU countries have improved their road safety performance over the period 2001-2010. More objective and insightful results are obtained compared to the ones based on the traditional indicator. The results show considerable road safety progress in most of the Member States during these ten years, and the fatality risk rather than the fatality number on Europe's roads has actually been reduced by approximately half. However, the situation differed considerably from country to country. The decomposition of the DEA-MI into 'efficiency change' and 'technical change' further reveals that the bulk of the improvement during the last decade was attained through the adoption of productivity-enhancing new technologies throughout the road transport sector in Europe, rather than through the relatively underperforming countries catching up with those best-performing ones. Copyright © 2013 Elsevier Ltd. All rights reserved.

  16. 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

  17. Nuclear safety and radiation protection report of the Dampierre-en-Burly nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Dampierre-en-Burly nuclear power plant (INB 84 and 85, Loiret, 45 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  18. Nuclear safety and radiation protection report of the Nogent-sur-Seine nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Nogent-sur-Seine nuclear power plant (INB 129 and 130, Aube (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  19. Safety analysis of spent fuel transport and storage casks under extreme impact conditions

    International Nuclear Information System (INIS)

    Wolff, D.; Wieser, G.; Ballheimer, V.; Voelzke, H.; Droste, B.

    2005-01-01

    Full text: Worldwide the security of transport and storage of spent fuel with respect to terrorism threats is a matter of concern. In Germany a spent nuclear fuel management program was developed by the government including a new concept of dry on-site interim storage instead of centralized interim storage. In order to minimize transports of spent fuel casks between nuclear power plants, reprocessing plants and central storage facilities, the operators of NPPs have to erect and to use interim storage facilities for spent nuclear fuel on the site or in the vicinity of nuclear power plants. Up to now, 11 on-site interim storage buildings, one storage tunnel and 4 on-site interim storage areas (preliminary cask storage till the on-site interim storage building is completed) have been licensed at 12 nuclear power plant sites. Inside the interim storage buildings the casks are kept in upright position, whereas at the preliminary interim storage areas horizontal storage of the casks on concrete slabs is used and each cask is covered by concrete elements. Storage buildings and concrete elements are designed only for gamma and neutron radiation shielding reasons and as weather protection. Therefore the security of spent fuel inside a dual purpose transport and storage cask depends on the inherent safety of the cask itself. For nearly three decades BAM has been investigating cask safety under severe accident conditions like drop tests from more than 9 m onto different targets and without impact limiters as well as artificially damaged prototype casks. Since the terror attacks of 11 September 2001 the determination of casks' inherent safety also under extreme impact conditions due to terrorist attacks has been of our increasing interest. With respect to spent fuel storage one of the most critical scenarios of a terrorist attack for a cask is the centric impact of a dynamic load onto the lid-seal-system caused e.g. by direct aircraft crash or its engine as well as by a

  20. Flammable gas deflagration consequence calculations for the tank waste remediation system basis for interim operation

    Energy Technology Data Exchange (ETDEWEB)

    Van Vleet, R.J., Westinghouse Hanford

    1996-08-13

    This paper calculates the radiological dose consequences and the toxic exposures for deflagration accidents at various Tank Waste Remediation System facilities. These will be used in support of the Tank Waste Remediation System Basis for Interim Operation.The attached SD documents the originator`s analysis only. It shall not be used as the final or sole document for effecting changes to an authorization basis or safety basis for a facility or activity.

  1. Supporting Fernald Site Closure with Integrated Health and Safety Plans as Documented Safety Analyses

    International Nuclear Information System (INIS)

    Kohler, S.; Brown, T.; Fisk, P.; Krach, F.; Klein, B.

    2004-01-01

    At the Fernald Closure Project (FCP) near Cincinnati, Ohio, environmental restoration activities are supported by Documented Safety Analyses (DSAs) that combine the required project-specific Health and Safety Plans, Safety Basis Requirements (SBRs), and Process Requirements (PRs) into single Integrated Health and Safety Plans (I-HASPs). These integrated DSAs employ Integrated Safety Management methodology in support of simplified restoration and remediation activities that, so far, have resulted in the decontamination and demolition (D and D) of over 200 structures, including eight major nuclear production plants. There is one of twelve nuclear facilities still remaining (Silos containing uranium ore residues) with its own safety basis documentation. This paper presents the status of the FCP's safety basis documentation program, illustrating that all of the former nuclear facilities and activities have now replaced. Basis of Interim Operations (BIOs) with I-HASPs as their safety basis during the closure process

  2. Retained gas sampler interim safety assessment

    Energy Technology Data Exchange (ETDEWEB)

    Pasamehmetoglu, K.O.; Miller, W.O.; Unal, C.; Fujita, R.K.

    1995-01-13

    This safety assessment addresses the proposed action to install, operate, and remove a Retained Gas Sampler (RGS) in Tank 101-SY at Hanford. Purpose of the RGS is to help characterize the gas species retained in the tank waste; the information will be used to refine models that predict the gas-producing behavior of the waste tank. The RGS will take samples of the tank from top to bottom; these samples will be analyzed for gas constituents. The proposed action is required as part of an evaluation of mitigation concepts for eliminating episodic gas releases that result in high hydrogen concentrations in the tank dome space.

  3. Retained gas sampler interim safety assessment

    International Nuclear Information System (INIS)

    Pasamehmetoglu, K.O.; Miller, W.O.; Unal, C.; Fujita, R.K.

    1995-01-01

    This safety assessment addresses the proposed action to install, operate, and remove a Retained Gas Sampler (RGS) in Tank 101-SY at Hanford. Purpose of the RGS is to help characterize the gas species retained in the tank waste; the information will be used to refine models that predict the gas-producing behavior of the waste tank. The RGS will take samples of the tank from top to bottom; these samples will be analyzed for gas constituents. The proposed action is required as part of an evaluation of mitigation concepts for eliminating episodic gas releases that result in high hydrogen concentrations in the tank dome space

  4. The safety and effectiveness profile of eldecalcitol in a prospective, post-marketing observational study in Japanese patients with osteoporosis: interim report.

    Science.gov (United States)

    Saito, Hitoshi; Kakihata, Hiroyuki; Nishida, Yosuke; Yatomi, Sawako; Nihojima, Shigeru; Kobayashi, Yumiko; Tabata, Hidehiro; Nomura, Makoto

    2017-07-01

    This large-scale post-marketing surveillance study was conducted to assess the safety and effectiveness of eldecalcitol treatment in patients with osteoporosis in a Japanese clinical setting. A total of 3567 patients with osteoporosis were enrolled and received eldecalcitol 0.75 μg/day for 12 months. For this interim report, 3285 patients were eligible for analysis. Mean age was 74.9 ± 8.7 years; 86.8 % (2854/3285) were women. There were 142 reported adverse drug reactions (ADRs) in 129 patients (3.92 % of the total 3285 patients): the most common were hypercalcemia and increased blood calcium (0.88 %), renal impairment (0.27 %), abdominal discomfort (0.24 %), constipation (0.24 %), and pruritus (0.24 %). The incidence of ADRs was 5.10 % in men and 3.74 % in women. Although 10 serious ADRs were reported in 9 patients (0.27 %), no clinically significant safety issues were identified. Incidence of hypercalcemia or increased blood calcium was 8.47 % in patients with renal impairment and only 0.74 % in patients without renal impairment. At last observation, the incidence of new vertebral and nonvertebral fractures was 2.44 % and 1.70 %, respectively. There was a significant increase in bone mineral density at the lumbar spine and distal radius. The bone turnover markers BAP, serum NTX, urinary NTX, and TRACP-5b were suppressed by eldecalcitol treatment in both sexes. In conclusion, consistent with the findings of the phase III pivotal clinical trial, eldecalcitol was shown to have a favorable safety profile and effectiveness in Japanese patients with osteoporosis. However, periodic measurements of serum calcium were required to prevent occurrence of hypercalcemia during eldecalcitol treatment, especially in patients with renal impairment.

  5. Annual report 2007

    International Nuclear Information System (INIS)

    2007-01-01

    The National Agency for the Radioactive Wastes Management (ANDRA), is public company, with an industrial and commercial status. This document presents the activities of the year 2007. It details the organization, the personnel, the world cooperation, the research programs, the safety, the public information and relation, the financial situation and the different sites. (A.L.B.)

  6. Scientific Report 2007

    International Nuclear Information System (INIS)

    2009-09-01

    This annual scientific report gives an concise overview of research and development activities at the Belgian Nuclear Research Centre SCK-CEN in 2007. The report discusses progress and main achievements in the following areas: reactor safety, radioactive waste and clean-up, radiation protection, the BR2 reactor, nuclear research and society, managing nuclear knowledge and fusion research

  7. The probabilistic risk analysis of external hazards of an interim storage for spent nuclear fuel in Olkiluoto

    International Nuclear Information System (INIS)

    Puukka, Tiia

    2014-01-01

    Due to natural disasters occurred in the world and the experiences perceived of the Fukushima nuclear accident, the particular knowledge of the role and influence of external hazards in the safety of interim storage of spent nuclear fuel has been emphasized. For that reason it is substantial that they are included in the probabilistic risk assessment (PRA) of the interim storage facility. This is also required by the Regulatory Guides issued by The Finnish Radiation and Nuclear Safety Authority STUK. To enhance safety culture and nuclear safety in Olkiluoto, The Finnish utility Teollisuuden Voima Oyj has recently completed an analysis of external natural (seismic events are studied as a separate analysis) and unintentional human-induced risks associated with the spent fuel pool cooling and decay heat removal systems as part of the full-scope PRA study for the interim storage of spent fuel (KPA store). The analysis had four goals to achieve: (1) to determine the definition of an initiating event in the context of the KPA store, (2) to identify all potential external hazards and hazard combinations, (3) to perform a qualitative screening analysis based on frequency-strength analysis and detailed plant responses analysis and (4) to model the hazards passed the screening analysis so that model can be used as a risk analysis tool in the risk informed decision making and operating procedures. The assessment carried out included the analysis of operation procedures of decay heat removal, the study of external hazards related initiating events included in the PRA of the OL1 and OL2 nuclear power plants and their dependencies on the initiating events of the KPA store. All external hazards related initiating events were modeled using fault tree linking method. The main result and conclusion of this study was that using the screening analysis, initiating events caused by external hazards that could lead to leakage of the spent fuel pools or that could pose a threat to the

  8. 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

  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. Interim PET Response-adapted Strategy in Untreated Advanced Stage Hodgkin Lymphoma: Results of GOELAMS LH 2007 Phase 2 Multicentric Trial.

    Science.gov (United States)

    Carras, Sylvain; Dubois, Benjamin; Senecal, Delphine; Jais, Jean-Philippe; Peoc'h, Michel; Quittet, Philippe; Foussard, Charles; Bouabdallah, Krimo; Gastinne, Thomas; Jourdan, Eric; Sanhes, Laurence; Ertault, Marjan; Lamy, Thierry; Molina, Lysiane

    2018-03-01

    Patients with advanced stage Hodgkin lymphoma still present unsatisfactory outcomes. The Groupe d'étude des Leucémies Aigues et des Maladies du Sang (GOELAMS) group conducted a prospective multicentric trial (NCT00920153) for advanced stage Hodgkin lymphoma to evaluate a positron emission tomography (PET)-adapted strategy. Patients received an intensive regimen (VABEM [vindesine, doxorubicin, carmustine, etoposide, and methylprednisolone]) in front-line and interim 18F FDG-PET evaluation after 2 courses (PET-2). Patients with negative PET-2 findings received 1 additional course. Patients with positive PET-2 findings underwent early salvage therapy followed by high-dose therapy/autologous stem cell transplantation. Fifty-one patients were included. The final complete remission rate was 88%. With a median follow up of 5.3 years, 5-year event-free survival and overall survival rates were 75.3% and 85.3%, respectively, for the whole cohort. Patients who were PET-2-negative had 5-year event-free survival and overall survival rates of, respectively, 77.8% and 88.2% versus 85.1% and 91.7% for patients who were PET-2-positive. A PET-guided strategy with early salvage therapy and high-dose therapy/autologous stem cell transplantation for patients with interim PET-2-positive findings is safe and feasible and provide similar outcome as patients with a negative PET-2. Copyright © 2018 Elsevier Inc. All rights reserved.

  11. 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.

  12. 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

  13. Nuclear safety and radiation protection report of the Saint-Alban-Saint-Maurice nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Saint-Alban-Saint-Maurice nuclear power plant (INB 119 and 120, Isere (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  14. Research program on regulatory safety - Overview report 2010

    International Nuclear Information System (INIS)

    Mailaender, R

    2011-01-01

    This report for the Swiss Federal Office of Energy (SFOE) summarises the program's main points of interest, work done in the year 2010 and the results obtained. The main highlights of the research program, which was co-ordinated by the Swiss Federal Nuclear Safety Inspectorate ENSI are reported on. Topics reported on include nuclear fuels and materials, the development of a data base on damage and internal incidents, external incidents and human factors. Also, system behaviour and hazardous accident events are reported on, as are radiation protection and waste disposal. Project highlights include the KORA II project, which examined corrosion crack development in austenitic structural materials, the OECD's Halden Reactor Project in the man-technology-organisational area, and work done in the Mont Terri rock research laboratory. Also, national and international co-operation is briefly looked at and work to be done in 2011 is reviewed. A list of current and completed projects completes the report

  15. Working group on VVER safety analysis - report of the 2010 meeting

    International Nuclear Information System (INIS)

    Kliem, S.

    2010-01-01

    The AER Working Group D on WWER reactor safety analysis held its nineteenth meeting in Pisa, Italy, during the period 15-16 April, 2010. The meeting was hosted by the San Piero a Grado Nuclear Research Group of the University of Pisa and was held in conjunction with the second workshop on the OECD/NEA Benchmark for the Kalinin-3 WWER-1000 NPP and the fourth workshop on the OECD Benchmark for Uncertainty Analysis in Best-Estimate Modelling (UAM) for Design, Operation and Safety Analysis of LWRs. Altogether 12 participants attended the meeting of the working group D, 8 from AER member organizations and 4 guests from non-member organization. The co-ordinator of the working group, Mr. S. Kliem, served as chairman of the meeting. The meeting started with a general information exchange about the recent activities in the participating organizations. The given presentations and the discussions can be attributed to the following topics:-Code validation and benchmarking including the calculation of the OECD/NEA Benchmark for the Kalinin-3 WWER-1000 NPP;-Safety analyses and code developments;-Future activities A list of the participants and a list of the handouts distributed at the meeting are attached to the report. The corresponding PDF-files can be obtained from the chairman. (Author)

  16. Establishment of a rationalized safety assurance logic aiming at FBRs with enhanced social acceptance (1). Interim report of CEA/JNC collaboration NWP-5(a) from 1999 to 2001: common view and JNC's contribution

    International Nuclear Information System (INIS)

    Niwa, Hajime; Tobita, Yoshiharu; Kurisaka, Kenichi; Kubo, Shigenobu; Kamiyama, Kenji

    2001-12-01

    This is an interim report describing the progress and the results of the collaborative research works between JNC and CEA on the safety logic in future fast reactors under the title of 'Establishment of a Rationalized Safety Assurance Logic Aiming at FBRs with Enhanced Social Acceptance' from 1999 to 2001. This contains JNC's contribution and common view of both partners. (1) Safety goals are proposed from JNC and CEA. Significant coherency is found such as to keep defense-in depth concept, mitigation measures against core melt are taken into account for containment design, evacuation free' concept is pursued, quantitative safety target is also considered as well as deterministic approach, and improvement of social acceptance is considered from the development stage of the fuel cycle including nuclear power plants. (2) Safety characteristics of each candidate coolant were compared and discussed. Gas-cooled fast reactor is a common interest area. Discussions are focused on: safety design requirements, safety evaluation events list, transient behavior analysis, core catcher designs, and so on. (3) JNC's results include criticality map for predicting CDA behavior and consequences, and CDA analysis results of lead-cooled and gas-cooled fast reactors with SIMMER-III. The collaboration on the action NWP-5a is recognized as being of great importance for the orientation of the innovative design studies. (author)

  17. TWRS safety SSCs: Requirements and characteristics

    International Nuclear Information System (INIS)

    Smith-Fewell, M.A.

    1997-01-01

    Safety Systems, Structures, and Components (SSCs) have been identified from hazard and accident analyses. These analyses were performed to support the Tank Waste Remediation System (TWRS) Final Safety Analysis Report (FSAR) and Basis for Interim Operation (BID). The text identifies and evaluates the SSCs and their supporting SSCs to show that they either prevent the occurrence of the accident or mitigate the consequences of the accident to below the acceptance guidelines. The requirements for the SSCs to fulfill these tasks are described

  18. Safety and efficacy of ipragliflozin in Japanese patients with type 2 diabetes in real-world clinical practice: interim results of the STELLA-LONG TERM post-marketing surveillance study.

    Science.gov (United States)

    Nakamura, Ichiro; Maegawa, Hiroshi; Tobe, Kazuyuki; Tabuchi, Hiromi; Uno, Satoshi

    2018-02-01

    Data regarding the efficacy and safety of sodium-glucose cotransporter 2 inhibitors in the real-world setting in Japan are limited. The STELLA-LONG TERM study is an ongoing 3-year post-marketing surveillance study of ipragliflozin in type 2 diabetes (T2D) patients. Here, we report the interim results (including 3-, 12-, and 24-month data). All Japanese patients with T2D who were first prescribed ipragliflozin between 17 July 2014 and 16 October 2015 at participating centers in Japan were registered in STELLA-LONG TERM. At 3, 12, and 24 months, the safety analysis set comprised 11,053, 5475, and 138 patients, respectively; the efficacy analysis set comprised 8757 patients. Ipragliflozin treatment resulted in statistically significant improvements versus baseline in hemoglobin A1c, fasting plasma glucose concentration, body weight, blood pressure, heart rate, and serum concentrations of low-density lipoprotein cholesterol and triglycerides. The adverse drug reaction incidence rate was 10.71%, the most common reactions being renal and urinary disorders (5.06%), infections and infestations (1.24%), and skin and subcutaneous tissue disorders (1.14%). Ipragliflozin was well tolerated and effective in Japanese patients with T2D; no new safety issues were identified.

  19. THE INTRASTATE CONFLICT AND ITS EFFECTS TO THE INTERNATIONAL SECURITY: SOMALIA BETWEEN 2007 AND 2010

    Directory of Open Access Journals (Sweden)

    ALEJANDRO AMIGO TOSSI

    2017-12-01

    Full Text Available In the current international system there are a number of intra-state situations that prevent the consolidation of a safe global environment. These states are stage of a series of events whose effects go beyond its borders. Somalia represented one of these cases between 2007 and 2010 as a series of internal events generated impacts in its neighbors, the region, and the international system. According to the above, the purpose of this article is “to analyze the cause-effect relationship between phenomena occurring within Somalia and stability of neighboring countries, the Horn of Africa and international security. As a methodology, in a first phase it is described the historical background of Somalia prior to the period analyzed, then it is analyzed internal phenomena that occurred in Somalia relevant from the perspective of international security, and finally, it is stated how these phenomena caused effects on neighboring states, the region’s stability and international security.

  20. Marcoule institute for separation chemistry - ICSM. Scientific report 2007 - 2010

    International Nuclear Information System (INIS)

    2010-01-01

    The mixed research unit 'Institute for Separation Chemistry' was created jointly by CEA, CNRS, University of Montpellier and Ecole Nationale superieure de Chimie de Montpellier has obtained authorisation to start experiments including a few grams of depleted uranium and natural thorium in January 2010. Last takeoff was from our theory group, who started in October 2009. But the unit 'Institut de Chimie separative de Marcoule' existed as a team scattered in several places in France since 2007. At that time, monthly meetings gathered people for full days of open discussion every month, as 'Point ICSM', where colleagues from R/D Departments of the centre of Marcoule composed half of the audience. Scientific activity began in 2007 with progressive joining of ICSM of team leaders, co-workers, technicians and students, today with 38 permanent staff and 29 nonpermanent scientists and students. Most of the staff joined ICSM after or before participating to the European practical summer school in Analytical and separation chemistry, hold yearly for a full week including practical sessions since the first edition 2006 in Montpellier. Resources in Uranium are scarce, if only the 235 isotope is used. Wastes related to nuclear energy production are potentially dangerous. Since fifty years, the chemistry associated to nuclear energy production always followed the principles of green chemistry. Permanent attention in devoted to closing the life-cycle of materials and fuel, minimize wastes and ascertain the acceptability by a society via knowledge of chemistry and physical chemistry involved in the chemistry used for separation. Developing knowledge in order to propose new separation processes is the central aim of the ICSM. Enlarging this central goal to surfaces of materials, sono-chemistry as an example of green chemistry, chemistry and physical chemistry specific to actinides complete this picture. Thus, the ICSM is devoted to chemistry at the service of the nuclear energy of

  1. Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. General Safety Requirements. Pt. 3 (Chinese Edition)

    International Nuclear Information System (INIS)

    2014-01-01

    This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

  2. Radiation protection and safety of radiation sources: International basic safety standards. General safety requirements. Pt. 3 (French Edition)

    International Nuclear Information System (INIS)

    2016-01-01

    This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

  3. Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. General Safety Requirements. Pt. 3 (Arabic Edition)

    International Nuclear Information System (INIS)

    2015-01-01

    This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

  4. 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

  5. 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

  6. Descriptive epidemiology of infectious gastrointestinal illnesses in Sydney, Australia, 2007-2010.

    Science.gov (United States)

    Fletcher, Stephanie; Sibbritt, David; Stark, Damien; Harkness, John; Rawlinson, William; Andresen, David; Van Hal, Sebastian; Merif, Juan; Ellis, John

    2015-01-01

    There is a lack of information about the prevalence of gastrointestinal illnesses in Australia. Current disease surveillance systems capture only a few pathogens. The aim of this study is to describe the epidemiology of infectious gastrointestinal illnesses in Sydney, Australia. A retrospective cross-sectional study of patients with gastrointestinal symptoms who visited tertiary public hospitals in Sydney was conducted between 2007 and 2010. Patients with diarrhoea or loose stools with an enteric pathogen detected were identified. Demographic, clinical and potential risk factor data were collected from their medical records. Measures of association, descriptive and inferential statistics were analysed. In total, 1722 patients were included in this study. Campylobacter (22.0%) and Clostridium difficile (19.2%) were the most frequently detected pathogens. Stratified analysis showed that rotavirus (22.4%), norovirus (20.7%) and adenovirus (18.1%) mainly affected children under 5 years; older children (5-12 years) were frequently infected with Campylobacter spp. (29.8%) and non-typhoid Salmonella spp. (24.4%); infections with C. difficile increased with age.Campylobacter and non-typhoid Salmonella spp. showed increased incidence in summer months (December to February), while rotavirus infections peaked in the cooler months (June to November). This study revealed that gastrointestinal illness remains a major public health issue in Sydney. Improvement of current disease surveillance and prevention and control measures are required. This study emphasizes the importance of laboratory diagnosis of enteric infections and the need for better clinical data collection to improve management of disease risk factors in the community.

  7. Safety analysis of dual purpose metal cask subjected to impulsive loads due to aircraft engine crash

    International Nuclear Information System (INIS)

    Shirai, Koji; Namba, Kosuke; Saegusa, Toshiari

    2009-01-01

    In Japan, the first Interim Storage Facility of spent nuclear fuel away from reactor site is being planned to start its commercial operation around 2010, in use of dual-purpose metal cask in the northern part of Main Japan Island. Business License Examination for safety design approval has started since March, 2007. To demonstrate the more scientific and rational performance of safety regulation activities on each phase for the first license procedure, CREPEI has executed demonstration tests with full scale casks, such as drop tests onto real targets without impact limiters and seismic tests subjected to strong earthquake motions. Moreover, it is important to develop the knowledge for the inherent security of metal casks under extreme mechanical-impact conditions, especially for increasing interest since the terrorist attacks from 11th September 2001. This paper presents dynamic mechanical behavior of the metal cask lid closure system caused by direct aircraft engine crash and describes calculated results (especially, leak tightness based on relative dynamic displacements between metallic seals). Firstly, the local penetration damage of the interim storage facility building by a big passenger aircraft engine research (diameter 2.7m, length 4.3m, weight 4.4ton, impact velocity 90m/s) has been examined. The reduced velocity is calculated by the local damage formula for concrete structure with its thickness of 70cm. The load vs. time function for this reduced velocity (60m/s) is estimated by the impact analysis using Finite Element code LS-DYNA with the full scale engine model onto a hypothetically rigid target. Secondly, as the most critical scenarios for the metal cask, two impact scenarios (horizontal impact hitting the cask and vertical impact onto the lid metallic seal system) are chosen. To consider the geometry of all bolts for two lids, the gasket reaction forces and the inner pressure of the cask cavity, the detailed three dimensional FEM models are developed

  8. Safety Analysis of Dual Purpose Metal Cask Subjected to Impulsive Loads due to Aircraft Engine Crash

    Science.gov (United States)

    Shirai, Koji; Namba, Kosuke; Saegusa, Toshiari

    In Japan, the first Interim Storage Facility of spent nuclear fuel away from reactor site is being planned to start its commercial operation around 2010, in use of dual-purpose metal cask in the northern part of Main Japan Island. Business License Examination for safety design approval has started since March, 2007. To demonstrate the more scientific and rational performance of safety regulation activities on each phase for the first license procedure, CREPEI has executed demonstration tests with full scale casks, such as drop tests onto real targets without impact limiters(1) and seismic tests subjected to strong earthquake motions(2). Moreover, it is important to develop the knowledge for the inherent security of metal casks under extreme mechanical-impact conditions, especially for increasing interest since the terrorist attacks from 11th September 2001(3)-(6). This paper presents dynamic mechanical behavior of the metal cask lid closure system caused by direct aircraft engine crash and describes calculated results (especially, leak tightness based on relative dynamic displacements between metallic seals). Firstly, the local penetration damage of the interim storage facility building by a big passenger aircraft engine crash (diameter 2.7m, length 4.3m, weight 4.4ton, impact velocity 90m/s) has been examined. The reduced velocity is calculated by the local damage formula for concrete structure with its thickness of 70cm. The load vs. time function for this reduced velocity (60m/s) is estimated by the impact analysis using Finite Element code LS-DYNA with the full scale engine model onto a hypothetically rigid target. Secondly, as the most critical scenarios for the metal cask, two impact scenarios (horizontal impact hitting the cask and vertical impact onto the lid metallic seal system) are chosen. To consider the geometry of all bolts for two lids, the gasket reaction forces and the inner pressure of the cask cavity, the detailed three dimensional FEM models are

  9. GROWTH OF THE INTERNATIONAL CRITICALITY SAFETY AND REACTOR PHYSICS EXPERIMENT EVALUATION PROJECTS

    Energy Technology Data Exchange (ETDEWEB)

    J. Blair Briggs; John D. Bess; Jim Gulliford

    2011-09-01

    Since the International Conference on Nuclear Criticality Safety (ICNC) 2007, the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and the International Reactor Physics Experiment Evaluation Project (IRPhEP) have continued to expand their efforts and broaden their scope. Eighteen countries participated on the ICSBEP in 2007. Now, there are 20, with recent contributions from Sweden and Argentina. The IRPhEP has also expanded from eight contributing countries in 2007 to 16 in 2011. Since ICNC 2007, the contents of the 'International Handbook of Evaluated Criticality Safety Benchmark Experiments1' have increased from 442 evaluations (38000 pages), containing benchmark specifications for 3955 critical or subcritical configurations to 516 evaluations (nearly 55000 pages), containing benchmark specifications for 4405 critical or subcritical configurations in the 2010 Edition of the ICSBEP Handbook. The contents of the Handbook have also increased from 21 to 24 criticality-alarm-placement/shielding configurations with multiple dose points for each, and from 20 to 200 configurations categorized as fundamental physics measurements relevant to criticality safety applications. Approximately 25 new evaluations and 150 additional configurations are expected to be added to the 2011 edition of the Handbook. Since ICNC 2007, the contents of the 'International Handbook of Evaluated Reactor Physics Benchmark Experiments2' have increased from 16 different experimental series that were performed at 12 different reactor facilities to 53 experimental series that were performed at 30 different reactor facilities in the 2011 edition of the Handbook. Considerable effort has also been made to improve the functionality of the searchable database, DICE (Database for the International Criticality Benchmark Evaluation Project) and verify the accuracy of the data contained therein. DICE will be discussed in separate papers at ICNC 2011. The status of the

  10. Forest Disturbances and Regrowth Assessment Using ALOS PALSAR Data from 2007 to 2010 in Vietnam, Cambodia and Lao PDR

    Directory of Open Access Journals (Sweden)

    Stéphane Mermoz

    2016-03-01

    Full Text Available This paper aims to develop a new methodology for monitoring forest disturbances and regrowth using ALOS PALSAR data in tropical regions. In the study, forest disturbances and regrowth were assessed between 2007 and 2010 in Vietnam, Cambodia and Lao People’s Democratic Republic. The deforestation rate in Vietnam has been among the highest in the tropics in the last few decades, and those in Cambodia and Lao are increasing rapidly. L-band ALOS PALSAR mosaic data were used for the detection of forest disturbances and regrowth, because L-band SAR intensities are sensitive to forest aboveground biomass loss. The methodology used here combines SAR data processing, which is particularly suited for change detection, forest detection and forest disturbances and regrowth detection using expectation maximization, which is closely related to fuzzy logic. A reliable training and testing database has been derived using AVNIR-2 and Google Earth images for calibration and validation. Efforts were made to apply masking areas that are likely to show different SAR backscatter temporal behaviors from the forests considered in the study, including mangroves, inundated forests, post-flooding or irrigated croplands and water bodies, as well as sloping areas and urban areas. The resulting forest disturbances and regrowth map (25-m resolution indicates disturbance rates of −1.07% in Vietnam, −1.22% in Cambodia and −0.94% in Lao between 2007 and 2010, with corresponding aboveground biomass losses of 60.7 Tg, 59.2 Tg and 83.8 Tg , respectively. It is expected that the method, relying on free of charge data (ALOS and ALOS2 mosaics, can be applied widely in the tropics.

  11. Safety significance of ATR passive safety response attributes

    International Nuclear Information System (INIS)

    Atkinson, S.A.

    1990-01-01

    The Advanced Test Reactor (ATR) at the Idaho National Engineering Laboratory was designed with some passive safety response attributes which contribute to the safety of the facility. The three passive safety attributes being evaluated in the paper are: 1) In-core and in-vessel natural convection cooling, 2) a passive heat sink capability of the ATR primary coolant system (PCS) for the transfer of decay power from the uninsulated piping to the confinement, and 3) gravity feed of emergency coolant makeup. The safety significance of the ATR passive safety response attributes is that the reactor can passively respond to most transients, given a reactor scram, to provide adequate decay power removal and a significant time for operator action should the normal active heat removal systems and their backup systems both fail. The ATR Interim Level 1 Probabilistic Risk Assessment (PRA) models and results were used to evaluate the significance to ATR fuel damage frequency (or probability) of the above three passive response attributes. The results of the evaluation indicate that the first attribute is a major safety characteristic of the ATR. The second attribute has a noticeable but only minor safety significance. The third attribute has no significant influence on the ATR firewater injection system (emergency coolant system)

  12. 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

  13. 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)

  14. 75 FR 18778 - Safety Zone; Ocean City Air Show 2010, Atlantic Ocean, Ocean City, MD

    Science.gov (United States)

    2010-04-13

    ...-AA00 Safety Zone; Ocean City Air Show 2010, Atlantic Ocean, Ocean City, MD AGENCY: Coast Guard, DHS... zone on the Atlantic Ocean in the vicinity of Ocean City, Maryland to support the Ocean City Air Show. This action is intended to restrict vessel traffic movement on the Atlantic Ocean to protect mariners...

  15. 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...

  16. 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

  17. 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

  18. Strategic orientation for research and development 2007-2010

    International Nuclear Information System (INIS)

    2010-01-01

    It is now clearly apparent that the pressure exerted by human activities on the environment, essentially through the added greenhouse effect and various forms of pollution, is irreversibly changing, on the human and global scale, the conditions of life on Earth. Aware of these stakes, international and European institutions are putting into place regulatory frameworks to incite governments to develop policy responses (for example, the United Nations Framework Convention on Climate Change, directives on waste, soils, etc.). The resulting measures are aimed at reducing anthropogenic emissions and at devising lifestyles that are adapted to these new conditions, e.g. preventive policies, policies of adaptation to climate change, new industrial policies based on green technologies. In order to establish the nature, scope and dosage of these policies and actions knowledge and technology are indispensable. To some extent this knowledge is available and already mastered, but in other areas further research, development and demonstration work are required. Any eventual health or environmental risks must also be addressed to ensure competitive deployment of new technologies (second-generation biofuels, CO 2 capture and storage). ADEME's strategic research and development orientation for 2007-2010 focuses on these emerging fields of knowledge and technology, articulated in ten main R and D programmes. Of these ten programmes, seven will develop technical and organisational options to reduce the pressure that humans exert on their surroundings. The three remaining programmes aim to acquire the knowledge needed to conceive and implement effective public policies in the areas of energy management, renewable energy, waste, air quality, soils and noise pollution. Both at the European level, with for example the energy goals set for 2020, and in France, with the commitments now being implemented in the framework of the Grenelle environmental summit, ADEME is centrally placed in a

  19. WHO European Childhood Obesity Surveillance Initiative: body mass index and level of overweight among 6-9-year-old children from school year 2007/2008 to school year 2009/2010.

    LENUS (Irish Health Repository)

    Wijnhoven, Trudy Ma

    2014-01-01

    The World Health Organization (WHO) Regional Office for Europe has established the Childhood Obesity Surveillance Initiative (COSI) to monitor changes in overweight in primary-school children. The aims of this paper are to present the anthropometric results of COSI Round 2 (2009\\/2010) and to explore changes in body mass index (BMI) and overweight among children within and across nine countries from school years 2007\\/2008 to 2009\\/2010.

  20. 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.

  1. The Realization Mechanism of China's Monetary Policy Objectives: 2001-2010

    Institute of Scientific and Technical Information of China (English)

    Wang Guogang

    2013-01-01

    This article explores the realization mechanism for the final and interim targets of China's monetary policy from 2001 to 2010.It finds that the three significant price surges in the ten years were not the results of loose monetary policy While maintaining rapid economic growth,China avoided the inflation linked with excess monetary supply.The introduction of total new lending in the interim targets also showed the maturing of China's monetary policy target system.To improve China's monetary operation,three measures need to te taken:firstly,basing stabilizing monetary policy on the trend of the non-food price index within the CPI;secondly,readjusting the definition of money according the different characteristics of transaction money and reserve money;and thirdly,including yuan exchange rates into the intermediate objectives of monetary policy.

  2. Nuclear safety authority. Strategical planning 2005- 2007

    International Nuclear Information System (INIS)

    Anon.

    2006-01-01

    The Nuclear safety Authority (A.S.N.) provides, in the name of the state, the monitoring of nuclear safety and radiation protection to protect workers, patients, public and environment from the risks in relation with nuclear activities and more broadly with ionizing radiations, it contributes to citizens information in these areas. The ambition of A.S.N. is to carry out a successful, legitimate, credible nuclear monitoring, recognized by citizens and that constitutes an international reference. (N.C.)

  3. Interim performance specifications for conceptual waste-package designs for geologic isolation in salt repositories

    International Nuclear Information System (INIS)

    1983-06-01

    The interim performance specifications and data requirements presented apply to conceptual waste package designs for all waste forms which will be isolated in salt geologic repositories. The waste package performance specifications and data requirements respond to the waste package performance criteria. Subject areas treated include: containment and controlled release, operational period safety, criticality control, identification, and waste package performance testing requirements. This document was generated for use in the development of conceptual waste package designs in salt. It will be revised as additional data, analyses, and regulatory requirements become available

  4. ICSBEP-2007, International Criticality Safety Benchmark Experiment Handbook

    International Nuclear Information System (INIS)

    Blair Briggs, J.

    2007-01-01

    1 - Description: The Critically Safety Benchmark Evaluation Project (CSBEP) was initiated in October of 1992 by the United Sates Department of Energy. The project quickly became an international effort as scientist from other interested countries became involved. The International Criticality Safety Benchmark Evaluation Project (ICSBEP) is now an official activity of the Organization of Economic Cooperation and Development - Nuclear Energy Agency (OECD-NEA). This handbook contains criticality safety benchmark specifications that have been derived from experiments that were performed at various nuclear critical facilities around the world. The benchmark specifications are intended for use by criticality safety engineers to validate calculational techniques used to establish minimum subcritical margins for operations with fissile material. The example calculations presented do not constitute a validation of the codes or cross section data. The work of the ICSBEP is documented as an International Handbook of Evaluated Criticality Safety Benchmark Experiments. Currently, the handbook spans over 42,000 pages and contains 464 evaluations representing 4,092 critical, near-critical, or subcritical configurations and 21 criticality alarm placement/shielding configurations with multiple dose points for each and 46 configurations that have been categorized as fundamental physics measurements that are relevant to criticality safety applications. The handbook is intended for use by criticality safety analysts to perform necessary validations of their calculational techniques and is expected to be a valuable tool for decades to come. The ICSBEP Handbook is available on DVD. You may request a DVD by completing the DVD Request Form on the internet. Access to the Handbook on the Internet requires a password. You may request a password by completing the Password Request Form. The Web address is: http://icsbep.inel.gov/handbook.shtml 2 - Method of solution: Experiments that are found

  5. Efforts toward enhancing seismic safety at Kashiwazaki Kariwa nuclear power station

    Energy Technology Data Exchange (ETDEWEB)

    Yamashita, Kazuhiko

    2010-09-15

    Kashiwazaki-Kariwa Nuclear Power Station, 8212MW, was struck by M6.8 quakes in July 2007. TEPCO has steadily been conducting restoration and post-earthquake equipment integrity assessment, aiming to make it a disaster-resistant power station. 2 units among 7 resumed commercial operation by June 2010. This earthquake has provided a great deal of knowledge and information useful for nuclear safety improvement. It has also served as a valuable reference for the IAEA in developing earthquake-related guidelines. TEPCO would like to share the knowledge and information thereby contributing to improving the safety of nuclear power generation. We will introduce some of our activities.

  6. Areva. 2007 figures economic, social, societal and environmental data; Areva. Chiffres 2007 donnees economiques, sociales, societales et environnementales

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This document presents the 2007 economic, social, societal and environmental data of the Areva Group. Content: 1 - Improvement initiative: Continuous improvement, Innovation; 2 - Financial performance: 2007 results; 3 - Commitment to employees: Stakeholder relations, Health and safety, Radiation protection, Radiological impacts, Technological risks, Workforce, Workforce and training; 4 - Environment: Water, Energy, Gaseous releases, Liquid releases, Conventional waste, Radioactive waste; 5 - Reporting and performance indicators: Reporting methodology, Auditors' report, Social indicators, Environmental indicators.

  7. RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste; Fud-program 2010. Program foer forskning, utveckling och demonstration av metoder foer hantering och slutfoervaring av kaernavfall

    Energy Technology Data Exchange (ETDEWEB)

    2010-09-15

    The RD and D programme 2010 gives an account of SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas - the programme for Low and Intermediate Level Waste (the Loma program) and the Nuclear Fuel Program. The RD and D Programme 2010 consists of five parts: Part I: Overall Plan, Part II: Loma program, Part III: Nuclear Fuel Program, Part IV: Research on analysis of long-term safety, Part V: Social Science Research. The 2007 RD and D programme was focused primarily on technology development to realize the final repository for spent nuclear fuel. The actions described were aimed at increasing awareness of long-term safety and to obtain technical data for application under the Nuclear Activities Act for the final repository for spent fuel and under the Environmental Code of the repository system. Many important results from these efforts are reported in this program. An overall account of the results will be given in the Licensing application in early 2011. The authorities' review of RD and D programme in 2007 and completion of the program called for clarification of plans and programs for the final repository for short-lived radioactive waste, SFR, and the final repository for waste, SFL. This RD and D program describes these plans in a more detailed way

  8. CEA Annual report 2007; CEA rapport annuel 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The CEA, a prominent player in research development and innovation, is active in three main domains: energy, health care and information technology, defense and security. This annual report presents the CEA activities for the year 2007 in these three main areas: science and technology working for nuclear deterrence and global security, the energies without greenhouse effect gases emission against the climatic change, researches in the information sciences and technologies for a better communication and health. The CEA safety, organization, communication and international relations are also presented. (A.L.B.)

  9. Diet quality and history of gestational diabetes mellitus among childbearing women, United States, 2007-2010.

    Science.gov (United States)

    Xiao, Rui S; Simas, Tiffany A Moore; Person, Sharina D; Goldberg, Robert J; Waring, Molly E

    2015-02-26

    Women with a history of gestational diabetes mellitus (GDM) have elevated risk of developing type 2 diabetes. Diet quality plays an important role in the prevention of type 2 diabetes. We compared diet quality among childbearing women with a history of GDM with the diet quality of childbearing women without a history of GDM. We used data from the National Health and Nutrition Examination Survey for 2007 through 2010. We included women without diabetes aged 20 to 44 years whose most recent live infant was born within the previous 10 years and who completed two 24-hour dietary recalls. The Healthy Eating Index (HEI)-2010 estimated overall and component diet quality. Multivariable linear regression models estimated the association between a history of GDM and current diet quality, adjusting for age, education, smoking status, and health risk for diabetes. A history of GDM was reported by 7.7% of women. Compared with women without a history of GDM, women with a history of GDM had, on average, 3.4 points lower overall diet quality (95% confidence interval [CI], -6.6 to -0.2) and 0.9 points lower score for consumption of green vegetables and beans (95% CI, -1.4 to -0.4). Other dietary component scores did not differ by history of GDM. In the United States, women with a history of GDM have lower diet quality compared with women who bore a child and do not have a history of GDM. Improving diet quality may be a strategy for preventing type 2 diabetes among childbearing women.

  10. Nuclear safety and radiation protection report of EdF's Tricastin operational hot base nuclear facilities (BCOT) - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the Tricastin operational hot base facility (INB no. 157, Bollene, Vaucluse (FR)), a nuclear workshop for storage and maintenance and qualification operations on some EdF equipments. Then, the nuclear safety and radiation protection measures taken regarding the facility are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, if some, are reported as well as the effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility is presented and sorted by type of waste, quantities and type of conditioning. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  11. Application of ergonomics principles in underground mines through the Occupational Safety and Health Management System--OSHMS OHSAS 18.001:2007.

    Science.gov (United States)

    de Arruda, Agnaldo Fernando Vieira; Gontijo, Leila Maral

    2012-01-01

    The underground mining activity is regarded as one of the activities that cause most accidents, deaths and illnesses in the world, highlighting the coal mines. This study examined how ergonomics principles can help improve this environment, reduce the number of accidents and occupational diseases, train and empower workers and leaders and humanize the activities of the duty cycle of an underground mine. For this, it was developed a conceptual model of safety managing and health at work for the underground mining through the incorporation of ergonomics principles in the Occupational Safety and Health Management System and OHSAS 18001 (2007). The elaboration of the model was based on analysis of the environments and stages of work in underground mines and the PDCA cycle to ensure continuous improvement.

  12. Nuclear safety and radiation protection report of the Saint-Laurent-des-Eaux nuclear facilities - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Saint-Laurent-des-Eaux nuclear power plant (Saint-Laurent-Nouan (FR)): 2 partially dismantled graphite-gas reactors and a graphite sleeves storage silo (INB 46 and 74), and 2 PWR reactors in operation (INB 100). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  13. 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

  14. Report on activities of Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear installations in the Slovak Republic in 2007. Annual report

    International Nuclear Information System (INIS)

    2007-04-01

    A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2007 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Issuance of authorizations, assessment, supervisory activities and enforcement; (4) Nuclear safety of nuclear installations in the Slovak Republic; (5) Safety of other nuclear installations; (6) Management of radioactive waste; (7) Nuclear materials; (8) Emergency planning and preparedness; (9) International activities; (10) Public communication; (11) Nuclear Regulatory Authority of the Slovak Republic; (12) Abbreviations

  15. National report of the Slovak Republic. Compiled according to the terms of the convention on nuclear safety, June 2010

    International Nuclear Information System (INIS)

    Balaj, J.; Homola, J.; Rovny, J.; Metke, E.; Zemanova, D.; Grebeciova, J.; Turner, M.; Pospisil, M.; Bystricka, S.; Jurina, V.; Rovny, I.; Soltes, L.; Husarova, M.; Petrovic, J.; Fazekasova, H.; Zizkova, D.; Vagac, M.; Maudry, J.; Hacaj, A.; Betak, A.; Barbaric, M.

    2010-06-01

    A brief safety report of the Slovak Republic in 2010 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented.These activities are reported under the headings: (1) Introduction; (2) Nuclear installations in Slovak Republic in terms of the convention; (3) Legislation and regulation; (4) General safety aspects; (5) Safety of nuclear installations in Slovakia; ((6) Annexes; (6.1) List of nuclear installations and technical and economic indicators; (6.2) Selected generally binding legal regulations and safety guidelines in relation to nuclear and radiation safety; (6.3) List of selected national and international documents applicable to safety of nuclear installations; (6.4) Limits for radioactive discharges; (6.5) Team of authors.

  16. Interim criteria for Organic Watch List tanks at the Hanford Site

    International Nuclear Information System (INIS)

    Babad, S.; Turner, D.A.

    1993-09-01

    This document establishes interim criteria for identifying single-shell radioactive waste storage tanks at the Hanford Site that contain organic chemicals mixed with nitrate/nitrite salts in potentially hazardous concentrations. These tanks are designated as ''organic Watch List tanks.'' Watch List tanks are radioactive waste storage tanks that have the potential for release of high-level waste as a result of uncontrolled increases in temperature or pressure. Organic Watch List tanks are those Watch List tanks that contain relatively high concentrations of organic chemicals. Because of the potential for release of high-level waste resulting from uncontrolled increases in temperature or pressure, the organic Watch List tanks (collectively) constitute a Hanford Site radioactive waste storage tank ''safety issue.''

  17. 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.

  18. Driver and vehicle type parameters' contribution to traffic safety in UAE

    OpenAIRE

    Alkheder,Sharaf A.; Sabouni,Reem; El Naggar,Hany; Sabouni,Abdul Rahim

    2013-01-01

    Former traffic safety studies showed clearly that driver or human factor is a major contributor to road accidents. Hence, to better understand the traffic accident nature it's so vital to analyze all characteristics related to drivers involved in these accidents. This article focuses on this aspect through using a dataset representing UAE traffic accidents in the time interval between 2007 and 2010. A major focus was given in this article to analyzing the relation between traffic accidents an...

  19. How to communicate safety? Some reflections from European project studies

    International Nuclear Information System (INIS)

    Richardson, Philip; Galson, Daniel

    2009-12-01

    Attempts to site geological disposal facilities for radioactive waste - and associated public reactions - indicate that communicating safety and demonstrating safety are very different things. The three different approaches to stakeholder engagement undertaken in the context of the PAMINA, ARGONA and CIP projects have provided valuable insights into how risk communication processes and tools can be improved. The approaches used in these projects all involve the participation of interested stakeholders in identifying concerns and issues, which are then examined in a co-operative fashion between stakeholders and developers acting in partnership. Such approaches offer avenues for dialogue and confidence building where such channels were previously not well developed, Full results from the projects will be available in late 2009 for PAMINA and ARGONA and in early 2010 for CIP. The comments and interim insights outlined here will be developed further and incorporated in the overall project outputs, and help inform developing European policy in this area. It is already clear, however, that the approaches used in these projects offer great promise in helping to develop the trust in the institutions and organisations involved that is essential in gaining support and acceptance for the waste management activities now underway across Europe

  20. 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

  1. Electronic flight bag (EFB) : 2010 industry survey

    Science.gov (United States)

    2010-09-01

    This document provides an overview of Electronic Flight Bag (EFB) systems and capabilities, as of June 2010. This document updates and replaces the April 2007 EFB Industry Review (Yeh and Chandra, 2007). As with the previous industry survey, the focu...

  2. Replacement cross-site transfer system project W-058 safety class upgrade summary report

    International Nuclear Information System (INIS)

    Schlosser, R.L.

    1998-01-01

    This report evaluates the design of the replacement cross-site transfer system structures, systems, and components for safety related applications as defined in the Tank Waste Remediation Systems Basis for Interim Operations

  3. 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

  4. Physical protection of shipments of irradiated reactor fuel; Interim guidance. Regulatory report

    International Nuclear Information System (INIS)

    1980-06-01

    During May, 1979, the U.S. Nuclear Regulatory Commission approved for issuance in effective form new interim regulations for strengthening the protection of spent fuel shipments against sabotage and diversion. The new regulations were issued without benefit of public comment, but comments from the public were solicited after the effective date. Based upon the public comments received, the interim regulations were amended and reissued in effective form as a final interim rule in May, 1980. The present document supersedes a previously issued interim guidance document, NUREG-0561 (June, 1979) which accompanied the original rule. This report has been revised to conform to the new interim regulations on the physical protection of shipments of irradiated reactor fuel which are likely to remain in effect until the completion of an ongoing research program concerning the response of spent fuel to certain forms of sabotage, at which time the regulations may be rescinded, modified or made permanent, as appropriate. This report discusses the amended regulations and provides a basis on which licensees can develop an acceptable interim program for the protection of spent fuel shipments

  5. Use of alternative dispute resolution--HHS. Notice of interim policy.

    Science.gov (United States)

    1992-10-27

    The Department has developed an interim policy to address the use of alternative dispute resolution (ADR) as required by the Administrative Dispute Resolution Act (ADR Act), Public Law No. 101-552. This interim policy also responds to the Negotiated Rulemaking Act, Public Law No. 101-648, and relevant elements of the Executive Order on Civil Justice Reform (E.O. 12778). The Department is adopting an interim policy because we need a baseline of experience and knowledge from our own pilot activities and those of other agencies before finalizing a policy.

  6. 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)

  7. 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.

  8. 75 FR 70126 - Safety Zone; Fireworks Displays, Potomac River, National Harbor, MD

    Science.gov (United States)

    2010-11-17

    ... of docket USCG-2010-0776 and are available online by going to http://www.regulations.gov , inserting... Guard received a total of one piece of correspondence in response to the temporary interim rule. No...

  9. Continuation of the summarizing interim report on previous results of the Gorleben site survey as of May 1983

    International Nuclear Information System (INIS)

    1990-04-01

    In addition to results from the 1983 interim report, this report contains, in order to supplement the surface explorations, seismic reflection measurements, hydrogeologic and seismologic investigations, sorption experiments, and studies of glacial development in the site region and of long-term safety of final waste repositories in salt domes. The site's high grade of suitability for becoming a final radioactive waste repository, the legal basis as well as quality assurance are evaluated. (orig.) [de

  10. Safe interim storage of Hanford tank wastes, draft environmental impact statement, Hanford Site, Richland, Washington

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    This Draft EIS is prepared pursuant to the National Environmental Policy Act (NEPA) and the Washington State Environmental Policy Act (SEPA). DOE and Ecology have identified the need to resolve near-term tank safety issues associated with Watchlist tanks as identified pursuant to Public Law (P.L.) 101-510, Section 3137, ``Safety Measures for Waste Tanks at Hanford Nuclear Reservation,`` of the National Defense Authorization Act for Fiscal Year 1991, while continuing to provide safe storage for other Hanford wastes. This would be an interim action pending other actions that could be taken to convert waste to a more stable form based on decisions resulting from the Tank Waste Remediation System (TWRS) EIS. The purpose for this action is to resolve safety issues concerning the generation of unacceptable levels of hydrogen in two Watchlist tanks, 101-SY and 103-SY. Retrieving waste in dilute form from Tanks 101-SY and 103-SY, hydrogen-generating Watchlist double shell tanks (DSTs) in the 200 West Area, and storage in new tanks is the preferred alternative for resolution of the hydrogen safety issues.

  11. Safe interim storage of Hanford tank wastes, draft environmental impact statement, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1994-07-01

    This Draft EIS is prepared pursuant to the National Environmental Policy Act (NEPA) and the Washington State Environmental Policy Act (SEPA). DOE and Ecology have identified the need to resolve near-term tank safety issues associated with Watchlist tanks as identified pursuant to Public Law (P.L.) 101-510, Section 3137, ''Safety Measures for Waste Tanks at Hanford Nuclear Reservation,'' of the National Defense Authorization Act for Fiscal Year 1991, while continuing to provide safe storage for other Hanford wastes. This would be an interim action pending other actions that could be taken to convert waste to a more stable form based on decisions resulting from the Tank Waste Remediation System (TWRS) EIS. The purpose for this action is to resolve safety issues concerning the generation of unacceptable levels of hydrogen in two Watchlist tanks, 101-SY and 103-SY. Retrieving waste in dilute form from Tanks 101-SY and 103-SY, hydrogen-generating Watchlist double shell tanks (DSTs) in the 200 West Area, and storage in new tanks is the preferred alternative for resolution of the hydrogen safety issues

  12. 75 FR 37452 - Science Board Advisory Committee; Notice of Meeting

    Science.gov (United States)

    2010-06-29

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2010-N-0001... Safety and Applied Nutrition (CFSAN). The Science Board will hear about an interim report from the... the committee. Written submissions may be made to the contact person on or before August 9, 2010. Oral...

  13. Wind Energy in Spain. 2007, a year of growth; La energia eolica en Espana. 2007, un ano de crecimiento

    Energy Technology Data Exchange (ETDEWEB)

    Soria, E.

    2008-07-01

    With an increase in annual power of more than 3,500 MW in 2007, at years end Spain had more than 15,000 MW of wind power in operation. This sets a record for wind power installed in a single year. The energy produced by the wind mills during 2007 (more than 27,000 GWh) has led to an unprecedented coverage of the annual electric demand in our country, with a value approaching 10% a year. Wind power will achieve the objectives set in the current Renewable Energy Plan (PER 2005-2010), which calls for 20,155 MW by 2010. With the projects undertaken in the last few years, the Spanish wind power sector has consolidated its leading position in the international arena. (Author) 3 refs.

  14. Descriptive epidemiology of infectious gastrointestinal illnesses in Sydney, Australia, 20072010

    Directory of Open Access Journals (Sweden)

    Stephanie Fletcher

    2015-10-01

    Full Text Available Objective: There is a lack of information about the prevalence of gastrointestinal illnesses in Australia. Current disease surveillance systems capture only a few pathogens. The aim of this study is to describe the epidemiology of infectious gastrointestinal illnesses in Sydney, Australia. Methods: A retrospective cross-sectional study of patients with gastrointestinal symptoms who visited tertiary public hospitals in Sydney was conducted between 2007 and 2010. Patients with diarrhoea or loose stools with an enteric pathogen detected were identified. Demographic, clinical and potential risk factor data were collected from their medical records. Measures of association, descriptive and inferential statistics were analysed. Results: In total, 1722 patients were included in this study. Campylobacter (22.0% and Clostridium difficile (19.2% were the most frequently detected pathogens. Stratified analysis showed that rotavirus (22.4%, norovirus (20.7% and adenovirus (18.1% mainly affected children under 5 years; older children (5–12 years were frequently infected with Campylobacter spp. (29.8% and non-typhoid Salmonella spp. (24.4%; infections with C. difficile increased with age. Campylobacter and non-typhoid Salmonella spp. showed increased incidence in summer months (December to February, while rotavirus infections peaked in the cooler months (June to November. Discussion: This study revealed that gastrointestinal illness remains a major public health issue in Sydney. Improvement of current disease surveillance and prevention and control measures are required. This study emphasizes the importance of laboratory diagnosis of enteric infections and the need for better clinical data collection to improve management of disease risk factors in the community.

  15. Post-mining safety implementations and environmental aspects of abandoned mine sites in Limousin. 2006 status (and perspectives 2007)

    International Nuclear Information System (INIS)

    2007-01-01

    This document summarizes the actions carried out in 2006 at some French abandoned mine sites: 1 - safety implementations and risks abatement in the framework of post-mining actions: coal mines of Ahun (23) and Argentat (19), antimony mines of Biard (87); 2 - remedial actions at the tin/tungsten mine of Puy-les-Vignes (87) and at the gold mine of Chatelet (23); 3 - 2007 post-mining perspectives; 4 - environmental aspects of abandoned mine sites: gold mines of Chatelet (23), Cheni and Bourneix (87), uranium mines of Haute-Vienne (expertise, control of effluents, financial warranties about tailings storage sites maintenance). (J.S.)

  16. Los nacionalismos regionalistas de Brasil y Colombia en la Unión de Estados Suramericanos (UNASUR) (2007- 2011 y 2010-2014)

    OpenAIRE

    Rojas Azula, Maria Camila

    2017-01-01

    El objeto del presente estudio de caso es realizar una comparación entre Brasil y Colombia, en el marco de su mayor protagonismo en la UNASUR, en el caso de Brasil del año 2007 a 2011 y en el caso de Colombia del año 2010 a 2014. Lo anterior se hizo examinando la toma de decisiones de estos países para la ejecución de las grandes propuestas de la UNASUR en materia de seguridad, economía y cultura, teniendo como referencia la categoría de nacionalismo regionalista. Esto con el fin de comparar...

  17. Safety analysis of exothermic reaction hazards associated with the organic liquid layer in tank 241-C-103

    International Nuclear Information System (INIS)

    Postma, A.K.; Bechtold, D.B.; Borsheim, G.L.; Grisby, J.M.; Guthrie, R.L.; Kummerer, M.; Turner, D.A.; Plys, M.G.

    1994-03-01

    Safety hazards associated with the interim storage of a potentially flammable organic liquid in waste Tank C-103 are identified and evaluated. The technical basis for closing the unreviewed safety question (USQ) associated with the floating liquid organic layer in this tank is presented

  18. Safety analysis of exothermic reaction hazards associated with the organic liquid layer in tank 241-C-103

    Energy Technology Data Exchange (ETDEWEB)

    Postma, A.K.; Bechtold, D.B.; Borsheim, G.L.; Grisby, J.M.; Guthrie, R.L.; Kummerer, M.; Turner, D.A. [Westinghouse Hanford Co., Richland, WA (United States); Plys, M.G. [Fauske and Associates, Inc., Burr Ridge, IL (United States)

    1994-03-01

    Safety hazards associated with the interim storage of a potentially flammable organic liquid in waste Tank C-103 are identified and evaluated. The technical basis for closing the unreviewed safety question (USQ) associated with the floating liquid organic layer in this tank is presented.

  19. Prevalence of Depressive Symptoms and Related Factors in Japanese Employees: A Comparative Study between Surveys from 2007 and 2010

    Directory of Open Access Journals (Sweden)

    Masahito Fushimi

    2015-01-01

    Full Text Available Aims. The aim of this study was to examine the prevalence of depressive symptoms and their related factors in Japan. The results were analyzed to identify the relationship between high scores on the CES-D, sociodemographic status, and employment-related variables. Methods. Employees in Akita prefecture completed the Center for Epidemiologic Studies Depression Scale (CES-D during a survey period between November and December 2010. The cutoff point for the CES-D scores was 16 or above (high scorers. Results. Data from 1,476 employees indicated that 44.2% had high scores on the CES-D. Sociodemographic and occupation-related factors associated with a high risk of depression were being female, young age, fewer hours of sleep on weekdays, and working over 8 hours per day, whereas drinking alcohol one to two days per week, albeit only in men, was significantly associated with a low risk of depression. The present results were consistent with the results of a previous survey completed in 2007; however, the present results regarding job categories and smoking behavior were not significantly associated with depression and thus were inconsistent with the 2007 survey data. Conclusions. These results can be useful as benchmark values for the CES-D and might help predict depressive disorders.

  20. 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

  1. Environmental Restoration Disposal Facility (Project W-296) Safety Assessment

    International Nuclear Information System (INIS)

    Armstrong, D.L.

    1994-08-01

    This Safety Assessment is based on information derived from the Conceptual Design Report for the Environmental Restoration Disposal Facility (DOE/RL 1994) and ancillary documentation developed during the conceptual design phase of Project W-296. The Safety Assessment has been prepared to support the Solid Waste Burial Ground Interim Safety Basis document. The purpose of the Safety Assessment is to provide an evaluation of the design to determine if the process, as proposed, will comply with US Department of Energy (DOE) Limits for radioactive and hazardous material exposures and be acceptable from an overall health and safety standpoint. The evaluation considered affects on the worker, onsite personnel, the public, and the environment

  2. Environmental Restoration Disposal Facility (Project W-296) Safety Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Armstrong, D.L.

    1994-08-01

    This Safety Assessment is based on information derived from the Conceptual Design Report for the Environmental Restoration Disposal Facility (DOE/RL 1994) and ancillary documentation developed during the conceptual design phase of Project W-296. The Safety Assessment has been prepared to support the Solid Waste Burial Ground Interim Safety Basis document. The purpose of the Safety Assessment is to provide an evaluation of the design to determine if the process, as proposed, will comply with US Department of Energy (DOE) Limits for radioactive and hazardous material exposures and be acceptable from an overall health and safety standpoint. The evaluation considered affects on the worker, onsite personnel, the public, and the environment.

  3. 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...

  4. 75 FR 69648 - Safety Analysis Requirements for Defining Adequate Protection for the Public and the Workers

    Science.gov (United States)

    2010-11-15

    ... interpretative posture weakens the safety structure the rule is designed to hold firmly in place. 10 CFR Part 830... Basis Documents, and notes that the Safety Basis Approval Authority may prescribe interim controls and... managers ``are expected to carefully evaluate situations that fall short of expectations and only provide...

  5. 75 FR 74022 - Safety Analysis Requirements for Defining Adequate Protection for the Public and the Workers

    Science.gov (United States)

    2010-11-30

    ... posture weakens the safety structure the rule is designed to hold firmly in place. 10 CFR Part 830 imposes... Basis Documents, and notes that the Safety Basis Approval Authority may prescribe interim controls and... managers ``are expected to carefully evaluate situations that fall short of expectations and only provide...

  6. Interim long-term surveillance plan for the Cheney disposal site near, Grand Junction, Colorado

    International Nuclear Information System (INIS)

    1997-08-01

    This interim long-term surveillance plan (LTSP) describes the U.S. Department of Energy's (DOE) long-term care program for the Uranium Mill Tailings Remedial Action (UMTRA) Project Cheney Disposal Site in Mesa County near Grand Junction, Colorado. This LSTP describes the long-term surveillance program the DOE will implement to ensure the Cheney disposal site performs as designed and is cared for in a manner that protects the public health and safety and the environment. Before each disposal site is licensed for custody and long-term care, the Nuclear Regulatory Commission (NRC) requires the DOE to submit such a site-specific LTSP

  7. Safety and effectiveness of 24-week treatment with iguratimod, a new oral disease-modifying antirheumatic drug, for patients with rheumatoid arthritis: interim analysis of a post-marketing surveillance study of 2679 patients in Japan.

    Science.gov (United States)

    Mimori, Tsuneyo; Harigai, Masayoshi; Atsumi, Tatsuya; Fujii, Takao; Kuwana, Masataka; Matsuno, Hiroaki; Momohara, Shigeki; Takei, Syuji; Tamura, Naoto; Takasaki, Yoshinari; Ikeuchi, Satoshi; Kushimoto, Satoru; Koike, Takao

    2017-09-01

    To determine the real-world safety and effectiveness of iguratimod (IGU) for rheumatoid arthritis (RA), a 52-week, Japanese, post-marketing surveillance study was conducted. An interim analysis at week 24 was performed. This study included all RA patients who received IGU following its introduction to the market. All adverse events (AEs) and adverse drug reactions (ADRs) were collected. Effectiveness was evaluated by the change in Disease Activity Score 28-C-reactive protein (DAS28-CRP) from baseline to week 24. Safety was analyzed in 2679 patients. The overall incidences of AEs, ADRs, and serious ADRs were 38.41, 31.65, and 3.21%, respectively; the most commonly reported serious ADRs were pneumonia/bacterial pneumonia, interstitial lung disease, and Pneumocystis jiroveci pneumonia. Concomitant glucocorticoid use and comorbid conditions associated with respiratory disease were identified as risk factors for serious infections. Pulmonary alveolar hemorrhage and increased international normalized ratio of prothrombin time were observed with concomitant use of IGU and warfarin. The DAS28-CRP decreased from baseline to week 24. Although a safety concern was identified with concomitant use of IGU and warfarin, this real-world study showed no other new safety concerns and similar effectiveness to clinical trials. IGU is a new therapeutic option for RA patients.

  8. Proceedings of the 2007 LWR Fuel Performance Meeting / TopFuel 2007 'Zero by 2010'

    International Nuclear Information System (INIS)

    2007-01-01

    ANS, ENS, AESJ and KNS are jointly organizing the 2007 International LWR Fuel Performance Meeting following the successful ENS TopFuel meeting held during 22-26 October, 2006 in Salamaca, Spain. Merging three premier nuclear fuel design and performance meetings: the ANS LWR Fuel Performance Meeting, the ENS TopFuel and Asian Water Reactor Fuel Performance Meeting (WRFPM) created this international meeting. The meeting will be held annually on a tri-annual rotational basis in USA, Asia, and Europe. The technical scope of the meeting includes all aspects of nuclear fuel from fuel rod to core design as well as performance experience in commercial and test reactors. The meeting excludes front end and back end fuel issues, however, it covers all front and/or back issues that impact fuel designs and performance

  9. 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

  10. 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.)

  11. Safety of nuclear installations in the Slovak Republic and activities of the Nuclear Regulatory Authority of the Slovak Republic in 2007

    International Nuclear Information System (INIS)

    Zemanova, D.

    2008-01-01

    Prepared pursuant to the provisions of the Atomic Act, the report provides information on the safety of nuclear installation in the Slovak Republic and activities of the Nuclear Regulatory Authority of the Slovak Republic ( UJD SR). UJD SR executes its activities in the area of legislation, issuance of authorizations and permissions for the siting, construction, operation and decommissioning of nuclear installations, in the area of reviews, assessments and control of nuclear safety of nuclear installations and emergency planning, in the area of records and accountability of nuclear materials, independent public information and in the area of international co-operation focused on peaceful uses of nuclear power. Based on the results of inspection activities and evaluation of safety indicators, UJD SR assessed the operation of nuclear installations in the Slovak Republic as safe and reliable. No significant event that could have a negative impact on the personnel, population or environment occurred in 2007. (orig.)

  12. Research program on nuclear technology and nuclear safety - Overview report 2010; Forschungsprogramm Kerntechnik und Nukleare Sicherheit. Ueberblicksbericht 2010

    Energy Technology Data Exchange (ETDEWEB)

    Cavedon, J.-M.

    2011-07-01

    This comprehensive report for the Swiss Federal Office of Energy (SFOE) summarises the program's main points of interest, work done in the year 2010 and the results obtained. The main highlights of the research program, which was co-ordinated by the Paul Scherrer Institute PSI are presented and discussed. Work done within the STARS program on third-generation nuclear power stations is discussed, as is that carried out on probabilistic safety analyses and human reliability. Analysis of activated materials and MOX nuclear fuel assemblies is discussed. A further project examined aging mechanisms in pressure-loaded components. Processes involved in serious accidents and cooling media loss were also examined. Other fluid-dynamic processes involved, along with other factors, are discussed. Work done on the upgrade of the PROTEUS experimental reactor is discussed, as is that done in connection with PSI's hot laboratory and on radiation-induced creeping in structural materials. Fuel cycles and the disposal of radioactive wastes are looked at and the optimisation of safety in sodium-cooled reactors is discussed. Energy economics aspects and national and international co-operation are briefly looked at and work to be done in 2011 is reviewed. A list of current and completed projects completes the report.

  13. 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.

  14. 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…

  15. 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

  16. 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

  17. 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)

  18. 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.

  19. 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.

  20. Research program on nuclear technology and nuclear safety - Overview report 2010

    International Nuclear Information System (INIS)

    Cavedon, J.-M.

    2011-01-01

    This comprehensive report for the Swiss Federal Office of Energy (SFOE) summarises the program's main points of interest, work done in the year 2010 and the results obtained. The main highlights of the research program, which was co-ordinated by the Paul Scherrer Institute PSI are presented and discussed. Work done within the STARS program on third-generation nuclear power stations is discussed, as is that carried out on probabilistic safety analyses and human reliability. Analysis of activated materials and MOX nuclear fuel assemblies is discussed. A further project examined aging mechanisms in pressure-loaded components. Processes involved in serious accidents and cooling media loss were also examined. Other fluid-dynamic processes involved, along with other factors, are discussed. Work done on the upgrade of the PROTEUS experimental reactor is discussed, as is that done in connection with PSI's hot laboratory and on radiation-induced creeping in structural materials. Fuel cycles and the disposal of radioactive wastes are looked at and the optimisation of safety in sodium-cooled reactors is discussed. Energy economics aspects and national and international co-operation are briefly looked at and work to be done in 2011 is reviewed. A list of current and completed projects completes the report

  1. 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.

  2. Nuclear safety and radiation protection report of the Chooz nuclear facilities - 2010; Rapport sur la surete nucleaire et la radioprotection des installations nucleaires de Chooz - 2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-06-15

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Chooz nuclear power plant (Ardennes (FR)): 2 PWR reactors in operation (Chooz B, INB 139 and 144) and one partially dismantled PWR reactor (Chooz A, INB 163). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  3. Nuclear safety and radiation protection report of the Flamanville nuclear facilities - 2010; Rapport sur la surete nucleaire et la radioprotection des installations nucleaires de Flamanville - 2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-06-15

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Flamanville nuclear power plant (Manche (FR)): 2 PWR reactors in operation (INB 108 and 109), and 1 PWR under construction (Flamanville 3, INB 167). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, water consumption and waste management at Flamanville 3 construction site) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  4. Preparation for tritiated waste management of fusion facilities: Interim storage WAC

    Energy Technology Data Exchange (ETDEWEB)

    Decanis, C., E-mail: christelle.decanis@cea.fr [CEA, DEN, Centre de Cadarache, F-13108 Saint-Paul-lez-Durance (France); Canas, D. [CEA, DEN/DADN, Centre de Saclay, F-91191 Gif-sur-Yvette cedex (France); Derasse, F. [CEA, DEN, Centre de Cadarache, F-13108 Saint-Paul-lez-Durance (France); Pamela, J. [CEA, Agence ITER-France, F-13108 Saint-Paul-lez-Durance (France)

    2016-11-01

    Highlights: • Fusion devices including ITER will generate tritiated waste. • Interim storage is the reference solution offering an answer for all types of tritiated radwaste. • Interim storage is a buffer function in the process management and definition of the waste acceptance criteria (WAC) is a key milestone in the facility development cycle. • Defining WAC is a relevant way to identify ahead of time the studies to be launched and the required actions to converge on a detailed design for example material specific studies, required treatment, interfaces management, modelling and monitoring studies. - Abstract: Considering the high mobility of tritium through the package in which it is contained, the new 50-year storage concepts proposed by the French Alternative Energies and Atomic Energy Commission (CEA) currently provide a solution adapted to the management of waste with tritium concentrations higher than the accepted limits in the disposals. The 50-year intermediate storage corresponds to 4 tritium radioactive periods i.e., a tritium reduction by a factor 16. This paper details the approach implemented to define the waste acceptance criteria (WAC) for an interim storage facility that not only takes into account the specificity of tritium provided by the reference scheme for the management of tritiated waste in France, but also the producers’ needs, the safety analysis of the facility and Andra’s disposal requirements. This will lead to define a set of waste specifications that describe the generic criteria such as acceptable waste forms, general principles and specific issues, e.g. conditioning, radioactive content, tritium content, waste tracking system, and quality control. This approach is also a way to check in advance, during the design phase of the waste treatment chain, how the future waste could be integrated into the overall waste management routes and identify possible key points that need further investigations (design changes, selection

  5. Assessment of safety culture in isfahan hospitals (2010).

    Science.gov (United States)

    Raeisi, Ahmed Reza; Nazari, Maryam; Bahmanziari, Najme

    2013-01-01

    Many internal and external risk factors in health care organizations make safety important and it has caused the management to consider safety in their mission statement. One of the most important tools is to establish the appropriate organizational structure and safety culture. The goal of this research is to inform managers and staff about current safety culture status in hospitals in order to improve the efficiency and effectiveness of health services. This is a descriptive-survey research. The research population was selected hospitals of Isfahan, Iran. Research tool was a questionnaire (Cronbach alpha 0.75). The questionnaire including 93 questions (Likert scale) classified in 12 categories: Demographic questions, Individual attitude, management attitude, Safety Training, Induced stress, pressure and emotional conditions during work, Consultation and participation, Communications, Monitoring and control, work environment, Reporting, safety Rules, procedures and work instructions that distributed among 45 technicians, 208 Nurses and 62 Physicians. All data collected from the serve was analysis with statistical package of social science (SPSS). In this survey Friedman test, Spearman correlation, analysis of variance (ANOVA) and factor analysis have been used for data analyzing. The score of safety culture dimensions was 2.90 for Individual attitude, 3.12 for management attitude, 3.32 for Safety Training, 3.14 for Induced stress, pressure and emotional conditions during work, 3.31 for Consultation and participation, 2.93 for Communications, 3.28 for Monitoring and control, 3.19 for work environment, 3.36 for Reporting, 3.59 safety Rules, procedures and work instructions that Communication and individual attitude were in bad condition. Safety culture among different hospitals: governmental and educational, governmental and non-educational and non-governmental and different functional groups (physicians, nurses, diagnostic) of studied hospitals showed no

  6. Financial Analysis Report: Malaysia Airlines 2007 - 2011

    OpenAIRE

    Gilbert O'Neil Mushure

    2014-01-01

    This work is an analysis of the annual reports of Malaysia Airlines Berhad from 2007 to 2011. Profitability analysis was done on the financial statements of the company from 2007 to 2011. Cash and working capital management analysis were done on the financial statements of 2010 and 2011. It was found that Malaysia Airlines Berhad was constantly suffering from high costs of operations which resulted in consecutive negative gross profit over the years.Net profit remained positive only as a resu...

  7. FY-2007 PNNL Voluntary Protection Program (VPP) Program Evaluation

    International Nuclear Information System (INIS)

    Wright, Patrick A.; Fisher, Julie A.; Goheen, Steven C.; Isern, Nancy G.; Madson, Vernon J.; Meicenheimer, Russell L.; Pugh, Ray; Schneirla, Keri A.; Shockey, Loretta L.; Tinker, Mike R.

    2008-01-01

    This document reports the results of the FY-2007 PNNL VPP Program Evaluation, which is a self-assessment of the operational and programmatic performance of the Laboratory related to worker safety and health. The report was compiled by a team of worker representatives and safety professionals who evaluated the Laboratory's worker safety and health programs on the basis of DOE-VPP criteria. The principle elements of DOE's VPP program are: Management Leadership, Employee Involvement, Worksite Analysis, Hazard Prevention and Control, and Safety and Health Training.

  8. Warm winds from the Pacific caused extensive Arctic sea-ice melt in summer 2007

    Energy Technology Data Exchange (ETDEWEB)

    Graversen, Rune G.; Drijfhout, Sybren [Royal Netherlands Meteorological Institute, De Bilt (Netherlands); Mauritsen, Thorsten [Max-Planck Institute for Meteorology, Hamburg (Germany); Tjernstroem, Michael; Maartensson, Sebastian [Stockholm University, Department of Meteorology, Stockholm (Sweden)

    2011-06-15

    During summer 2007 the Arctic sea-ice shrank to the lowest extent ever observed. The role of the atmospheric energy transport in this extreme melt event is explored using the state-of-the-art ERA-Interim reanalysis data. We find that in summer 2007 there was an anomalous atmospheric flow of warm and humid air into the region that suffered severe melt. This anomaly was larger than during any other year in the data (1989-2008). Convergence of the atmospheric energy transport over this area led to positive anomalies of the downward longwave radiation and turbulent fluxes. In the region that experienced unusual ice melt, the net anomaly of the surface fluxes provided enough extra energy to melt roughly one meter of ice during the melting season. When the ocean successively became ice-free, the surface-albedo decreased causing additional absorption of shortwave radiation, despite the fact that the downwelling solar radiation was smaller than average. We argue that the positive anomalies of net downward longwave radiation and turbulent fluxes played a key role in initiating the 2007 extreme ice melt, whereas the shortwave-radiation changes acted as an amplifying feedback mechanism in response to the melt. (orig.)

  9. Spatial analysis and temporal trends of porcine reproductive and respiratory syndrome in Denmark from 2007 to 2010 based on laboratory submission data

    DEFF Research Database (Denmark)

    Lopes Antunes, Ana Carolina; Hisham Beshara Halasa, Tariq; Lauritsen, Klara Tølbøl

    2015-01-01

    of PRRSV in Danish swine herds from 2007 to 2010, based on type-specific serological tests from the PRRS surveillance and control program in Denmark using the results stored in the information management system at the National Veterinary Institute, Technical University of Denmark (DTU Vet). The average......Porcine reproductive and respiratory syndrome (PRRS) has been a cause for great concern to the Danish pig industry since it was first diagnosed in 1992. The causative agent of PRRS is an RNA virus which is divided into different genotypes. The clinical signs, as well as its morbidity and mortality...

  10. Fiscal 1976 Sunshine Project research report. Interim report (hydrogen energy); 1976 nendo chukan hokokushoshu. Suiso energy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1976-11-01

    This report summarizes the Sunshine Project research interim reports on hydrogen energy of every organizations. The report includes research items, laboratories, institutes and enterprises concerned, research targets, research plans, and progress conditions. The research items are as follows. (1) Hydrogen production technology (electrolysis, high- temperature high-pressure water electrolysis, 4 kinds of thermochemical techniques, direct thermolysis). (2) Hydrogen transport and storage technology (2 kinds of solidification techniques). (3) Hydrogen use technology (combustion technology, fuel cell, solid electrolyte fuel cell, fuel cell power system, hydrogen fuel engine). (4) Hydrogen safety measures technology (disaster preventive technology for gaseous and liquid hydrogen, preventing materials from embrittlement due to hydrogen, hydrogen refining, transport and storage systems, their safety technology). (5) Hydrogen energy system (hydrogen energy system, hydrogen use subsystems, peripheral technologies). (NEDO)

  11. Environmental Modelling for Radiation Safety (EMRAS) — A Summary Report of the Results of the EMRAS Programme (2003-2007)

    DEFF Research Database (Denmark)

    Arkhipov, A.; Charnock, T.W.; Gaschak, S.

    This publication provides a detailed overview of the results and achievements of the IAEA programme called EMRAS (Environmental Modelling for Radiation Safety), which ran from 2003 to 2007. The activities of the various working groups focused on the compilation of a handbook of parameter values...... for the prediction of radionuclide transfer in temperate environments, on the test and comparison of models to assess the transfer of tritium and 14C to biota and humans, on the validation of models for dose reconstruction due to 131I after the Chernobyl accident, on modelling the transfer of radionuclides...

  12. Development of Comprehensive Nuclear Safety Regulation Plan for 2007-2011

    International Nuclear Information System (INIS)

    Choi, Young Sung; Kim, Woong Sik; Park, Dong Keuk; Kim, Ho Ki

    2006-01-01

    The Article 8-2 of Atomic Energy Act requires the government to establish Atomic Energy Promotion Plan every five years. It sets out national nuclear energy policies in a systematic and consistent way. The plan presents the goals and basic directions of national nuclear energy policies on the basis of current status and prospects. Both areas of utilization and safety management of nuclear energy are included and various projects and schedules are delineated based on the national policy directions. The safety management area in this plan deals with the overall safety and regulation policy. Its detail projects and schedule should be developed in separate plans by responsible ministries under the mediation of the MOST. As a regulatory authority, MOST is responsible for safety management area and its technical support organization, KINS has developed Comprehensive Nuclear Safety Regulation Plan as an implementation plan of safety area. This paper presents the development process and specific projects contained in the Comprehensive Nuclear Safety Regulation Plan which is under development now

  13. 75 FR 36288 - Amended Safety Zone and Regulated Navigation Area, Chicago Sanitary and Ship Canal, Romeoville, IL

    Science.gov (United States)

    2010-06-25

    ...The Coast Guard is revising its safety zone and Regulated Navigation Area (RNA) on the Chicago Sanitary and Ship Canal (CSSC) near Romeoville, IL. This revised temporary interim rule reduces the areas covered by the safety zone and RNA, and places additional restrictions on vessels that may transit the RNA.

  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. Assessment of Safety Culture in Isfahan Hospitals (2010)

    OpenAIRE

    Raeisi, Ahmed Reza; Nazari, Maryam; Bahmanziari, Najme

    2013-01-01

    Introduction: Many internal and external risk factors in health care organizations make safety important and it has caused the management to consider safety in their mission statement. One of the most important tools is to establish the appropriate organizational structure and safety culture. The goal: The goal of this research is to inform managers and staff about current safety culture status in hospitals in order to improve the efficiency and effectiveness of health services. Methods: This...

  16. 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

  17. Prevalencia de sobrepeso y obesidad en niños menores de cinco años en el Perú 2007-2010 Prevalence of overwight and obesity among children under five years in Peru 2007-2010

    Directory of Open Access Journals (Sweden)

    Jaime Pajuelo-Ramírez

    2011-06-01

    Full Text Available Objetivos. Estimar la prevalencia de sobrepeso y obesidad en niños menores de cinco años en el Perú durante los años 2007 a 2010 y describir su distribución de acuerdo con ámbitos geográficos, niveles de pobreza, edad, educación de la madre, lactancia materna exclusiva, sexo y peso al nacer. Materiales y métodos: Se realizó una encuesta continua (transversal repetida, por muestreo aleatorio multietápico, del universo de niños menores de cinco años y gestantes residentes en el Perú, dividido en cinco ámbitos geográficos. Las mediciones antropométricas se efectuaron de acuerdo con metodología estándar internacional. Resultados: Se estudiaron 3 669 niños menores de cinco años, de ellos 50,3% fueron niños. En Lima Metropolitana residían 680; 763 en el resto de costa; 719 en la sierra urbana, 699 en la sierra rural y 808 en la selva. La prevalencia nacional de sobrepeso y obesidad es 6,9%, con la mayor prevalencia, en Lima Metropolitana (10,1% y con menor prevalencia en la selva (2,6%. Mediante regresión logística múltiple se identificaron como factores asociados a la edad, el sexo, el ámbito geográfico y el peso al nacer. Conclusiones: Los factores asociados con sobrepeso y obesidad son la procedencia de Lima Metropolitana, el primer año de vida, el sexo masculino y el peso al nacer mayor a 2,5 kg.Objectives: To estimate the prevalence of overweight and obesity in children under five in Peru in the years 2007-2010 and to describe according to geographical areas, poverty levels, maternal education, breastfeeding, child age, sex and birth weight. Materials and methods: continuous (repeated cross-sectional multistage, random sampling survey from the universe of children under five-years and pregnant women living in Peru, divided into five geographical areas. Results: Out of 3,669 children, 50.3% were males (Lima N=680, Remaining Coast N=763, Urban Sierra N=719, Rural Sierra N=699, Jungle N=808 having their weight and height

  18. Nuclear safety and radiation protection report of the basic nuclear facilities of the Tricastin nuclear power plant - 2010

    International Nuclear Information System (INIS)

    2011-06-01

    This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Tricastin nuclear power plant (INB 87 and 88, Saint-Paul-Trois-Chateaux, Drome (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

  19. Comparisons of the tropospheric specific humidity from GPS radio occultations with ERA-Interim, NASA MERRA, and AIRS data

    Science.gov (United States)

    Vergados, Panagiotis; Mannucci, Anthony J.; Ao, Chi O.; Verkhoglyadova, Olga; Iijima, Byron

    2018-03-01

    We construct a 9-year data record (2007-2015) of the tropospheric specific humidity using Global Positioning System radio occultation (GPS RO) observations from the Constellation Observing System for Meteorology, Ionosphere, and Climate (COSMIC) mission. This record covers the ±40° latitude belt and includes estimates of the zonally averaged monthly mean specific humidity from 700 up to 400 hPa. It includes three major climate zones: (a) the deep tropics (±15°), (b) the trade winds belts (±15-30°), and (c) the subtropics (±30-40°). We find that the RO observations agree very well with the European Centre for Medium-Range Weather Forecasts Re-Analysis Interim (ERA-Interim), the Modern-Era Retrospective Analysis for Research and Applications (MERRA), and the Atmospheric Infrared Sounder (AIRS) by capturing similar magnitudes and patterns of variability in the monthly zonal mean specific humidity and interannual anomaly over annual and interannual timescales. The JPL and UCAR specific humidity climatologies differ by less than 15 % (depending on location and pressure level), primarily due to differences in the retrieved refractivity. In the middle-to-upper troposphere, in all climate zones, JPL is the wettest of all data sets, AIRS is the driest of all data sets, and UCAR, ERA-Interim, and MERRA are in very good agreement, lying between the JPL and AIRS climatologies. In the lower-to-middle troposphere, we present a complex behavior of discrepancies, and we speculate that this might be due to convection and entrainment. Conclusively, the RO observations could potentially be used as a climate variable, but more thorough analysis is required to assess the structural uncertainty between centers and its origin.

  20. Time-dependent crack growth in Alloy 718: An interim assessment

    International Nuclear Information System (INIS)

    James, L.A.

    1982-08-01

    Previous results on the time-dependent nature of fatigue-crack propagation (FCP) in Alloy 718 at elevated temperatures were reviewed. Additional experiments were conducted to further define certain aspects of the time-dependent crack growth behavior. it was found that loading waveform influenced FCP behavior, with tensile hold-times producing higher growth rates than continuous cycling at the same frequency. Crack growth rates under hold-time conditions tended to increase with decreasing grain size. Finally, experiments were conducted which tended to cast some doubt upon the ability of linear-elastic fracture mechanics (LEFM) techniques to characterize cracking behavior in this alloy under hold-time conditions. However, since a superior correlating parameter has not yet been proven, it is suggested that LEFM methods be used in the interim with appropriate safety factors to account for the potential errors. 34 refs., 10 figs., 4 tabs

  1. FY-2007 PNNL Voluntary Protection Program (VPP) Program Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Wright, Patrick A.; Fisher, Julie A.; Goheen, Steven C.; Isern, Nancy G.; Madson, Vernon J.; Meicenheimer, Russell L.; Pugh, Ray; Schneirla, Keri A.; Shockey, Loretta L.; Tinker, Mike R.

    2008-08-15

    This document reports the results of the FY-2007 PNNL VPP Program Evaluation, which is a self-assessment of the operational and programmatic performance of the Laboratory related to worker safety and health. The report was compiled by a team of worker representatives and safety professionals who evaluated the Laboratory's worker safety and health programs on the basis of DOE-VPP criteria. The principle elements of DOE's VPP program are: Management Leadership, Employee Involvement, Worksite Analysis, Hazard Prevention and Control, and Safety and Health Training.

  2. 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.

  3. RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

    International Nuclear Information System (INIS)

    2010-09-01

    The RD and D programme 2010 gives an account of SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas - the programme for Low and Intermediate Level Waste (the Loma program) and the Nuclear Fuel Program. The RD and D Programme 2010 consists of five parts: Part I: Overall Plan, Part II: Loma program, Part III: Nuclear Fuel Program, Part IV: Research on analysis of long-term safety, Part V: Social Science Research. The 2007 RD and D programme was focused primarily on technology development to realize the final repository for spent nuclear fuel. The actions described were aimed at increasing awareness of long-term safety and to obtain technical data for application under the Nuclear Activities Act for the final repository for spent fuel and under the Environmental Code of the repository system. Many important results from these efforts are reported in this program. An overall account of the results will be given in the Licensing application in early 2011. The authorities' review of RD and D programme in 2007 and completion of the program called for clarification of plans and programs for the final repository for short-lived radioactive waste, SFR, and the final repository for waste, SFL. This RD and D program describes these plans in a more detailed way

  4. RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

    International Nuclear Information System (INIS)

    2010-09-01

    RDandD Programme 2010 presents SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas: the programme for low- and intermediate-level waste (the LILW Programme) and the Nuclear Fuel Programme. Operation of the existing facilities takes place within the Operational Process. RDandD Programme 2010 consists of five parts: Part I Overall plan of action Part II The LILW Programme Part III The Nuclear Fuel Programme Part IV Research for assessment of long-term safety Part V Social science research RDandD Programme 2007 was mainly focused on development of technology to realize the final repository for spent nuclear fuel. The efforts described were aimed at gaining a greater knowledge of long-term safety and compiling technical supporting documentation for applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. Many important results from these efforts are reported in this programme. The integrated account of the results will be presented in applications submitted in early 2011. The regulatory review of RDandD Programme 2007 and its supplement called for clarifications of plans and programmes for the final repository for short-lived radioactive waste, SFR, and the final repository for long-lived waste, SFL. This RDandD Programme describes these plans more clearly

  5. RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    2010-09-15

    RDandD Programme 2010 presents SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas: the programme for low- and intermediate-level waste (the LILW Programme) and the Nuclear Fuel Programme. Operation of the existing facilities takes place within the Operational Process. RDandD Programme 2010 consists of five parts: Part I Overall plan of action Part II The LILW Programme Part III The Nuclear Fuel Programme Part IV Research for assessment of long-term safety Part V Social science research RDandD Programme 2007 was mainly focused on development of technology to realize the final repository for spent nuclear fuel. The efforts described were aimed at gaining a greater knowledge of long-term safety and compiling technical supporting documentation for applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. Many important results from these efforts are reported in this programme. The integrated account of the results will be presented in applications submitted in early 2011. The regulatory review of RDandD Programme 2007 and its supplement called for clarifications of plans and programmes for the final repository for short-lived radioactive waste, SFR, and the final repository for long-lived waste, SFL. This RDandD Programme describes these plans more clearly

  6. RDandD Programme 2010. Programme for research, development and demonstration of methods for the management and disposal of nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    2010-09-15

    RDandD Programme 2010 presents SKB's plans for research, development and demonstration during the period 2011-2016. SKB's activities are divided into two main areas: the programme for low- and intermediate-level waste (the LILW Programme) and the Nuclear Fuel Programme. Operation of the existing facilities takes place within the Operational Process. RDandD Programme 2010 consists of five parts: Part I Overall plan of action Part II The LILW Programme Part III The Nuclear Fuel Programme Part IV Research for assessment of long-term safety Part V Social science research RDandD Programme 2007 was mainly focused on development of technology to realize the final repository for spent nuclear fuel. The efforts described were aimed at gaining a greater knowledge of long-term safety and compiling technical supporting documentation for applications under the Nuclear Activities Act for the final repository for spent nuclear fuel and under the Environmental Code for the final repository system. Many important results from these efforts are reported in this programme. The integrated account of the results will be presented in applications submitted in early 2011. The regulatory review of RDandD Programme 2007 and its supplement called for clarifications of plans and programmes for the final repository for short-lived radioactive waste, SFR, and the final repository for long-lived waste, SFL. This RDandD Programme describes these plans more clearly

  7. Annual Report 1998 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-05-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland.

  8. Annual Report 1998 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    International Nuclear Information System (INIS)

    1999-05-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland

  9. Annual Report 1999 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    International Nuclear Information System (INIS)

    2000-08-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland

  10. Efficacy and Safety of Rituximab in Children with Refractory Nephrotic Syndrome; A Multicenter Clinical Trial

    Directory of Open Access Journals (Sweden)

    Yo Han Ahn

    2014-06-01

    Conclusions: In this interim analysis of clinical trial to evaluate the efficacy and safety of RTX in children with refractory NS, RTX treatment for refractory NS was safe and effective, especially in patients with DNS.

  11. Annual Report 1999 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-08-15

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland.

  12. Local health department food safety and sanitation expenditures and reductions in enteric disease, 2000-2010.

    Science.gov (United States)

    Bekemeier, Betty; Yip, Michelle Pui-Yan; Dunbar, Matthew D; Whitman, Greg; Kwan-Gett, Tao

    2015-04-01

    In collaboration with Public Health Practice-Based Research Networks, we investigated relationships between local health department (LHD) food safety and sanitation expenditures and reported enteric disease rates. We combined annual infection rates for the common notifiable enteric diseases with uniquely detailed, LHD-level food safety and sanitation annual expenditure data obtained from Washington and New York state health departments. We used a multivariate panel time-series design to examine ecologic relationships between 2000-2010 local food safety and sanitation expenditures and enteric diseases. Our study population consisted of 72 LHDs (mostly serving county-level jurisdictions) in Washington and New York. While controlling for other factors, we found significant associations between higher LHD food and sanitation spending and a lower incidence of salmonellosis in Washington and a lower incidence of cryptosporidiosis in New York. Local public health expenditures on food and sanitation services are important because of their association with certain health indicators. Our study supports the need for program-specific LHD service-related data to measure the cost, performance, and outcomes of prevention efforts to inform practice and policymaking.

  13. Areva. 2007 figures economic, social, societal and environmental data

    International Nuclear Information System (INIS)

    2007-01-01

    This document presents the 2007 economic, social, societal and environmental data of the Areva Group. Content: 1 - Improvement initiative: Continuous improvement, Innovation; 2 - Financial performance: 2007 results; 3 - Commitment to employees: Stakeholder relations, Health and safety, Radiation protection, Radiological impacts, Technological risks, Workforce, Workforce and training; 4 - Environment: Water, Energy, Gaseous releases, Liquid releases, Conventional waste, Radioactive waste; 5 - Reporting and performance indicators: Reporting methodology, Auditors' report, Social indicators, Environmental indicators

  14. 14 CFR 1274.934 - Safety.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 5 2010-01-01 2010-01-01 false Safety. 1274.934 Section 1274.934... FIRMS Other Provisions and Special Conditions § 1274.934 Safety. Safety July 2002 NASA's safety priority... shall act responsibly in matters of safety and shall take all reasonable safety measures in performing...

  15. SERO SURVEI STATUS KEKEBALAN CAMPAK HASIL RISKESDAS 2007

    Directory of Open Access Journals (Sweden)

    Noer Endah Pracoyo

    2013-07-01

    Full Text Available Abstrak Penyakit campak merupakan penyakit menular yang sering terjadi pada anak-anak. Kasus campak di Indonesia masih sering terjadi meskipun telah berhasil direduksi. Jumlah kasus tahun 1990 sebanyak 180.000 kasus menjadi sekitar 20.000 kasus pada tahun 2010. Upaya mengurangi terjadinya penularan penyakit campak telah dilakukan pemberian imunisasi secara rutin pada balita dan booster pada anak usia sekolah dasar. Telah dilakukan analisis hubungan antara kekebalan campak pada individu terpilih dengan faktor risiko penyebab terjadinya kekebalan campak pada  Riskesdas 2007. Tujuannya untuk menilai hubungan antara fator risiko dengan kekebalan campak pada individu terpilih hasil Riskesdas 2007. Metode mengikuti kerangka Riskesdas 2007. Analisis data dengan menggunakan perangkat lunak stata 9.00. Hasilnya risiko non protektif campak sebesar 68% pada individu yang berusia 10-14 tahun, dan risiko non protektif  sebesar 73% pada golongan ekonomi menengah ke bawah yakni pada golongan ekonomi tingkat 3 . Kata kunci: titer antibodi campak, individu terpilih, riskesdas 2007 Abstract Measles is a contagious disease that often occurs in children. Cases of measles in Indonesia are still common despite successfully reduced. The number of cases of 180,000 cases in 1990 to approximately 20,000 cases in 2010. Efforts to reduce disease transmission measles immunization has been carried out on a regular basis. In the toddler and booster at primary school age children. Analyzed the relationship  measles antibody titers in individuals with risk factors for selected causes immunity against measles in Riskesdas 2007. The aim is to assess the relationship between risk factor immunity against measles in selected individual in Riskesdas 2007. The method follows the framework of Riskesdas 2007. Analysis of the data using the software stata 9:00. The result, risk non protective measles by 68% in individuals aged 10-14 years, and non-protective risk by 73% in the middle

  16. Bone mineral density across a range of physical activity volumes: NHANES 2007-2010.

    Science.gov (United States)

    Whitfield, Geoffrey P; Kohrt, Wendy M; Pettee Gabriel, Kelley K; Rahbar, Mohammad H; Kohl, Harold W

    2015-02-01

    The association between aerobic physical activity volume and bone mineral density (BMD) is not completely understood. The purpose of this study was to clarify the association between BMD and aerobic activity across a broad range of activity volumes, particularly volumes between those recommended in the 2008 Physical Activity Guidelines for Americans and those of trained endurance athletes. Data from the 2007-2010 National Health and Nutrition Examination Survey were used to quantify the association between reported physical activity and BMD at the lumbar spine and proximal femur across the entire range of activity volumes reported by US adults. Participants were categorized into multiples of the minimum guideline-recommended volume based on reported moderate- and vigorous-intensity leisure activity. Lumbar and proximal femur BMD were assessed with dual-energy x-ray absorptiometry. Among women, multivariable-adjusted linear regression analyses revealed no significant differences in lumbar BMD across activity categories, whereas proximal femur BMD was significantly higher among those who exceeded the guidelines by 2-4 times than those who reported no activity. Among men, multivariable-adjusted BMD at both sites neared its highest values among those who exceeded the guidelines by at least 4 times and was not progressively higher with additional activity. Logistic regression estimating the odds of low BMD generally echoed the linear regression results. The association between physical activity volume and BMD is complex. Among women, exceeding guidelines by 2-4 times may be important for maximizing BMD at the proximal femur, whereas among men, exceeding guidelines by ≥4 times may be beneficial for lumbar and proximal femur BMD.

  17. 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

  18. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2007

    Energy Technology Data Exchange (ETDEWEB)

    West Valley Environmental Services LLC (WVES) and URS - Washington Division

    2008-12-17

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2007. The report summarizes the calendar year (CY) 2007 environmental protection program at the WVDP. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment.

  19. West Valley Demonstration Project Annual Site Environmental Report Calendar Year 2007

    International Nuclear Information System (INIS)

    2008-01-01

    Annual Site Environmental Report for the West Valley Demonstration Project (WVDP) for Calendar Year 2007. The report summarizes the calendar year (CY) 2007 environmental protection program at the WVDP. Monitoring and surveillance of the facilities used by the DOE are conducted to verify protection of public health and safety and the environment

  20. Surveillance of Salmonella enteritidis in layer houses: a retrospective comparison of the Food and Drug Administration's egg safety rule (2010-2011) and the California Egg Quality Assurance Program (2007-2011).

    Science.gov (United States)

    Pitesky, Maurice; Charlton, Bruce; Bland, Mark; Rolfe, Dan

    2013-03-01

    Between July 2007 and December 2011, 2660 environmental drag swab samples were collected in total from California layer flocks on behalf of the California Egg Quality Assurance Program (CEQAP), the egg safety rule (21 CFR Parts 16 and 118) of the Food and Drug Administration (FDA), or both. The samples were processed by the California Animal Health and Food Safety Lab, and positive or negative results for Salmonella enterica serovar Enteritidis (SE) were recorded. This study retrospectively compares the differences between the FDA and CEQAP programs with respect to their SE environmental sampling surveillance results. To accomplish this comparison, two different CEQAP (new and old) data sets representing different SE environmental surveillance approaches in the life of the flock were compared against each other and against the FDA's SE environmental testing plan. Significant differences were noted between the CEQAP and FDA programs with respect to the prevalence of SE in the farm environment. Analyses of the prevalence of SE at different stages in the flock's life cycle (chick papers, preproduction, midproduction, postmolt, and premarket) found the highest prevalence of SE in premarket (11.9%), followed by postmolt (3.5%) and midproduction (3.4%), and there was a tie between chick papers and preproduction (2.1%). To assess the main effects of the presence of SE in the farm environment, backwards binary logistic regression was used. Of six independent variables examined (age of flock, year, season, owner, CEQAP membership, and analysis of pooled samples vs. individual swabs), only age of flock, owner, and year were determined to be significant factors in the final model. Although CEQAP membership and pooling vs. individuals swabs were not included in the final model, Pearson chi-square tests did show significantly higher odds of SE for non-CEQAP member farms and higher odds of SE in pooled samples vs. individual swabs.

  1. Annual Site Environmental Report, 2007(ASER)

    International Nuclear Information System (INIS)

    Sabba, D

    2008-01-01

    This report provides information about environmental programs during the calendar year (CY) of 2007 at the Stanford Linear Accelerator Center (SLAC), Menlo Park, California. Activities that span the calendar year, i.e., stormwater monitoring covering the winter season of 2007/2008 (October 2007 through May 2008), are also included. Production of an annual site environmental report (ASER) is a requirement established by the United States Department of Energy (DOE) for all management and operating (M and O) contractors throughout the DOE complex. SLAC is a federally-funded research and development center with Stanford University as the M and O contractor. Under Executive Order (EO) 13423 and DOE Order 450.1, 'Environmental Protection Program', SLAC effectively implemented and integrated the key elements of an Environmental Management System (EMS) to achieve the site's integrated safety and environmental management system goals. For normal daily activities, SLAC managers and supervisors are responsible for ensuring that policies and procedures are understood and followed so that: (1) Worker safety and health are protected; (2) The environment is protected; and (3) Compliance is ensured. Throughout 2007, SLAC focused on development and implementation of SLAC management systems to ensure continual improvement. These systems provided a structured framework for SLAC to implement 'greening of the government' initiatives such as EO 13148. Overall, management systems at SLAC are effective, supporting compliance with all relevant statutory and regulatory requirements. SLAC continues to demonstrate significant progress in implementing and integrating EMS into day-to-day operations at SLAC. The annual management review and ranking of environmental aspects were completed this year by SLAC's EMS Steering Committee, the Environmental Safety Committee (ESC) and thirteen objectives and targets were established for 2007. For each objective and target, a work plan, or Environmental

  2. Annual Site Environmental Report, 2007(ASER)

    Energy Technology Data Exchange (ETDEWEB)

    Sabba, D

    2008-10-07

    This report provides information about environmental programs during the calendar year (CY) of 2007 at the Stanford Linear Accelerator Center (SLAC), Menlo Park, California. Activities that span the calendar year, i.e., stormwater monitoring covering the winter season of 2007/2008 (October 2007 through May 2008), are also included. Production of an annual site environmental report (ASER) is a requirement established by the United States Department of Energy (DOE) for all management and operating (M&O) contractors throughout the DOE complex. SLAC is a federally-funded research and development center with Stanford University as the M&O contractor. Under Executive Order (EO) 13423 and DOE Order 450.1, 'Environmental Protection Program', SLAC effectively implemented and integrated the key elements of an Environmental Management System (EMS) to achieve the site's integrated safety and environmental management system goals. For normal daily activities, SLAC managers and supervisors are responsible for ensuring that policies and procedures are understood and followed so that: (1) Worker safety and health are protected; (2) The environment is protected; and (3) Compliance is ensured. Throughout 2007, SLAC focused on development and implementation of SLAC management systems to ensure continual improvement. These systems provided a structured framework for SLAC to implement 'greening of the government' initiatives such as EO 13148. Overall, management systems at SLAC are effective, supporting compliance with all relevant statutory and regulatory requirements. SLAC continues to demonstrate significant progress in implementing and integrating EMS into day-to-day operations at SLAC. The annual management review and ranking of environmental aspects were completed this year by SLAC's EMS Steering Committee, the Environmental Safety Committee (ESC) and thirteen objectives and targets were established for 2007. For each objective and target, a work

  3. Safety significance of ATR [Advanced Test Reactor] passive safety response attributes

    International Nuclear Information System (INIS)

    Atkinson, S.A.

    1989-01-01

    The Advanced Test Reactor (ATR) at the Idaho National Engineering Laboratory was designed with some passive safety response attributes which contribute to the safety posture of the facility. The three passive safety attributes being evaluated in the paper are: (1) In-core and in-vessel natural convection cooling, (2) a passive heat sink capability of the ATR primary coolant system (PCS) for the transfer of decay power from the uninsulated piping to the confinement, and (3) gravity feed of emergency coolant makeup. The safety significance of the ATR passive safety response attributes is that the reactor can passively respond for most transients, given a reactor scram, to provide adequate decay power removal and a significant time for operator action should the normal active heat removal systems and their backup systems both fail. The ATR Interim Level 1 Probabilistic Risk Assessment (PRA) model ands results were used to evaluate the significance to ATR fuel damage frequency (or probability) of the above three passive response attributes. The results of the evaluation indicate that the first attribute is a major safety characteristic of the ATR. The second attribute has a noticeable but only minor safety significance. The third attribute has no significant influence on the ATR Level 1 PRA because of the diversity and redundancy of the ATR firewater injection system (emergency coolant system). 8 refs., 4 figs., 1 tab

  4. In vitro evaluation of the marginal integrity of CAD/CAM interim crowns.

    Science.gov (United States)

    Kelvin Khng, Kwang Yong; Ettinger, Ronald L; Armstrong, Steven R; Lindquist, Terry; Gratton, David G; Qian, Fang

    2016-05-01

    The accuracy of interim crowns made with computer-aided design and computer-aided manufacturing (CAD/CAM) systems has not been well investigated. The purpose of this in vitro study was to evaluate the marginal integrity of interim crowns made by CAD/CAM compared with that of conventional polymethylmethacrylate (PMMA) crowns. A dentoform mandibular left second premolar was prepared for a ceramic crown and scanned for the fabrication of 60 stereolithical resin dies, half of which were scanned to fabricate 15 Telio CAD-CEREC and 15 Paradigm MZ100-E4D-E4D crowns. Fifteen Caulk and 15 Jet interim crowns were made on the remaining resin dies. All crowns were cemented with Tempgrip under a 17.8-N load, thermocycled for 1000 cycles, placed in 0.5% acid fuschin for 24 hours, and embedded in epoxy resin before sectioning from the mid-buccal to mid-lingual surface. The marginal discrepancy was measured using a traveling microscope, and dye penetration was measured as a percentage of the overall length under the crown. The mean vertical marginal discrepancy of the conventionally made interim crowns was greater than for the CAD/CAM crowns (P=.006), while no difference was found for the horizontal component (P=.276). The mean vertical marginal discrepancy at the facial surface of the Caulk crowns was significantly greater than that of the other 3 types of interim crowns (Pmargin, the mean horizontal component of the Telio crowns was significantly larger than that of the other 3 types, with no difference at the lingual margins (P=.150). The mean percentage dye penetration for the Paradigm MZ100-E4D crowns was significantly greater and for Jet crowns significantly smaller than for the other 3 crowns (Pmarginal discrepancies of the Jet interim crowns at the facial surface and with the horizontal marginal discrepancies of the Caulk interim crowns at the lingual surface (Pmarginal discrepancy was found with the interim crowns fabricated by CAD/CAM as compared with PMMA crowns

  5. Federal Employees Health Benefits Program and Federal Employees Dental and Vision Insurance Program: eligibility for Pathway Programs participants. Interim final rule with request for comments.

    Science.gov (United States)

    2014-01-06

    The U.S. Office of Personnel Management (OPM) is issuing an interim final regulation to update the Federal Employees Health Benefits Program (FEHBP) and the Federal Employees Dental and Vision Insurance Program (FEDVIP) regulations to reflect updated election opportunities for participants in the Pathways Programs. The Pathways Programs were created by Executive Order (E.O.) 13562, signed by the President on December 27, 2010, and are designed to enable the Federal Government to compete effectively for students and recent graduates by improving its recruitment efforts through internships and similar programs with Federal agencies. This interim final rule furthers these recruitment and retention efforts by providing health insurance, as well as dental and vision benefits, to eligible program participants and their families.

  6. 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

  7. 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.

  8. Results of forest monitoring on Olkiluoto island in 2010

    International Nuclear Information System (INIS)

    Aro, L.; Huhta, A.-P.; Hoekkae, H.; Lindroos, A.-J.; Rautio, P.; Helmisaari, H.-S.

    2011-11-01

    Forest investigations carried out on Olkiluoto aim to monitor the state of the forest ecosystems, quantify Olkiluoto-specific processes taking place in the forests producing input data for the safety assessment of spent nuclear fuel disposal, and follow possible changes in the forest condition resulting from the intensive construction activities currently being carried out in the area. The forest investigations form a part of the monitoring programme being carried out on Olkiluoto Island under the management of Posiva Oy. This report focuses on activities performed on bulk deposition and forest intensive monitoring plots (MRK and FIP plots) in 2010. In general, the deposition levels in 2010 in the open area and in stand throughfall were quite comparable to those in earlier years, although sulphur and calcium depositions were somewhat higher in the open area than in earlier years (2004-2008). The soil solution quality in 2010 was also quite comparable to that in earlier years. The NH 4 -N and NO 3 -N concentrations were low at all depths in the mineral soil of the FIP plots 4, 10 and 11. Instead, nitrate concentrations were high in the soil solution on FIP14. There appeared to be a clear overall increase in sulphate concentrations with increasing depth on FIP4 and FIP10. Chloride concentrations in the soil solution were extremely high at all depths on all FIP plots throughout the monitoring period; it is clear that there is a considerable input of NaCl in the deposition derived from the sea. The concentrations of heavy metals (Cd, Cr, Ni, Pb) in the soil solution at all depths at Olkiluoto during 2004-2010 continued in many cases to be close to or below the limit of quantification. In 2010 the monthly level of transpiration in the Scots pine dominated stand was smaller in May and bigger in July than during previous years (2007-2009). Monthly transpiration in the Norway spruce dominated stand was clearly lower in 2010 than in 2007-2009, and there is a decreasing

  9. Results of forest monitoring on Olkiluoto island in 2010

    Energy Technology Data Exchange (ETDEWEB)

    Aro, L.; Huhta, A.-P.; Hoekkae, H.; Lindroos, A.-J.; Rautio, P. [Finnish Forest Research Institute, Vantaa (Finland); Helmisaari, H.-S. [Helsinki Univ. (Finland)

    2011-11-15

    Forest investigations carried out on Olkiluoto aim to monitor the state of the forest ecosystems, quantify Olkiluoto-specific processes taking place in the forests producing input data for the safety assessment of spent nuclear fuel disposal, and follow possible changes in the forest condition resulting from the intensive construction activities currently being carried out in the area. The forest investigations form a part of the monitoring programme being carried out on Olkiluoto Island under the management of Posiva Oy. This report focuses on activities performed on bulk deposition and forest intensive monitoring plots (MRK and FIP plots) in 2010. In general, the deposition levels in 2010 in the open area and in stand throughfall were quite comparable to those in earlier years, although sulphur and calcium depositions were somewhat higher in the open area than in earlier years (2004-2008). The soil solution quality in 2010 was also quite comparable to that in earlier years. The NH{sub 4}-N and NO{sub 3}-N concentrations were low at all depths in the mineral soil of the FIP plots 4, 10 and 11. Instead, nitrate concentrations were high in the soil solution on FIP14. There appeared to be a clear overall increase in sulphate concentrations with increasing depth on FIP4 and FIP10. Chloride concentrations in the soil solution were extremely high at all depths on all FIP plots throughout the monitoring period; it is clear that there is a considerable input of NaCl in the deposition derived from the sea. The concentrations of heavy metals (Cd, Cr, Ni, Pb) in the soil solution at all depths at Olkiluoto during 2004-2010 continued in many cases to be close to or below the limit of quantification. In 2010 the monthly level of transpiration in the Scots pine dominated stand was smaller in May and bigger in July than during previous years (2007-2009). Monthly transpiration in the Norway spruce dominated stand was clearly lower in 2010 than in 2007-2009, and there is a

  10. 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

  11. Early interim 18F-FDG PET in Hodgkin's lymphoma: evaluation on 304 patients

    International Nuclear Information System (INIS)

    Zinzani, Pier Luigi; Stefoni, Vittorio; Broccoli, Alessandro; Argnani, Lisa; Baccarani, Michele; Rigacci, Luigi; Puccini, Benedetta; Castagnoli, Antonio; Vaggelli, Luca; Zanoni, Lucia; Fanti, Stefano

    2012-01-01

    The use of early (interim) PET restaging during first-line therapy of Hodgkin's lymphoma (HL) in clinical practice has considerably increased because of its ability to provide early recognition of treatment failure allowing patients to be transferred to more intensive treatment regimens. Between June 1997 and June 2009, 304 patients with newly diagnosed HL (147 early stage and 157 advanced stage) were treated with the ABVD regimen at two Italian institutions. Patients underwent PET staging and restaging at baseline, after two cycles of therapy and at the end of the treatment. Of the 304 patients, 53 showed a positive interim PET scan and of these only 13 (24.5%) achieved continuous complete remission (CCR), whereas 251 patients showed a negative PET scan and of these 231 (92%) achieved CCR. Comparison between interim PET-positive and interim PET-negative patients indicated a significant association between PET findings and 9-year progression-free survival and 9-year overall survival, with a median follow-up of 31 months. Among the early-stage patients, 19 had a positive interim PET scan and only 4 (21%) achieved CCR; among the 128 patients with a negative interim PET scan, 122 (97.6%) achieved CCR. Among the advanced-stage patients, 34 showed a persistently positive PET scan with only 9 (26.4%) achieving CCR, whereas 123 showed a negative interim PET scan with 109 (88.6%) achieving CCR. Our results demonstrate the role of an early PET scan as a significant step forward in the management of patients with early-stage or advanced-stage HL. (orig.)

  12. Proceedings of the 9th annual meeting of Japanese Society of Radiation Safety Management 2010 Hiroshima

    International Nuclear Information System (INIS)

    2010-12-01

    This is the entitled program and proceedings held from December 1st through 3rd of 2010. The sessions including poster, invited/special speeches etc. are exposure reduction and dose level evaluation, shielding design, radioactive waste handling and its effective use, radiation measurement, safety control of radiation source, radioactive waste management (aerosol, liquid), education on radiation, molecular imaging, image analysis, radioactivity in environment, contamination inspection. (J.P.N)

  13. Mastering Microsoft Exchange Server 2010

    CERN Document Server

    McBee, Jim

    2010-01-01

    A top-selling guide to Exchange Server-now fully updated for Exchange Server 2010. Keep your Microsoft messaging system up to date and protected with the very newest version, Exchange Server 2010, and this comprehensive guide. Whether you're upgrading from Exchange Server 2007 SP1 or earlier, installing for the first time, or migrating from another system, this step-by-step guide provides the hands-on instruction, practical application, and real-world advice you need.: Explains Microsoft Exchange Server 2010, the latest release of Microsoft's messaging system that protects against spam and vir

  14. Fit of interim crowns fabricated using photopolymer-jetting 3D printing.

    Science.gov (United States)

    Mai, Hang-Nga; Lee, Kyu-Bok; Lee, Du-Hyeong

    2017-08-01

    The fit of interim crowns fabricated using 3-dimensional (3D) printing is unknown. The purpose of this in vitro study was to evaluate the fit of interim crowns fabricated using photopolymer-jetting 3D printing and to compare it with that of milling and compression molding methods. Twelve study models were fabricated by making an impression of a metal master model of the mandibular first molar. On each study model, interim crowns (N=36) were fabricated using compression molding (molding group, n=12), milling (milling group, n=12), and 3D polymer-jetting methods. The crowns were prepared as follows: molding group, overimpression technique; milling group, a 5-axis dental milling machine; and polymer-jetting group using a 3D printer. The fit of interim crowns was evaluated in the proximal, marginal, internal axial, and internal occlusal regions by using the image-superimposition and silicone-replica techniques. The Mann-Whitney U test and Kruskal-Wallis tests were used to compare the results among groups (α=.05). Compared with the molding group, the milling and polymer-jetting groups showed more accurate results in the proximal and marginal regions (P3D printing significantly enhanced the fit of interim crowns, particularly in the occlusal region. Copyright © 2016 Editorial Council for the Journal of Prosthetic Dentistry. Published by Elsevier Inc. All rights reserved.

  15. Health Effects of Unemployment in Denmark, Norway and Sweden 2007-2010: Differing Economic Conditions, Differing Results?

    Science.gov (United States)

    Heggebø, Kristian

    2016-07-01

    This article investigates short-term health effects of unemployment for individuals in Denmark, Norway, and Sweden during an economic downturn (2007-2010) that hit the Scandinavian countries with diverging strength. The longitudinal part of the European Union Statistics on Income and Living Conditions (EU-SILC) data material is analyzed, and results from generalized least squares estimation indicate that Denmark is the only Scandinavian country in which health status deteriorated among the unemployed. The individual-level (and calendar year) fixed-effect results confirm the negative relationship between unemployment and health status in Denmark. This result is robust across different subsamples, model specifications, and changes in both the dependent and independent variable. Health status deteriorated especially among women and people in prime working age (30-59 years). There is, however, only scant evidence of short-term health effects among the recently unemployed in Norway and Sweden. The empirical findings are discussed in light of: (1) the adequacy of the unemployment insurance system, (2) the likelihood of re-employment for the displaced worker, and (3) selection patterns into and out of employment in the years preceding and during the economic downturn. © The Author(s) 2016.

  16. Genotypic and PFGE/MLVA analyses of Vibrio cholerae O1: geographical spread and temporal changes during the 2007-2010 cholera outbreaks in Thailand.

    Directory of Open Access Journals (Sweden)

    Kazuhisa Okada

    Full Text Available BACKGROUND: Vibrio cholerae O1 El Tor dominated the seventh cholera pandemic which occurred in the 1960s. For two decades, variants of V. cholerae O1 El Tor that produce classical cholera toxin have emerged and spread globally, replacing the prototypic El Tor biotype. This study aims to characterize V. cholerae O1 isolates from outbreaks in Thailand with special reference to genotypic variations over time. METHODS/FINDINGS: A total of 343 isolates of V. cholerae O1 from cholera outbreaks from 2007 to 2010 were investigated, and 99.4% were found to carry the classical cholera toxin B subunit (ctxB and El Tor rstR genes. Pulsed-field gel electrophoresis (PFGE differentiated the isolates into 10 distinct pulsotypes, clustered into two major groups, A and B, with an overall similarity of 88%. Ribotyping, multiple-locus variable-number tandem-repeat analysis (MLVA, and PCR to detect Vibrio seventh pandemic island II (VSP-II related genes of randomly selected isolates from each pulsotype corresponded to the results obtained by PFGE. Epidemiological investigations revealed that MLVA type 2 was strongly associated with a cholera outbreak in northeastern Thailand in 2007, while MLVA type 7 dominated the outbreaks of the southern Gulf areas in 2009 and MLVA type 4 dominated the outbreaks of the central Gulf areas during 2009-2010. Only MLVA type 16 isolates were found in a Thai-Myanmar border area in 2010, whereas those of MLVA types 26, 39, and 41 predominated this border area in 2008. Type 39 then disappeared 1-2 years later as MLVA type 41 became prevalent. Type 41 was also found to infect an outbreak area. CONCLUSIONS: MLVA provided a high-throughput genetic typing tool for understanding the in-depth epidemiology of cholera outbreaks. Our epidemiological surveys suggest that some clones of V. cholerae O1 with similar but distinctive genetic traits circulate in outbreak sites, while others disappear over time.

  17. Trends in the aggressiveness of end-of-life care for Korean pediatric cancer patients who died in 2007-2010.

    Directory of Open Access Journals (Sweden)

    June Dong Park

    Full Text Available In light of the Korean Supreme Court's 2009 ruling favoring a patient's right to die with dignity, we evaluated trends in aggressive care in a cohort of pediatric cancer patients. Methods We conducted a population-based retrospective study that used administrative data for patients who died in 2007-2010 among the 5,203 pediatric cancer patients registered at the Korean Cancer Central Registry (KCCR during 2007-2009.In the time period covered, 696 patients died. The proportion who had received chemotherapy in the last 30 days of life decreased from 58.1% to 28.9% (P<0.001, those who received new chemotherapy in the same time period decreased from 55.2% to 15.1% (P<0.001, and those who received treatment in the last 2 weeks of life decreased from 51.4% to 21.7% (P<0.001. In the last 30 days of life, the proportion of patients whose hospital admission period was over 14 days increased from 70.5% to 82.5% (P = 0.03, the proportion who received cardiopulmonary resuscitation decreased from 28.6% to 9.6% (P<0.001, and we found no statistically significant trends in the proportion of emergency department visits, intensive care unit admissions, or mechanical ventilation.In this study, in contrast with earlier ones, the aggressiveness of end-of-life care of Korean pediatric cancer patients decreased dramatically.

  18. Annual report 1996 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland. figs., tabs., refs.

  19. Annual report 1996 concerning the nuclear safety and radiological protection in the Swiss nuclear installations

    International Nuclear Information System (INIS)

    1997-05-01

    The report presents detailed information about the nuclear safety and radiological protection in the Swiss nuclear power plants, the central interim storage at Wuerenlingen, the Paul Scherrer Institute (PSI) and other nuclear installations in Switzerland. figs., tabs., refs

  20. Pesticide residues determination in Polish organic crops in 2007-2010 applying gas chromatography-tandem quadrupole mass spectrometry.

    Science.gov (United States)

    Walorczyk, Stanisław; Drożdżyński, Dariusz; Kowalska, Jolanta; Remlein-Starosta, Dorota; Ziółkowski, Andrzej; Przewoźniak, Monika; Gnusowski, Bogusław

    2013-08-15

    A sensitive, accurate and reliable multiresidue method based on the application of gas chromatography-tandem quadrupole mass spectrometry (GC-QqQ-MS/MS) has been established for screening, identification and quantification of a large number of pesticide residues in produce. The method was accredited in compliance with PN-EN ISO/IEC 17025:2005 standard and it was operated under flexible scope as PB-11 method. The flexible scope of accreditation allowed for minor modifications and extension of the analytical scope while using the same analytical technique. During the years 2007-2010, the method was used for the purpose of verification of organic crop production by multiresidue analysis for the presence of pesticides. A total of 528 samples of differing matrices such as fruits, vegetables, cereals, plant leaves and other green parts were analysed, of which 4.4% samples contained pesticide residues above the threshold value of 0.01 mg/kg. A total of 20 different pesticide residues were determined in the samples. Copyright © 2013 Elsevier Ltd. All rights reserved.

  1. 49 CFR 385.317 - Will a safety audit result in a safety fitness determination by the FMCSA?

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 5 2010-10-01 2010-10-01 false Will a safety audit result in a safety fitness... SAFETY REGULATIONS SAFETY FITNESS PROCEDURES New Entrant Safety Assurance Program § 385.317 Will a safety audit result in a safety fitness determination by the FMCSA? A safety audit will not result in a safety...

  2. 14 CFR 1260.37 - Safety.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 5 2010-01-01 2010-01-01 false Safety. 1260.37 Section 1260.37 Aeronautics... Provisions § 1260.37 Safety. Safety October 2000 (a) The Recipient shall act responsibly in matters of safety and shall take all reasonable safety measures in performing under this grant or cooperative agreement...

  3. Methodology for Safety Assessment Applied to Predisposal Waste Management. Report of the Results of the International Project on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) 2004–2010)

    International Nuclear Information System (INIS)

    2015-12-01

    Report of the Results of the International Project on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) (2004–2010) The IAEA’s progamme on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) focused on approaches and mechanisms for application of safety assessment methodologies for the predisposal management of radioactive waste. The initial outcome of the SADRWMS Project was achieved through the development of flowcharts, which have since been incorporated into IAEA Safety Standards Series No. GSG-3, Safety Case and Safety Assessment for Predisposal Management of Radioactive Waste. In 2005, an initial specification was developed for the Safety Assessment Framework (SAFRAN) software tool to apply the SADRWMS flowcharts. In 2008, an in-depth application of the SAFRAN tool and the SADRWMS methodology was carried out on the predisposal management facilities of the Thailand Institute of Nuclear Technology Radioactive Waste Management Centre (TINT Facility). This publication summarizes the content and outcomes of the SADRWMS programme. The Chairman’s Report of the SADRWMS Project and the Report of the TINT test case are provided on the CD-ROM which accompanies this report

  4. 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.…

  5. Replicating the EnhanceFitness physical activity program in Hawai`i's multicultural population, 2007-2010.

    Science.gov (United States)

    Tomioka, Michiyo; Sugihara, Naomi; Braun, Kathryn L

    2012-01-01

    Despite evidence of the benefits of regular physical activity, many older adults are not physically active. Health professionals are challenged to replicate evidence-based programs to address low levels of physical activity among members of their communities. EnhanceFitness is an evidence-based group exercise program developed in Seattle to increase the strength, flexibility, and balance of older adults. Hawai`i's Healthy Aging Partnership supported the rural island of Kaua`i to select, adapt, implement, and evaluate EnhanceFitness to increase physical activity among older adult residents (75% Asian/Pacific Islander [API]). Evaluation measures of the replication of EnhanceFitness included fidelity of EnhanceFitness delivery and participants' attendance, satisfaction with the program, confidence to exercise regularly, and pre-post fitness check measures of physical performance (chair stands, arm curls, and the up-and-go test). Between July 2007 and December 2010, 223 Kaua`i residents enrolled in EnhanceFitness; 178 (80%) participated at least 4 months and completed the 4-month fitness checks. EnhanceFitness classes were offered with a high degree of fidelity, and both API and white participants significantly improved their physical performance (chair stands, t = -11.06, P program and instructors and high confidence to continue to exercise regularly. EnhanceFitness is replicable in Hawai`i and increased physical performance among API and white older adults. This case study outlines a replication process that other communities can follow.

  6. Annual Dynamics of Forest Areas in South America during 2007-2010 at 50-m Spatial Resolution

    Science.gov (United States)

    Qin, Y.; Xiao, X.; Dong, J.; Zhou, Y.; Wang, J.; Doughty, R.; Chen, Y.; Zou, Z.; Moore, B., III

    2017-12-01

    The user community has an urgent need for high accuracy tropical forest distribution and spatio-temporal changes since tropical forests are facing defragmentation and persistent clouds. In this study, we selected South America as a hotspot and presented a robust approach to map annual forests during 2007-2010 based on the coupled greenness-relevant MOD13Q1 NDVI and structure/biomass-relevant ALOS PALSAR time series data. We analyzed the consistency and uncertainty among eight major forest maps at continental, country, and pixel scales. The 50-m PALSAR/MODIS forest area in South America was about 8.63×106 km2 in 2010. Large differences in total forest area (8.2×106 km2-12.7×106 km2) existed among these forest products. Forest products generated under a similar forest definition had similar or even larger variation than those generated under differing forest definitions. One needs to consider leaf area index as an adjusting factor and use much higher threshold values in the VCF datasets to estimate forest cover. Analyses of PALSAR/MODIS forest maps showed a relatively small and equivalent rate of loss (3.2×104 km2 year-1) in net forest cover to that of FAO FRA (3.3×104 km2 year-1). PALSAR/MODIS forest maps showed that more and more deforestation occurred in the intact forest areas. The rate of forest loss (1.95×105 km2 year-1) was higher than that of Global Forest Watch (0.81×105 km2 year-1). Caution should be used when using the different forest maps to analyze forest loss and make policies regarding forest ecosystem services and biodiversity conservation.

  7. Management report 2007 CNEN - Brazilian Nuclear Energy Commission; Relatorio de gestao 2007 CNEN - Comissao Nacional de Energia Nuclear

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This document reports the general activity management of the Comissao Nacional de Energia Nuclear - CNEN - Brazil during the year of 2007, involving the CNEN role in the public policy execution, the Brazilian program of nuclear activities in the areas of nuclear safety, research and development, radiopharmaceutical production, teaching, administration in general and miscellaneous.

  8. Czech interim spent fuel storage facility: operation experience, inspections and future plans

    International Nuclear Information System (INIS)

    Fajman, V.; Bartak, L.; Coufal, J.; Brzobohaty, K.; Kuba, S.

    1999-01-01

    The paper describes the situation in the spent fuel management in the Czech Republic. The interim Spent Fuel Storage Facility (ISFSF) at Dukovany, which was commissioned in January 1997 and is using dual transport and storage CASTOR - 440/84 casks, is briefly described. The authors deal with their experience in operating and inspecting the ISFSF Dukovany. The structure of the basic safety document 'Limits and Conditions of Normal Operation' is also mentioned, including the experience of the performance. The inspection activities focused on permanent checking of the leak tightness of the CASTOR 440/84 casks, the maximum cask temperature and inspections monitoring both the neutron and gamma dose rate as well as the surface contamination. The results of the inspections are mentioned in the presentation as well. The operator's experience with re-opening partly loaded and already dried CASTOR-440/84 cask, after its transport from NPP Jaslovske Bohunice to the NPP Dukovany is also described. The paper introduces briefly the concept of future spent fuel storage both from the NPP Dukovany and the NPP Temelin, as prepared by the CEZ. The preparatory work for the Central Interim Spent Nuclear Fuel Storage Facility (CISFSF) in the Czech Republic and the information concerning the planned storage technology for this facility is discussed in the paper as well. The authors describe the site selection process and the preparatory steps concerning new spent fuel facility construction including the Environmental Impact Assessment studies. (author)

  9. Interim performance criteria for photovoltaic energy systems. [Glossary included

    Energy Technology Data Exchange (ETDEWEB)

    DeBlasio, R.; Forman, S.; Hogan, S.; Nuss, G.; Post, H.; Ross, R.; Schafft, H.

    1980-12-01

    This document is a response to the Photovoltaic Research, Development, and Demonstration Act of 1978 (P.L. 95-590) which required the generation of performance criteria for photovoltaic energy systems. Since the document is evolutionary and will be updated, the term interim is used. More than 50 experts in the photovoltaic field have contributed in the writing and review of the 179 performance criteria listed in this document. The performance criteria address characteristics of present-day photovoltaic systems that are of interest to manufacturers, government agencies, purchasers, and all others interested in various aspects of photovoltaic system performance and safety. The performance criteria apply to the system as a whole and to its possible subsystems: array, power conditioning, monitor and control, storage, cabling, and power distribution. They are further categorized according to the following performance attributes: electrical, thermal, mechanical/structural, safety, durability/reliability, installation/operation/maintenance, and building/site. Each criterion contains a statement of expected performance (nonprescriptive), a method of evaluation, and a commentary with further information or justification. Over 50 references for background information are also given. A glossary with definitions relevant to photovoltaic systems and a section on test methods are presented in the appendices. Twenty test methods are included to measure performance characteristics of the subsystem elements. These test methods and other parts of the document will be expanded or revised as future experience and needs dictate.

  10. Safety aspects of long-term dry interim storage of type-B spent fuel and HLW transport casks

    International Nuclear Information System (INIS)

    Wolff, D.; Probst, U.; Voelzke, H.; Droste, B.; Roedel, R.

    2004-01-01

    Based on the German decision to minimise transports of spent fuel casks between nuclear power plants, reprocessing plants and central storage facilities several on-site storage facilities have been licensed till the end of 2003. Because of the large amount of type-B transport casks which are going to be used for long-term interim storage the question of time limited type-B license maintenance during the storage period of up to 40 years has been discussed under different aspects. This paper describes present technical aspects of the discussion. A main aspect of transport cask qualification for interim storage is the long-term behaviour of the metallic seal lid system. Concerning this results from current experimental long-term tests with metallic ''Helicoflex''-seals in which pool water is enclosed are presented. The test series has been performed by the Federal Institute for Materials Research and Testing (BAM) on behalf of the Federal Office for Radiation Protection (BfS) since 2001. Finally, the paper presents a German concept for an authorities' and technical experts' exchange of experience, know-how and state of the art referring to cask dispatch in nuclear facilities. BAM has taken over a central role in this so-called ''co-ordinating institution for cask dispatching information'' (''KOBAF'') which contains an online data base and a technical working group meeting twice a year. The goal is to keep comparable technical standards for all nuclear sites and storage facilities which are going to load and dispatch casks of the same or similar types under the responsibility of different German state governments for the next decades

  11. Why has the continuous decline in German suicide rates stopped in 2007?

    Directory of Open Access Journals (Sweden)

    Ulrich Hegerl

    Full Text Available BACKGROUND: Whereas German suicide rates had a clear decreasing tendency between 1991 and 2006, they increased from 2007 to 2010. Deeper analyses of suicide data might help to understand better this change. The aim of this study was to analyze 1 whether recent trends can be related to changes in specific suicide methods and diverge by gender and age; 2 whether the decrease of suicide rates before 2007 as well as the increase from 2007 to 2010 are driven by the same suicide method. METHODS: Analyses were based on suicide data from the Federal Statistical Office of Germany. For 1998-2010, 136.583 suicide cases of men and women with known age and suicide method could be identified. These data were analyzed by joinpoint regression analysis, allowing identification of the best fitting point in time ("joinpoint" at which the suicide rate significantly changes in magnitude or direction. RESULTS: The national downward trend between 1998 and 2007 was mainly due to corresponding changes in self-poisoning by other means than drugs (e.g., pesticides (annual percentage change (APC ≤ -4.33, drowning (APC ≤ -2.73, hanging (APC ≤ -2.69 and suicides by firearms (APC ≤ -1.46 in both genders. Regarding the overall increase of age-adjusted suicide rates in Germany 2007-2010, mainly the increase of self-poisoning (e.g., by drugs and "being overrun" (APC ≥ 1.50 contributed to this trend. LIMITATIONS: The true suicide rates might have been underestimated because of errors in the official death certificates. CONCLUSIONS: Increase in suicide rates in Germany since 2007 went along with corresponding changes for "being overrun" and "self-poisoning". Copycat suicides following the railway suicide of the goalkeeper Robert Enke partly contributed to the results. Thus, prevention of Werther effects and limitation of the availability of high pack sizes for drugs are of special relevance for the reversal of this trend.

  12. Multivitamin/mineral supplement contribution to micronutrient intakes in the United States, 2007-2010.

    Science.gov (United States)

    Wallace, Taylor C; McBurney, Michael; Fulgoni, Victor L

    2014-01-01

    Multivitamin/mineral (MVMM) supplements are the most common dietary supplements consumed in the United States; however, intake data specific to how MVMM use contributes to micronutrient intakes among Americans are absent from the current scientific literature. This analysis aimed to assess contributions of micronutrients to usual intakes derived from MVMM supplements and to compare those intakes to the dietary reference intakes for US residents aged ≥ 4 years according to the National Health and Nutrition Examination Survey (NHANES) 2007-2010 (n = 16,444). We used the National Cancer Institute method to assess usual intakes of 21 micronutrients. Our results showed that 51% of Americans consumed MVMM supplements containing ≥ 9 micronutrients. Large portions of the population had total usual intakes (food and MVMM supplement use) below the estimated average requirement for vitamins A (35%), C (31%), D (74%), and E (67%) as well as calcium (39%) and magnesium (46%). Only 0%, 8%, and 33% of the population had total usual intakes of potassium, choline, and vitamin K above the adequate intake when food and MVMM use was considered. The percentage of the population with total intakes greater than the tolerable upper intake level (UL) was very low for all nutrients; excess intakes of zinc were the highest (3.5%) across the population of all of the nutrients assessed in NHANES. In large proportions of the population, micronutrient sufficiency is currently not being achieved through food solutions for several essential vitamins and minerals. Use of age- and gender-specific MVMM supplements may serve as a practical means to increase the micronutrient status in subpopulations of Americans while not increasing intakes above the UL.

  13. 14 CFR 417.109 - Ground safety.

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Ground safety. 417.109 Section 417.109... TRANSPORTATION LICENSING LAUNCH SAFETY Launch Safety Responsibilities § 417.109 Ground safety. (a) Ground safety... 417.115(c), and subpart E of this part provide launch operator ground safety requirements. ...

  14. 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.

  15. 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

  16. Reducing Health Services for Refugees Through Reforms to the Interim Federal Health Program

    Directory of Open Access Journals (Sweden)

    Andrew C. Stevenson

    2018-04-01

    Full Text Available Since 1957 the Interim Federal Health Program (IFHP has provided temporary health care coverage to refugees and refugee claimants, but in 2012 the Conservative government reformed the IFHP, reducing, or eliminating access to health services for these groups. The government framed the changes around fairness and safety, stating that it would save tax payers $100 million over five years, reduce incentive for migrants with unfounded refugee claims from coming to Canada, protect public health and safety, and defend the integrity of the immigration system. With a Conservative majority, the reform was easily implemented despite a lack of evidence supporting these claims. In 2014, the Federal Court rejected the government's notion of fairness and safety, ruling that the cuts were cruel and unusual treatment of an already vulnerable population. The government appealed this ruling but, in 2016, the Liberals took power and restored funding to the IFHP to pre-2012 levels. Ad hoc evaluations predicted inequitable and adverse impacts on refugees, negative impacts on health, and increased costs to refugees, provincial governments, and health providers. Overall the threats and weaknesses of this reform clearly outweighed the few and unconvincing opportunities and strengths of the program, leading to its demise.

  17. Operational and safety aspects of vitrified waste casks

    International Nuclear Information System (INIS)

    Kirchner, B.

    1993-01-01

    For the time being two technical solutions have been developed for the interim storage: 1) one is based on forced air cooled pits set out in a concrete structure, as presently provided close to the Vitrification Facilities on reprocessing sites; 2) the other one is based on transportable storage casks standing vertically onto a storage pad, following principles similar to those already experienced with spent fuel storage casks. Considering these two solutions for interim storage, TRANSNUCLEAIRE has developed two main types of transportable casks for vitrified HAW; one is a routine transport cask; the other one is a transportable storage cask. Both are covered by the generic name TN28V and have already been described in previous papers. This paper deals with the safety and operation aspects of the casks under both transport and storage conditions. (J.P.N.)

  18. 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

  19. Validation of a method to evaluate future impact of road safety interventions, a comparison between fatal passenger car crashes in Sweden 2000 and 2010.

    Science.gov (United States)

    Strandroth, Johan

    2015-03-01

    When targeting a society free from serious and fatal road-traffic injuries, it has been a common practice in many countries and organizations to set up time-limited and quantified targets for the reduction of fatalities and injuries. In setting these targets EU and other organizations have recognized the importance to monitor and predict the development toward the target as well as the efficiency of road safety policies and interventions. This study aims to validate a method to forecast future road safety challenges by applying it to the fatal crashes in Sweden in 2000 and using the method to explain the change in fatalities based on the road safety interventions made until 2010. The estimation of the method is then compared to the true outcome in 2010. The aim of this study was to investigate if a residual of crashes produced by a partial analysis could constitute a sufficient base to describe the characteristics of future crashes. show that out of the 332 car occupants killed in 2000, 197 were estimated to constitute the residual in 2010. Consequently, 135 fatalities from 2000 were estimated by the model to be prevented by 2010. That is a predicted reduction of 41% compared to the reduction in the real outcome of 53%, from 332 in 2000 to 156 in 2010. The method was found able to generate a residual of crashes in 2010 from the crashes in 2000 that had a very similar nature, with regards to crash type, as the true outcome of 2010. It was also found suitable to handle double counting and system effects. However, future research is needed in order to investigate how external factors as well as random and systematic variation should be taken into account in a reliable manner. Copyright © 2015 Elsevier Ltd. All rights reserved.

  20. 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.